ML20203B162
| ML20203B162 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 02/03/1999 |
| From: | Terry C TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20203B160 | List: |
| References | |
| TXX-99017, NUDOCS 9902100245 | |
| Download: ML20203B162 (300) | |
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, l'" " ] Log # TXX-99017
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File # 10010 916 R 7t# ELECTRIC- Ref. # 10 CFR 50.90 !
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- c.g w ery- "
s.,,s., we, pmu,,, February 3,1999
. a Frenc(petNucteer opic,r
.w LU. S. Nuclear Regulatory Commission i
LAttn: Document Control Desk" ,
iWashington, DC 20555 I
SUBJECT:
l COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 FOLLOW-UP ITEMS RELATED TO THE PROPOSED CONVERSION !
- TO THE IMPROVED TECHNICAL SPECIFICATIONS
- ' SECTIONS 1,0, 3.1, 3.2,~ 3.3, 3.5, 3.6, 3.7, 3.8, 3.9 AND 5.0
~
REF: : SeS Attachment'1 !
, Gentlemen:
TU El$ctric requested an amendment to the' Comanche Peak Facility Operating Licenses
, (NPF-87 for Unit 1 and NFP-89 for Unit 2) by incorporating changes to th' e Technical Specifications (TS) as' provided in Reference 1. Additional information has been submitted as
- . noted below:
- =1 .The NRC staff requested additional information regarding Section 3.4," Reactor ,
L Coolant System," and Section 5.0,'" Administrative Controls,". which wac provided in !
Reference 2.-
- i .The NRC staff requested additional information regarding Section 1.0, "Use and
'Applice. tion," Section 2.0, " Safety Limits," and Section 3.0, " Limiting Conditions for
.. Operation Applicability / Surveillance Requirement Applicability" which was provided in Reference 3.
The NRC staff requested additionalinformation regarding Section 3.1," Reactivity J Control Systems," Section 3.2, " Power Distribution Systems," Section 3.5, " Emergency
- Core Cooling Systems," Section 3.9, " Refueling Operations," and Section 4.0, " Design j i Features," which was provided in Reference 4.
p; "E .L i The NRC staff requested additional information regarding Section 3.6, " Containment Systems," which was provided in Reference 5.
'm '
- ' . - The NRC staff requested additional information regarding Section 3.3, p 1" Instrumentation," which was provided in Reference 6.
! .1 The NRC staff requested additionalinformation regarding Section 3.7," Plant Systems," ;
which was provided in Reference 7. ;
. i5 SThe NRC staff requested additional information regarding Section 3.8, " Electrical Power
(
E*
Systems," which was provided in Reference 8. s
- Additionalinformation regarding Sections 3.1,3.2,3.4,3.5 and 5.0 was provided in p , L Reference 9.-
f CoMANCIIE PEAK SILAM ELECTRIC STATION war " ^ * ' * * " Glen Rose. Texas 76043 1002 'I' L s 9902100245 990203
@ q. PDR- ADOCK 0 -
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l TXX-98017 Page 2 of 2 ;
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Additional information regarding Sections 1.0,3.4 and 3.6 was provided in Reference 10.
L Corrections to TU Electric response to NRC requested additional information regarding Section 3.8 are provided in Reference 11.
. Additional information regarding Sections 1.0, 3.1, 3.3, 3.4, 3.6, 3.7, 3.9 and 5.0 was
! provided in Reference 12. l l The Attachments to this letter provide (1) additional information or supporting documentation l not provided in the original Request for Addition Information response, (2) answers to follow-up l questions, or (3) additional changes identified by the licensee for ITS Sections 1.0, 3.1, 3.2, l 3.3, 3.5, 3.6, 3.7, 3.8, 3.9 and 5.0.
l.-
l This letter and its attachments are not a supplement to Reference 1. A supplement to !
l Reference 1 will be provided at a later date.
The only commitments contained in this letter are to provide a supplement to Reference 1 at a later date and to provide the load profiles for the modified performance discharge tests and the service tests for batteries after the test procedures have been developed.
If you have any questions conceming the content of this letter, please contact Mr. Bob Dacko (254-897-0122).
i
- l. Sincerely, C. L Terry l
By:
D. R. Woodlan ,
Docket licensing Manager BSD/bd ,
Attachments: 1. List of References
- 2. Additional Information c- E. W. Merschoff, Region IV Mr. Arthur C. Tate J. l. Tapia, Region IV Bureau of Radiation Control Resident inspectors, CPSES Texas Department of Public Health T. J. Polich, NRR 1100 West 49* Street J. N. Donohew, NRR Austin, Texas 78704
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i Attachment 1 to TXX-98017'
. Page 1 of 1 -
References:
- 1) LTU Electric letter, logged TXX-97105, from C. L Terry to the NRC dated May 15,1997
- (License Amendment Request for conversion)
, 2) ' LTU Electric istter, logged TXX-98208, from C. L Terry to the NRC dated September 24, .
' 1998 (Additional information related to sections 3.4 and 5.0)
- 3) J TU Electric letter, logged TXX-98195, from C. L. Terry to the NRC dated August 28,1998 I (Additional information related to sections 1.0,2.0 and 3.0) i 4)' TU Electric letter, logged TXX-98182, from C. L. Terry to the NRC dated August 5,1998.
(Additional information related to sections 3.1, 3.2, 3.5, 3.9 and 4.0)
.(Additional information related to section 3.6) j
.6) TU Electric letter, logged TXX-98239, from C. L. Terry to the NRC dated November 24, 1998 (Additional information related to section 3.3)
- (Additional information related to section 3.7)
<1998 (Additional information related to section 3.8)-
9) TU Electric letter, logged TXX-98229, from C. L. Terry to the NRC dated October 23,~ 1998 j (Additional information follow-up items related to sections 3.1, 3.2, 3.4,3.5 and 5.0)
.1998 (Additional information follow-up items related to sections 1.0,3.4 and 3.6)
- 11) TU Electric letter, logged TXX-98273, from C. L. Terry to the NRC dated December 17, 1998 (Additional information for section 3.8, correction)
- 12) TU Electric letter, logged TXX-98272, from C. L. Terry to the NRC dated December 18, 1998 (Additional information follow-up items related to sections 1.0, 3.1, 3.3, 3.4. 3.6, 3.7, 3.9 and 5.0)
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/ Attachment 2 to TXX-98017J )
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1 The item numbers are formatted as follows: [ Source] [ITS Section]-[nnn) l Source = ' Q - NRC Question i I '
~ NR - NRC Follow-up O'uestion
~
. - CA - AmerenUE
- DC-PG&E i WC-WCNOC-
< 1TR -Traveler !
1 l.' ITS Item Number Appilcability Enclosed
!- 1.0 Q 1.1-1, Q 1.1-2. TSTF-205 - CA, CP, DC, WC YES l- i i- 3.1 CP-3.1-004 (new) CP'- YES 3.1 CP-3.1-005 (new)- CP YES ;
3.1- CP-3.1-ED1 (new) CP YES 3.2 - Q 3.2-6, TSTF-241 CA, CP, DC, WC YES
.t P
3.3 Q 3-LS-GEN. TSTF-135 ' CP YES-3.3 Q 2-13 CP: YES !
3.3 - Q 2 CP: YES ;
3.3 Q 8-04 CA, CP, DC, WC - YES i s 3.3 Q 3.3d GEN CP YES 3.3 Q 3.3.) CA, CP, DC, WC YES 3.3 ' Q 3.3-24 CP,DC YES 3.3 - Q 3.3 CA, CP, DC, WC YES 3.3 Q 3.3-63 CA, CP, DC, WC YES o
'+ 3.3 Q 3.3-73 CP YES 3.3 - Q 3.3-78 s CP .YES 3.3 Q 3.3-96 CA, CP, DC, WC YES 3.3 Q 3.3-97-. CA, CP, DC, WC YES 3.3 - CA-3.3-024 (new) CA NA 3.3 CP-3.3-ED1 (new)- CP YES 3.3 CP-3.3-ED2 (new) CP YES l- 3.3 CP-3.3-ED3 (new) CP YES 3.3 . CP-3.3-ED4 (new) CP- YES' b
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3.3 - CP-3.3-ED5 (new) - CP- YES 3.3 CP-3.3-ED6 (new) CP YES 3.3 CP-3.3-ED7 (new) CP YES
[ ,. ; 3.3 CP-3.3-002 ' CP- YES CP YES
- 3.3 CP-3.3-009 L, 4.
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' Attachment 2 to TXX-98017 Page 2 of 2 ITS item Number Applicability Enclosed ,
3.3 CP-3.3-010 CP YES-3.3 - CP-3.3-011 CP YES
3.3 CP-3.3-012 (new). TSTF-169 CA, CP, DC, WC YES 3.3 - CP-3.3-013 (new) CP YES 3.3 CP-3.3-014 (new) CP YES 3.3 CP-3.3-015 (new) CP YES 3.3 CP-3.3-016 (new) CP. YES _
3.3 CP-3.3-017 (new) CP YES 3.4 Q 3.4.11-4 TSTF-309 CA, CP, DC, WC YES 3.4 Q 3.4.12-7. TSTF-285 CA, DC, WC NA
, 3.4 CP-3.4-005 (new) CP- YES 3.5 CP-3.5-005 (new) CP YES 3.6 Q 3.6.3-23 CP,DC YES 3.6 Q 3.6.3-54 CA, WC NA 3.6 CA- 3.6-ED1 (new) CA NA 3.6 CP-3.6-ED (new) - CP YES 3.7 Q 3.7.3-2 CP YES 3.7 Q 3.7.5-4 WC NA 3.7 Q 3.7.16-3 CA, WC NA
~
3.7 CP-3.7-ED ' CP YES 3.8 Q 3.8.1-20 CP CP YES
, 3.8 Q 3.8.2-02 CP CP YES 3.8 Q 3.8.4-19 CP YES CA, CP, WC
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3.8 Q 3.0.10-01 CP YES Q 3.8.10-01 WC Q 3.8.10-01 CA 3.8 Q 3.88-02.p CP YES 3.8 CP-3.8-005 (new) CP YES 3.8 : CP-3.8-006 (new) CP YES 3.8 CP-3.8-007 (new) CP YES 3.8 CP-3.8-ED CP YES 3.9 - Q 3.9-1a, TSTF-272 CA, CP, DC, WC YES 5.0 Q 5.2-1. TSTF-258 CA, CP, DC, WC YES 5.0 Q 5.5-2 TSTF-237 CA,CP,DC YES 5.0 CP-5.0-ED (new) CP YES
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. ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 1.1-1 APPLICABILITY: CA, CP, DC, WC l REQUEST: CTS 1.3,' Analog Channel Operations Test CTS 1.3, Channel Operational Test [Diablo Canyon]
CTS'1.7, Channel Functional Test [Diablo Canyon] l CTS 1.35, Trip Actuating Device Operational Test [ Wolf Creek)-
CTS 1.36, Trip Actuating Device Operational Test [Callaway]
CTS 1.37 Trip Actuating Device Operational Test [ Comanche Peak]
CTS 1.38, Trip Actuating Device Operational Test (Diablo Canyon]
DOC 1-30-A -
ITS 1.1, Channel Operational Test (COT)
ITS 1.1, Channel Functional Test (CFT) (Diablo Canyon]
ITS 1.1, Trip Actuating Device Operational Test (TADOT)
. 'JFD 1.1-9 ~
L These are changes to both the CTS and the STS and arc considered generic.
Therefore, they are beyond the scope of the conversion review. The DOC states that '
, these changes are consistent with TSTF-39, Rev.1. Also, Diablo Canyon's ITS markup
! appears to be in error as shown by " Channel Operational" versus " Channel Operational Test (COT)."
Comment: If NRC has not approved TSTF-39 by the time the draft safety evaluation is ;
prepared, then these changes should be withdrawn from the conversion submittal at that
- time. These changes will not be reviewed on a plant-specific basis. In addition, correct 1
- the Diablo Canyon ITS markup for COT. j i
FLOG RESPONSE (original): TSTF-39 Rev.1 has been withdrawn by the TSTF. However, )
, . changes addressed in TSTF-39 Rev.1 have been subsumed by TSTF-205. Revision 1 of i
'.TSTF-205 is currently undergoing final review by the TSTF members. After final wording l l '
l changes for the COT definition as well as Section 3.3 Bases changes to establish the
[
e
. requirements for relay contact surveillance testing (issue originally raised at Peach Bottom) are agreed upon, Revision 1 will be ' submitted for NRC review. The attached pages represent the L : definition changes to be. included in Revision 1. The Section 3.3 Bases changes will be addressed under that Section's review.
FLOG RESPONSE (supplement): The FLOG proposes to incorporate Revision 3 of TSTF-205 r- which has been approved by NRC. The only changes required involve the definitions of
! MASTER RELAY TEST and SLAVE RELAY TEST. ITS Section 3.3 Bases changes to relax the requirements for relay contact surveillance testing, which per the traveler may be l L . performed during COTS and TADOTs by the verification of the change of state of a single
. contact of the relay, have not been incorporated.
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ATTACHED PAGES:
Attachment 4,' CTS.1.0L- ITS 1.0 i
Encl 2 ' 1-5 and 1-8 Enci5A Traveler Status Sheet,1.1-4 and 1.1-6 L
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BMMBB!MEEEM9 Fall ,
JER DEFINITIONS utMMEDimetiMe!Il-g usannatfied kERIAGE ,
A1EREWEE'Gegept1llCEse6TDterJMjectiaforelegofEthat&1sLnot idatifl#1LEMMEl cl Pressure Enundarv LE W GE LEMBEgencept3Gl,LEWEEEt$roughlainogisolablefaultUnXRCS1 component _
bownpjpe_malltor;tesselwelu MASTER RELAY TEST
- ' " A MASTER RELAY TEST shall consist."of be-the eneraizinnaben ;f 9 r;gir,g. . .m .,
alla ster reiayscm - . =1.wirea 3rpr channel urtxABILdd , jet-A r N v fyingfeet4en the of OMRA51uiT or eacn requirea master 3 relay. The MASTER 1 RELAY-TEST shall include a continuity check of each associated requiredsslave 1 3o.4
-relay. Thi ItASTER;REEAETESTimaKbeIper_ formed;by;means~ofianyiseri.es:o.f ' o.1.11-te@ntialzgetlapoigoritAta]Istepsj i
1.10 "E"0 ",'S) Of T.
lJSLIC J.nz :n ir.divital in ; cer,tr 11cd er L"",ES",IC'E0 #,, 8-
, . ~ ,
E d, ,
i."C' . llacvtr. ;n indivii:1 i: net a nt;r of tt, p211; iring eny p;ried in '
sid tr.: indivii:1 r;;iva = ac7; tie =1 d;;c.
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0FFSITE DOSE 0'LC' J L^ TIC "'i"J'l 1 om 1.19 The OFFSITE DOSE CALCULATION MANUAL (0DCM) shall contain the methodology and- '! 8-S
. parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by
- Section 6.8.3 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Specifications 6.9.1.3 and 6.9.1.4.
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CPSES Mark-up ofCTS- 1.0 1-5 1/29/99
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MER.lCggBI i M DEFINITIONS 1
r RATED THERMAL POWER IMP 3 h28 a RATElHHEME-POWER shall be a total reactor core heat transfer rate to ...
the reactor coolant of 3411 Mwt. FMed h.
REACTOR TRIP SYSTEM (9551 RESPONSE TIME 1
h29 The RIN "EACT0", " 0YS"fi RESPONSE TIME shall be the time-interval from when the monitored parameter exceeds its lg53 Trip sSetpoint at the channel 1 sensor until loss of stationary gripper coil voltage. The?respgnseiyae;any be . N A , Mx , '
9ttf9(JiesthredjbylAsensIBCKteriesigIsequesttialgovetlapping;Iot: total stgggeistDatQthe ent@re;.responseltimeEis Weejfted seasured.1 In111eu[of 108 A j M@espones31ae tepe;9ettf.ied;forgselected components;'providedjthat 0 1.19 >
thg20gggestslandi.nethodologgggritgatiethavelbeen;prevjousitrevjewed and -
B R M Le p yi4he E I
l'.30 A "E"0"'ASLE C'.'Ch" ; Mil k eny of th;;; ce .dition; ; aificd in 100r"50.73. . l i-3.sA M j SHUTDOWN MARGIN (SDK1 hM SW SHM0WlHERGEN shall be the' instantaneous amount of reactivity by which the reactor is suberitical or would be subcritical from its present condition .1_1-_ M _ M,
" d assuming all rod cluster conko] assemblies Q!CCAQ (;hatde;; ;nd satrol) are fully inserted except for the single 3;CA red clu;ter ;;n.2,1y of highest i
. . reactivity worth which is assumed to be fully withdrawn. iylthJipyIRCCATtfotZeapable GRiERWtfDQy2 inter $5EtM2dB3J1 tim 0t$lC6fithe2HCCAlgDfEhylMcougedforlig gm0$ tat!RiestionArag!Eend BIDD InfMWFKAnd2Ethqual!aglaoderstostemperaternbre3!!bngedKthelhet atM M 4es s tat ges.1 1 MEMi h32 The SIT S00"0A"Y ; hell b; th;t linc ;; ;hr;.;n in figurc 5.13.
SLAVE RELAY TEST
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'1__.30 A SLAVE slave RELAY TEST shall c6nsistTef relatsanmwdnuMTM,.it)Bd7AL3hanntTtir,.R e i uandbe th anarWM"M fCh v ify14;;; tion a murtmu.in oi ead uec3.Lredislaimi relay. The SLAVE
. RELAY TEST shall includef3tB 8pteinlani a continuity check ;; ; ;ini;;;. of 1 3o.4 associated t#qilitied] testable actuation devices. IM SI4yRRELAYJIEST7 day 2be o.1.1 1 MffoN9fdibflllpatislof18nyfsgt@lWJtejlD$tiiT?fget} appM)fitMallstepsM _
-E CPSES Mark-up ofCTS- 1.0 - 1-8 1/29M9
i INDUSTRY TRAVELERS APPLICABLE TO SECTION l'.0 I TRAVELER # STATUS DIFFERENCE COMMENTS i
TSTF 19, Rev 1 Not Incorporated NA1H~12 Esp @ed;9 Not appr;;;d as of tr;;;ler Cut- TR-1.0 004 off data. l e
TS E ;^. R- '
Incorporated 1.1-9 NRC3pprov,edJ ad.. E C pumummmeegl g 0 1,1 1 g I
TSTI-54 Ineerporated h44 mem-mmeum 0 1.1 2 mm TUI-00' IriCGrp07Gied W 0 1.1-9 i ummmmmmmum 15TFh52;"t;Xi; Incorporated 111113, ,
Incorporatsdra chNges;pepHRC g "
en -~ts;9,re,f,t,-, ,,.
,com,w.
=
3 D,3.A?)P14EM"s! " * ,$ . "
TSTF ill, Rev -14 Incorporated 1.1 5 - - - - -
0 1.1 4 mammmmmmme
= 07 Rcv i Incorporated 1.1 6 NJtClapprovedil Ms O m I = -74, R;; 1 Not31ncorporated h44 g Ro1.41 i
4 l- = ^0, Rcv i N_6tZfncorporated 1.1-11 g l Q 1.4 1 1
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1 Definitions 1.1 1.1 Definitions (continued)
All LEAKAGE (except RCP seal water injection or leakoff) that is not identified LEAKAGE: )
- c. Pressure Boundary LEAKAGE LEAKAGE (except SG LEAKAGE) through a nonisolable fault in an RCS component body, pipe wall, or vessel wall.
HASTER RELAY TEST A MARTFR RFIAY TFST shall consis_t of energizing I Cd;ch zwird:1hster relaign uw ui em 1.1 9 l G ,6f sun en.welluPEHetuTAY vertrying 0 1.1 1 tne UttHABIL11T oT esca i,mpareGigastefj relay.
The MASTER RELAY TEST shall include a continuity check of each? associated tequired slave relay. The MASTERIRELAETEST:may;be? performed:by~means!ofiany sergs~off sequenti al riover3 appinglot; totalisteps; MODE A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel, j DPERABLE-0PERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function (s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function (s) are also capable of performing their related support function (s).
h PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrementation. These tests are:
- a. Described in Chapter 13. Initial Test Irvam of ?B-PS4j the FSAR:
- b. Authorized under the provisions of 10 CFR 50.59:
l' or
- c. Otherwise approved by the Nuclear Regulatory Commission.
(continued)
CPSESMark-up ofNUREG-1431ITS-1.0 1.1-4 1/29/99
I Definitions 1.1 1.1 Definitions (continued) t SLAVE RELAY TEST A SLAVE RELAY TEST shall consie af anaroizing T 1.1 9 bect, 7,,,,;J&~6D1 ave rela (ip? (["
fatiteettfe4channebOPERABRm 0111 tie Ort.Matuuir or eacn riwam slave relay. -
The SLAVE RELAY TEST shall include, as a ;;;ini:2, .
a continuity check of associated testable actuation devices. Lhel(IAVEIBELAy3ESEmeEtHL' performed;by means[ofi3g G E jesio_flse g eDtlal E Re.rlappfgl Con totalls_tepjs STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, i channels, or other designated components in the associated function.
THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. l TRIP ACTUATING DEVICE A TADOT shall consist of operating the trip
' OPERATIONAL TEST actuating device and verifying the t_he OPERABILITY gGa))IdevjcesMngthe channel 1.1-1 1 1-9 requiredifgirip;actuatingideyjce!ONRABILITY) s (TET' of r; wired 1EclMis;XCH ai&;Lis Q'i.2 o.
t:;; X e e l a .,,0. q :lar ;. interlad ;.
dispi;yg, ;nd trip functi;n; tsfiefE M E.'G; ttfR_T"~%j~fgG2MO. ]T;5E800Eml$
.-_--- _-,=_ m.__ e_. , m_._m_ w _a m..
.mm ._ u. m
_erme -
n~umv_wwa m wer..m auw.xw-~ ~~ ~~ um N The TA00T shall include adjustment, as necessary, of the trip actuating device so that it actuates at the required setpoint within the necessary regired accuracy. Ihe3 ADO.Esaylb(rperformed).by:means gf3msgiesWfIse@enttalgpyerJappingetit_otal channelEstep,0 CPSES Mark-up ' ofNUREG-1431 ITS - 1.0 1.1-6 1/29/99
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ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 1.1-2 APPLICABILITY: CA, CP, DC, WC ' I
. REQUEST: - CTS 1.3,' Analog Channel Operations Test CTS 1.5, Channel Calibration CTS 1.35, Trip Actuating Device Operational Test [ Wolf Creek)-
CTS 1.36, Trip Actuating Device Operational Test [Callaway) .
CTS 1.37, Trip Actuating Device Operational Test [ Comanche Peak)
. CTS 1.38, Trip Actuating Device Operational Test [Diablo Canyon]
DOC 1-32-A ITS 1.1, Channel Calibration
' ITS 1.1, Channel Operational Test (COT)
ITS 1.1, Trip Actuating Device Operational Test (TADOT) :
JFD 1.1-1
' These are changes to both the CTS and the STS and are considered generic changes. l Therefore, they are beyond the scope of the conversion review. The DOC states that i these changes are consistent with TSTF-64.
Comment: If NRC has not approved TSTF-64 by the time the draft safety evaluation is
. prepared, then these changes should be withdrawn from the conversion submittal at that
' time. These changes will not be reviewed on a plant-specific basis. j i
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FLOG RESPONSE (original): TSTF-04 has been withdrawn by the TSTF. However, changes addressed in TSTF-64 have been subsumed by TSTF-205. Revision 1 of TSTF-205 is
. currently undergoing final review by the TSTF members. After final wording changes for the COT definition as well as Section 3.3 Bases changes to establish the requirements for relay contact surveillance testing (issue originally raised at Peach Bottom) are agreed upon,
- Revision 1 will be submitted for NRC review. The attached pages represent the definition
~changes to be included in Revision 1. The Section 3.3 Bases changes will be addressed under that Section's review. ,
FLOG RESPONSE (supplement): The FLOG proposes to incorporate Revision 3 of TSTF-205
' which has been approved by NRC. The only changes required involve the definitions of
. MASTER RELAY TEST and SLAVE RELAY TEST. ITS Section 3.3 Bases changes to relax tne requirements for relay contact surveillance testing, which per the traveler may be performed during COTS and TADOTs by the verification of the change of state of a single contact of the relay, have not been incorporated. See also the response to Comment Number Q 1.1-1.
- A1TACHED PAGES:
None'
i L ADDITIONAL INFORMATION COVER SHEET
' ADDITIONAL INFORMATION NO: CP 3.1-004 (new) APPLICABILITY: CP j 1
l- REQUEST: - DOC 5-02-M is revised to be DOC 5-02-R.
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ATTACHED PAGES:
Attachment 16, CTS 3/4.10 - ITS 3.1 Enci 2 3/4.10-5 ,
' Enci 3A 3 and 3a
. Enci 3B 2 i
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CPSESMarkup ofCTS3M.10 3N.10-S U29/99
I CHANGE IMBER gitC DESCRIPTION Therefore, because the exceptions applicable to each LCO addressed by [LCO 3.10.4] are no longer required. [LC0 3.10.4] may be eliminated. This change is acceptable because it imposes more stringent requirements (i.e.,
eliminating exception). The elimination of the STEs has no adverse impact on the health and safety of the public.
5 01, R Not applicable to CPSES. See conversion comparison table (enclosure 3B).
Special Test Exception LC0 3.1o 4 "pacition Indication T
.5 02 MR CP 3'1 004 l' System Shutdown" would beM rylocat@ based on relocation of LCO.3.1.3.3, " Position InalcatTng _I Systems Shutdown." NRC application of TS Criteria concluded that the STE LCOs could be included with' corraenandina LCOs remaining in TS and thus LCO 3.10.
- couldubelteJocatedl!!ith LCO 2 3.1.J. g .. . io..g r a m ry.
l Titis:pcoposedgregiatorrelocates2tequirementKwhicitdo not;gingtJshE53!tDag.ano3gWE50DKgag1Eto docuse!Ltaggit3psenesEcagsmangetasta]M s -
- rpm 13Leggag!!!agagnagigmpmIgi!,g[elfsssIn dR9GERIERREEMNIR33NWBDDER$3ED#Jectlye .
h W.8!GEMMERGEREB3RMBt9990MItetpftenents;and
- i opM M @ fjnc M dedM n]ttle lS; Befettielt3!MBREggueGLeningEmms:SheH51to;be m W 1 2itationslupon CAR $3 M E R E N E Rd B D alBR M!IIF_M 3!Idiatelthe i
385$1DtVingitise
- - .- - m e m.
Gatien'ofithe (M@lionI18 pternautanuttmann ul35
. . _ , . . _ . , - _ . _ . . . . . . . . . . . ~ . - . . . . . . . . . . . , . ,
6 t$3%glR03 )310E h g)#*$hatZaty L sejgetmagbettBRE11Lnsstr.mL1mistsstatt!et L 110sebalelMeetsalut!L3eEmis11Etegulatorsontrols l (*19EalREBM1BMBestaRGlinaBIEssuttalligghe msaaniamensmummymesnamaeanto pt!NessJillBIBI12sgre11st.J!aalthlGWtinigrj!ttive CRint10DM319DSBNIE1NptallLdfMM1_deJ!tificat. ion GIlEilmm104RGBlm!!ERootB01%1!!!!QlBEltmoing tt!1cingaguergsgetrigedieraltamorgesIoEtta ICPSES Description of Changes to CTS 3N.10 3 HD/99 d
l l
I I CHANGE Ni)BER NSHC DESCRIPTION l 3 CP 3.1 004 -
)
M M C # 10C8tml h i M U lpo!
tasagig!agum!st!I28!! cool!8d]!ammelWLthKeerent IM!!Nt!MIEla8MB3REME'EBIE1RWNeetlMB 9!aMtima!IBtHEBaR16K1M91GataingM!E4m!urgtbat IDespaigmentempyfM1!ssat!a872Watter32 te3aggiagigrageetten10magKMIERWMLwjapaction salagrmgiggingynarltte migenspee:g3enensJed i parag!!nt3!Ithin'11sttsj l
l I
CPSES Description of Changes to CTS 3N.10 3a 12989
, . CONVERSION COMPARISON TABLE CURRENT TS 3/4.10 - Page_2 of 2: j 6
APPLICABILITYl
~
' TECH SPEC CHANGE ,
NLDGER DESCRIPTION ~ DIABLO CANYON COMANCHEiPEAK' WOLF CREEK CAllARY .
hf5 - Ms- yes. M M TR-3.1-Ol1 pg, g g gggg g g g .
tanstuts:chgewEvimmgaiMutaRterstleiMM9stme FHYSIChTESUhtsthistegihallassQtBMm12 -
Mutsag Special Test Exception [LCO 3.10.4] Seactor Coolant Loops" No - not in CTS Yes Yes Yes -
a- 4-01. would be deleted. This specification allows the suspending -
M- of requirements of one or scre LCOs (depending on plant- !
specific current TS) under certain conditions. ' Elimination of the special test exceptions is , justified either because -
their elimination would be consistent with IEJREG-1431 Rev 1.
4 or because the applicable tests are perfomed only during initial plant startup and are no longer needed. Therefore. ;
because the exceptions applicable to each LCO addressed by.
[LCO 3.10.4] are no longer required.- [LCO 3.10.4] may be eliminated. .
5 01 Special Test Exception LCO 3.10.5 ' Position Indication. Yes - See LAR %-01 No - See CN 5-02-M No - relocated per No - relocated per-R System Shutdown." would be relocated based on relocation of Amendment 89 Amendment 103. '
LCO 3.1.3.3. Tosition Indicating Systems - Shutdown." ' NRC application of TS criteria concluded that the STE LCOs could be included with corresponding LCOs remaining in TS_and that LCO 3.10.5 could be relocated with LCO 3.1.3.3. ,
- - Special Test Exception LCO 31^ " L.M fndication No - See CN 5-01-R Y Jelocated.to h-relocatedper No - bu -l System Shutdown." - would b(releosted C;$= .. ' j Amendment 89 relocat ~
'] MB relocation of LCO 3.1.3.3 -rvui.,u.i m icating Systems - L' .
ed per [
Shutdown." NRC application of TS criteria concluded that Amendue the STE LCOs could be included with correspondina 'N J nt 103. f r_emaining in TS and thus LCO 3. % ]d,befe}ccatsdiwlth ;
/"LCO 3.1.3.34 1: ;; . . . ,._.i.
Y - j 3
i CPSES Conversion Comparison Tame - CTS 3H.10 7/2 M s i a
f
___.m.o m.a_ _ .__.u.i_-__-..w..s ==_._.._________mrm__._.__m___mm..
_.-..__ _._--_s_m. ,m. u ..- __- zu.u._ a..A..r_ -._..m.._
. - ... . . . .. - . . ~ . .- ..
i ADDITIONAL INFORMATION COVER SHEET
. ADDITIONAL INFORMATION NO: CP 3.1-005 (new) APPLICABILITY: CP REQUEST: A change (see DOC 05-02-LS) which incorporates an STS requirement was improperly reflected in the CTS markup. The CTS markup is hereby corrected. The description
- of change (DOC 05-02-LS), the NSHC (LS-7), and the ITS (SR 3.1.2.1) are correct and no
- additional modification is required.
~ ATTACHED PAGES:
Attachment 7 CTS - 3/4.1 ITS - 3.1 Enci2 3/4.1-2 I
l
[
a REACTIVITY CONTROLS SIRVEILLANCE pmlIREMENTS TContinued)-
- c. .When in MODE 2 with K.n less than 1, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior. to achieving qg(gj reactor criticality by verifying that the predicted critical control
~
rod position is within the limits of Specification 3.1.3.6:
, d. Prior to initial operation above 5% RATED THERMAL POWER after each fuel loading, by consideration of the factors of Specification MYY5 4.1.1.1.le.~ below, with the control banks at the maximum insertion limit of Specification 3.1.3.6: and e .' When in MODE 23rtig& TW34, 3 or 4, at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by - ENL '
ca;ider;ti;; cf the f;11 ming f;;ter;.
- 1) "n ter C= int Sy;ts Mrd.. cenc;ntr;tica. XMWh
- 2) Cetrel red p;;iti;;.
- 3) ";nter 0;;1=t Sy;t:7 ;;;r:g; te gr;tur;.
- 4) raci krr.up M;;d en gre;; therr;l :ncr;y ;;ncretica.
- 5) X;ner, sas..tr;tica, ad
- 5) S;nri; ;;;.;;ntr;tien.
- g 4.1.1.1.2 For Modes 1 and 2 only, the overall core reactivity balance shall be cocpared to predicted values to demonstrate agreement within it a k/k oglR Ni$os m'mdk251 t1 st once per 31 Effective
~
Full Power Days (EFPD) .
Thi; :=-rt: . ; Mil /
cadidor ;t in;t tMK fxter; ;t;t;d in Sp;;' . .n..;n 4.1.1.1.1;. . ;M;;. 05 06 A predicted reactivity values sheWgg be adjusted (normalized) to correspond 03.14 @to the actual core condit*ons. m W 9 ;+h., igggpyjggtjpjgr;ge
~
morior to exceeding a fuel burnup of 60 EFPD after each fuel loading.3 MII$D 6 : m Mh M H t!M B N N NH20ste M 05 05 LS J TR 3.1 003 CPSESMark-up of CTS - 3N.] 3M i-2 1/29/99 x .
. _ _ _ - _ _ - _ _ _ _ _ . .h
4 1
1 .
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: CP 3.1-ED1 (new) APPLICABILITY: CP REQUEST: Deletes the descripter " emergency" when discussing boration for one or more rods inoperable in the Bases for Required Actions A.1.1 and A.1.2 for LCO 3.1.4.
The wording may be misleading as the ITS requires "boration" not " emergency boration".
~ ATTACNED PAGES:
.y Attachment 7. CTS 3/4.1 -ITS 3.1
~
Enci5B B 3.1-25 e ')
i
.i T
4 4
h ,q' .
4,'- ,3- i
- Rod Group Alignment Licits
~
B 4:4-5 EE.1 1- . BASES 1
o U* iLCO (continued) -
y _
The requirement.to maintain the rod' alignment to within plus or minus 12' step ' .+ -.c - .e... & u.a.,y J is U = conservative. The minimum misaligr.nent assumed in safety analysis is~24~ steps.(15 inches), and in some cases a total misalignment from fully withdrawn to fully inserted is assumed.
Failure to meet the requirements of this LCO may produce unacceptable power peaking factors and LRs, or unacceptable SDMs, all' of which may constitute initial conditions inconsistent T with the safety analysis.
APPLICABILITY The ' requirements on RCCA OPERABILITY and alignment are applicable in MODES 1 and 2, because these are the only MODES in'which neutron (or fission) power is generated,- and the OPERABILITY (i.e., trippability)-and alignment of rods have the potential to
- affect the safety of the plant. In MODES 3, 4, 5, and 6, the ,
alignment limits.do not apply because the st-d rods are '
tMSa}]g bettened-fgggggged and the reactor is shut down and not producing fission power. In the shutdown MODES, the ,
OPERABILITY of the shutdown and control rod; has the potential to i affect the required SOM, but this effect can be compensated for !
by an increase in the boron concentration of the RCS. See ;
LC0 '3.1.1, " SHUTDOWN MARGIN (SDM)--T,,, 200*T," for SOM in i MODES)258tML,1RESSEB3, 4 and 5 and LCO 3.9.1, " Boron Concentration," for boron concentration requirements during
, refueling.
i
-ACTIONS A.1.1 and A.1.2 When one or more rods are Nntrippable], there is
, a possibility that the required SOM may be adversely affected.
Under these conditions, it is important to determine the SDM, and i if it is less than the required value, initiate boration until the required SOM is' recovered. The Completion Time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is adequate for determining SOM and, if. necessary.
for.init wration end-restoMeg toSaestort SDM.
0 5lD_11 L .: u n .: ..v
..-. (continued)
.a CPSESMark-ngp ofNUREG-1431 Bases - ITS3.1 B 3.1-25 1/2939
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 3.2 APPLICABILITY: CA, CP, DC, WC
- REQUEST: ITS 3.2.4 - Quadrant Power Tilt Ratio CTS 3/4.2.4- Quadrant Power Tilt Ratio (All FLOG Plants)
DOC 04-01-A -
JFD 3.2-05 ITS Required Achon A.5
~ " Calibrate excore detectors to show zero QPTR," to " Normalize excore detectors to eliminate l tilt," based upon WOG-95 (and rejected TSTF-25). A preferred wording would be that proposed 1
- in the Comanche Peak CTS mark-up, " Calibrate excore detectors to show zero Quadrant . !
. Power Tilt." What is status of WOG-957. j u l FLOG Response (original): Traveler WOG-95 was transmitted to the NRC in February 1998. l j
as TSTF-241. The FLOG is incorporating TSTF-241 including the latest revisions discussed at the June 1998 WOG MERITS Mini-Group meeting.' These revisions corrected errors made l
during the development of TSTF-241. ;
- Additionally, Wolf Creek submitted a License Amendment Request to CTS 3/4.2.4, Quadrant ,
. Power Tilt Ratio, on February 4,1998 which was approved on April 27,1998 in Amendment No. !
116. This amendment incorporated the changes proposed in TSTF-241.
]
l The FLOG believes that it is appropriate to incorporate the proposed TSTF-241 changes based on the NRC approval of the Wolf Creek amendment request. l l
FLOG RESPONSE: . (supplement) The NRC and the Technical Specification Task Force have agreed upon the acceptable changes to be included in this traveler. Most of these changes
. were incorporated into the FLOG submittals in the initial RAI response as noted above. The
. final set of needed modifications have been incorporated as noted in the attached pages.'
FLOG Response (supplement): This response is being supplemented to correct editorial
' errors made in the inserted text for Bases 3.2.1, Actions A.2 and A.3. Additionally, TSTF-241, j Rev. 4 was recently issued and is believed to be the Revision to be approved by the NRC. ,
' Revision 4 had been accurately reflected in previous FLOG responses. The Traveler Status
. page is only being updated to reflect the issuance of Revision 4.' l LATTACHED PAGES':
Encl. 5A1 - Traveler Status Sheet Encl. 5B - B 3.2-5 and B 3.2-Sa
.y P"
- ~,
INDUSTRY TRAVELERS APPLICABLE TO SECTION 3.2 TRAVELER # STATUS DIFFERENCE # COMMENTS TSTF 24 Not Incorporated NA Not NRC approved as of traveler cut off date.
TSTF 95 Incorporated 3.2 06 Approved by NRC TSTF 97 Incorporated 3.2 07 Approved by NRC TSTF 98, Rev. 21 Incorporated 3.2 03 TSTF 99 Incorporated 3.2 08 Approved by NRC TSTF-109 Incorporated 3.2 15 Approved by NRC Incorporated 3.2 10 "'"
TSTF 110 Rev. 23 Approy d by_NRC l .2 004 isamma-TSTF-112. Rev. 1 Not Incorporated NN9122.0 "Ct ""C GPP,T{Cd 2-1
%5 ep %# 5 nr 5 %5 W b 5 El cut-off dctc.
APPE0 Vet by M Cfl Applicab]eltoiCAOC plantsE(CPSESlonly)
TSTF 136 Incorporated NA Approved2by1NRC l m.: .2 004 TSTF 164 Incorporated 3.2 11 Applicable to CAOC only. (CPSES)
'0C ^'. prepoccd Mjfidd.Ja! @
~
. Incorpomi.ed 3.2 05 26 "cv. 2 IS((EFA)
, 3.2489 egr_eed;uporj J 312121 diLring32!17/98 meet 1Ebetweeni and NRC Wes40s :r5corprcted was o.u 2s l l
I:
I
. . - .- . . - - --_ - . - _ . ~ _ . . -. -. - _ _ _ .
Fo(Z) (Fa Methodology)
B 3.2.1' BASES -(continted) l 4
ACTIONS- M Reducing 114ERMAL POWER by 2 it RTP for each it by which Fj(Z) exceeds its limit, maintains an acceptable absolute power density. Fj(Z) is Pd(Z) multiplied by a factor $3hgg account 4ng for manufacturing tolerances and measurement uncertainties.
Pd(Z) is the measured value of Fa(Z). The Completion Time of 15 minutes provides an acceptable time to reduce power in an
. orderly manner and without allowing the plant to remain in an unacceptable condition for an extended period of time. The o.3.2 6 2
antinuslallegable3cterilevel;initiaUrdeterminediby; Required '
AM1oGEastatstatfjecteoresde!!eretnationet fa4ZM an mdM ir g u piposeriteducggM3tthK152mistesaf
-thle Fa'q)1dstggget_1g;11f3peessetyltoIccePllygft[the decreased enximurallemste3mwarasyrgogcreasesiinLFa1Z1 l
~
woMd;aUnG!Lcj!stDgithelgakfadelaUeWeblOoner3evel;and i increa.sigenerlupitehjs1redsedHisin U
A reduction of the Power Range Neutron Flux-High trip setpoints by 21% for each it by which Fj(Z) exceeds its limit, is a conservative action for protection against the consequences of !
severe transients with unanalyzed power distributions. The Completion Time of 8 Zg hours is sufficient considering the small likelihood of a severe transient in this time period and the preceding prompt reduction in THERNAL POWER in accordance with Required Action A.1. MMggMK1 stet 0ltsi)plfgeutror) 0 3.2 6 ElwENicir*Nampeglgstyymeg1M AjGk&ML :==3aun ____ - -=M*So!
f/G)?4MdRMm!BB2HiHighitr,1p MIM10EiB2BBC11BBERBMmREEDMEBBB fa4DDine111A8 Mon?
HBiltetHINGdEtLERI le Power)
RaiBr E BIB W M B B N Ea* Q %
mnenem omwarnemaem EERtEMaltRPEggplE25]
u Reduction in the Overpower trTNM6 trip setpoints by 2 it for each 1% by which Fj(Z) exceeds its limit, is a conservative action for protection against the consequences of severe transients with unanalyzed power distributions. The Completion Time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (continued)
CPSESMark-up of NUREG-1431 Bases-ITS3.2 B 3.2 1/2989
-. . - .. ~. . . . - _ .- . .. . -
Fe(Z) (Fo Methodology) i B 3.2.1 i
L _ BASES (continued) l l 1s sufficient considering the small likelihood of a severe transient in this time period, and the preceding prompt reduction in THERMAL POWER in accordance with Required Action A.1. M 'glggjgg; m 0-3.2-6 f
l Ma '. i.. - . 2)B IM EeW1_ WlUO!!. ~
l t8tR$JfA!!8!99!!!aOSERtlyisisg!!mgs131!mRhours ;
l otthe E/QBigetsj!!!LtMElf3tecesfgyXJosp1Mthithe l degee8e81agenta11ogable;cesamig; top;;setpointsa Decreases 11g f/GDoQlOlWJncreating;theleax;inum_0verpower E161tdp;se! Mints l
bd I Verification that Fj(7) has been restored to within its limit, by performing SR 3.2.1.1 prior to increasing THERMAL POWER above the limit imposed by Required Action A.1, ensures that core ,
conditions during operation at higher power levels are consistent !
)
l l
l l
l l
i (continued)
J CPSESMark-up of NUREG-1431 Bases-ITS3.2 B 3.2-Sa 1/29M9 l
I-
- __ _. - - - - . - . _ - __ - . -~
I
\ ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3-LS GEN APPLICABILITY: CP REQUEST: TSTF-135 changes Comment: TSTF-135 was rejected except for the traveler changes identified by the following justifications: DOC 3 which deletes STS Condition V for two inoperable trains; DOC 4 which makes changes STS T3.3.1-1 Note (b); DOC 5 which deletes Source Range Flux for Applicabilities in T3.3.1-1 with Note (f); and DOC 7 which deletes Intermediate Range Flux for Applicabilities in T3.3.1-1 with Note (e). Revise the submittal to delete all other TSTF-135 proposed changes.
FLOG RESPONSE: This traveler was discussed during meetings with the NRC staff during the week of August 10,1998. The attached pages represent changes, including revised DOCS and JFDs, that we believe are acceptable to NRC. These changes are marked with the change code "TR-3.3-006" since the majority of these mark-ups were self-identified and pre-date the RAl. Mark-ups are based on TSTF-135 Rev. 3.
FLOG RESPONSE (supplemental): Revised Bases to be consistent with TSTF-135 Rev. 3.
ATTACHED PAGES:
Attachment 9, CTS 3/4.3 - ITS 3.3 l
1 Enci5B B 3.3-8 and B 3.3-49 l
l
)
i
. . _ . . .. - - - . - ~ . - - . - - - - . .-
RTS Instrumentation
./ g , B 3 .3 .'1 BASES .
APPLICABLE even with a random failure of one of the other three protection SAFETY ANALYSES, channels. Three operable instrumentation channels in a' _ ,
LCO, and two of three configuration are generally required when there is APPLICABILITY no potential for contrni system and protection system interaction (continued) that could simultaneously create a need for RTS trip and disable one RTS channel. The two-out of three and two out of four configurations allow one channel to be tripped orjq)pespid cP 3.3 009 during maintenance or testing without causing a reactor trip. Specific exceptions to the above general philosophy exist and are discussed below.
Reactor Trio System Functions The safety analyses and OPERABILITY requirements applicable to each RTS Function are discussed below:
- 1. Manual Reactor Trio The Manual Reactor Trip ensures that the control room operator can initiate t reactor trip at any time by using either of two reactor trip switches in the control room. A Manual Reactor Trip accomplishes the same results as any one of the automatic trip Functions. It is used by the reactor operator to shut down the reactor whenever any parameter is rapidly trending toward its Trip Setpoint.
The LCO requires two Manual Reactor Trip channels to be OPERABLE. Each channel is controlled by a manual reactor trip ell _tch] "dJ
@. s.;;M. ; witch. Each channel activates the reactor trip breaker in both trains. Two independent channels are required to be OPDABLE so that no single random failure will disable the Manual Reactor Trip Function.
In H0DE 1 or 2, manual initiation of a reactor trip must be OPERABLE. These are the MODES in which the shutdown rods ,
and/or control rods are partially or fully withdrawn from the core. In H0DE 3, 4, or 5, the manual initiation Function must also be OPERABLE if the--ogeIoKnore l TR 3.3 006 ll shutdown or control rods are withdrawn or the Cor, trol Red Driv; 'CRO) Bgi;ControT& System is capable of withdrawina the shutdown rods or the control rodGC,_
Cd;~;;rM m t.x;t: Gin Inis conciuon, inaavertent control. rod withdrawal is possible. In H0DE 3, 4, or 5, manual initiation of a reactor trip does not have to be OPERABLE if the GRO RodLControl System is not capable of withdrawing the CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B3.3-8 1/29/99
RTS Instrumentation B 3.3.1-BASES-nwherminianamshamtsalmsrmamunamenshouwkundne accomplishes the interlock's Functica. The Completion CP 3.3 ED1 Time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is based on operating experience and the minimum amount of time allowed for manual operator actions. The Completion' Time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is reasonable, based on operating experience, to reach MODE 3 from full power in an orderly manner and.without challenging unit systems. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Completion Times are equal to the time allowed by LC0 3.0.3 for shutdown actions in the event of a complete loss of RTS Function.
T.1 and T.2 Condition T applies .to the P 7. P 8, P 9, and P 13 interlocks.
With one:oritore channe1[s), inoperable? fu en; cut ;f-ta; cr two cut ;f f;ur ;;incid=;; logic the assriated interlock must be verified to be in its required state for the existing unit condition;by^ob_servationlofithelpermissive: annunciator; window within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or the unit must be placed in MODE 2 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. These actions are conservative for the case where power level is being raised. Verifying the interlock status manually.
accomplishes the interlock's Function. The Completion Time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is based on operating experience and the minimum amount of I time allowed for manual operator actions. The Completion Time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is reasonable, based on operating experience, to reach -
M00E~2 from full power in an orderly manner and without challenging unit systems.
U.1 and U.2 .1 =d U.2.2 Condition U applies to the RTB Undervoltage and Shunt Trip Hechanisms, or diverse trip features, in MODES 1 and 2. With one of the diverse trip features inoperable, it must be restored to an OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or the unit must be placed in a MODE where the requirement does not apply. This is accomplished by placing the unit in MODE 3 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> total time) f;11;=d by spning th; P,Es in 1 ;dditien;i h;ur ,
(55 heur: t;tel tin ). The Completion Time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is a !
reasonable time, based on operating experience, to reach MODE 3 l from full power in an orderly manner and without challenging unit -l
' systems.
With the PsH : eg n ad th; unit in MODE 3 this trip ranctim i; n; 1 = ;;r r;;; ired tc b; 0"C"X LELCondition?Clis lTR3.3006 efftaredqff 7 ~=6ipTBreaWLTitt;1 Mbechan1W 1 C 6 4 .a = R t* JTimu43nd2Lmuodgoinol pysten 1sieppab100CNidNithdemarcnonem note 2gramotifu11y :
irf$ertediepp}ieeble.. The affected RTB shall not be bypassed while one of the diverse features is inoperable except for the time required l CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-49 1/29/99
m . . . ~ _ _ _ . _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ . . _ _ . _ _ _ _ _ _ . . _ _ _ _ .
I j:
ADDITIONAL INFORMATION COVER SHEET ,
' ADDITIONAL INFORMATION NO: Q 2-13 APPLICABILITY: CP f i
REQUEST: This Functional Unit [ CTS 10] is moved to ITS 3.8.1.
b Comment: - {CP} The CTS markup is deficient. Actions 25 and 26 which apply to the ;
SSSS are not included in the Rev 0. Provide the appropriate pages and justifications to 1 complete the package. Justify each proposed change to the CTS,
{CP} Actuation instrumentation testing is proposed for ITS Section 3.8.1. This is d contrary to ISTS format which includes sequencer operability with DG operability in
- Section 3.8.1, but sequencer testing is limited to functional tests associated with LOCA/ LOP testing. Revise the ITS to adopt the ISTS format and bring sequencer instrument loop testing back into the instrumentation tech specs if LOP and LOCA l ' testing is not otherwise sufficient to demonstrate operability. Justify each proposed l- change to the CTS. Note that CTS require channel calibration at refueling and TADOT at 62d staggered testing.
FLOG RESPONSE (revised): Item (1). The formal transmittal page of CTS 3/4.3-30 was incomplete. The complete page will be included.
Item (2). The CTS Table 4.3-2, Functional Unit 11a. and 11b Channel Calibration, performed with a refueling frequency, is captured within the requirements of ITS SR 3.8.1.18. The required TADOT, with its qualifying notes, is currently perfoimed with a monthly frequency. ;
This TADOT, and its qualifying notes, will be moved to the newly created ITS SR 3.8.21. These !
changes are administrative in that, consistent with the ISTS format as described in the Comment, all sequencer requirements are retained, but are associated with DG operability and, hence, are moved to the specifications associated with the DG. The ITS markup of SR 3.8.21 will be revised to reflect this philosophy.
' ATTACHED PAGES:
' Attachment 14 - ITS 3.8 - Electrical Power Systems Enci5A 3.8-15 Enci5B B 3.8-31 Enci 6A - 6a Enci 68 7a 4
^
4 1
i
AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS -
SURVEILLANCE FREQUENCY
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e, REFERENCES- 1. 10 CFR 50, Appendix A, GDC 17.
7 4
- 2. FSAR, Chapter 8.
- 3. M
-.-__,'~MTuL.Z j ",egulatory Guide 1.9) BF,;33u]y299).
CP 3.8 005
- 4. FSAR, Chapter 6.
(continued)
' CPSESMark-up ofNUREG-1431 Bases -ITS3.8 B 3.8-31 12989
l CHANGE leeER JUSTIFICATION !
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. CPSES NUREG-1431 Differences -ITS 3.8 - 6a U29/99 t
v -
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. CONVERSION COMPARISON TABLE ITS SECTION 3.8: 7e of 7 NUPBER - DESCRIPTION -l Diablo Canyon Comanche Peak Wolf- Creek Callaway 3,8-R IbejeoMgtoAs3surye1Maggggettmspritttspitbe,nodjfled fetiloaseeJFD Tes- yes in DLusimithem;ggsjgentJt11llimtrsquitsmentsj 3318 53 3.841 l&pA.DAActimWAshusestauldedO94tpotatoAIS Noh W t partloftCTS Mon Not.patt of. QTS l80 - Igg requLrementsfapplicab1,2 t olt!!agloss;ptom.9fttheibuses 0-3.s.E -4y thetisapplyale._ctiticalismatdodluksanenttaJmcejsatet antana 32 8-g igillaCreelkss3AaMaimmimaEEmadiEmogatdsedifet M No ye4 IM s o.3.8.4 17 E IlmiAIREtantesLWatansignisstaqRLantorJiaLtetLcaneGity hM sutve111 sultic M s .
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5 CPSES Conversion Comparison Table -ITS3.8 1/29M9
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 2-32 APPLICABILITY: CP REQUEST: These changes affect the ACTION STATEMENTS for inoperable undervoltage
' or degraded voltage relays. For all trip functions, new statements are added which require that the diesel generator, which was made inoperable by the inoperable undervoltage or degraded voltage relay, may be declared inoperable in lieu of entering LCO 3.0.3. If the number of OPERABLE channels per bus is less than the Required Number, one hour is now allowed to restore the channel to operability before compensatory actions are required.
Comment: The one hour time period to restore at least one inoperablie channel to operable status (LCO 3.3.5, Actions B.1, C.1 and E.1)is moot when the altemate action to place the plant outside the applicability is within six hours of entering the condition.
Restoring a channel to operable status is always an option, albeit in the first or the sixth hour.
The Required Action D.1 one hour time period to restore one channel to operable status is inadequately justified. Retain CTS requirements to declare the affected bus inoperable immediately.
I FLOG RESPONSE: The 'a ges to TS 3.3.5 that were agreed upon during the September meeting are reflected in the response to JFD 3.3-131. The LS-23 will be revised to discuss the safety significance of the change from entering LCO 3.0.3 to entering the action statements for an inoperable DG.
FLOG RESPONSE (supplemental): Revised NSHC LS-23 to change " channel" to " bus" ATTACHED PAGES:
Attachment 9, CTS 3/4.3 - ITS 3.3 Enci 4 51 f
e
, - n- .. ,., . . -r,
l IV. SPECIFIC NO SIGNIFICANT HAZARDS CONSIDERATIONS NSHC LS 23 r 10 CFR 50.92 EVALUATION FOR L
l TECHNICAL CHANGES THAT IMPOSE LESS RESTRICTIVE
! REQUIREMENTS WITHIN THE TECHNICAL SPECIFICATIONS The ESFAS loss of power undervoltage and degraded voltage relays are intended to detect a condition where the offsite power supply is either unavailable or is !
insufficiently stable to allow safe unit operation and initiate the sequences to l shed the loads on the safeguards electrical busses (when appropriate), start the diesel generators, and load the busses onto the diesel generator. If one of these relays was inoperable, the principal effect is that, in the event of a loss or degradation of offsite power, the affected diesel generator would not be successfully started and supplied to the appropriate safeguards bus: in other words, l the effect would be the same as if the diesel generator were inoperable. In the i l
structure of NUREG 1431. Rev. 1., any subsequent actions required by the Technical Specifications would be made in accordance with those specifications concerning diesel generator operability.
The proposed changes affect the Action Statements for inoperable undervoltage or degraded voltage relays. For all trip functions, new statements are added which require that the diesel generator made inoperable by the inoperable undervoltage or ;
degraded voltage relay be declared inoperable, in lieu of entering LC0 3.0.3. In addition, one hour i allowed to attempt to restore the channel to operability ,
before thera [fect bus ~ s~ declared;1nop6tablelandXurther, compensatory actions _ l0232 '
l are required. The one hour compieuvn u.c J ~.. .;;c^.; c;p e ti;c :c rg,c;r ; cst fcilurc; cr.d takes into account the low probability of occurrence of an event during the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period which would require the diesel generators to start on loss of offsite power.
Illsammut 11stantecariternalnapalungemtemthane2ntMMicRTcentinued N G tf iti g !! NcMical
,r.mhve rtwarn'-a 3 err.maammamemamarummw EBEMMEEMNNME 3MC8amereffect1.h N j88el TN.Mt.h3hg 6mmm mm 818POMM e rm. - mmen- -r semawan-mu eff ht Cen3ggp_ T Tplgtj tr#5 mammaammmmmmmweMansanentenemmentmuersammaanneinnummametw
/ > > . wD% RM M101Nft1hgitM IBMIRBMagmiditiej!gD13g!m3mmagtsugggggLORM!I The proposed TS change has been evaluated and it has been determined that it involves no significant hazards consideration. This determination has been performed in accordance with the criteria set forth in 10 CFR 50.92 M) as quoted below:
The Commission may make a final determination, pursuant to the procedures in 5.0.91, that a proposed amendment to an operating license for a facility licensed under 50.21(b) or 50.22 or for a testing facility involves no CPSESNo SignifIcant Hazards t'onsideration - CTS 3N.3 51 H29/99
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 8-04 APPLICABILITY: CA, CP, DC, WC l l
REQUEST: Consistent with NUREG 1431, Rev.1 (ITS 3.3.3 Required Actions C.1, E.1, and I G.1), this change deletes the requirement to initiate an alternate means of monitoring within f 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when two channels of containment radiation level (or RVLIS) are inoperable as >
specified in current TS [3.3.3.6 ACTION c].
Comment: What is the basis for deleting the requirement to initiate the attemate method of monitoring in the case of containment high range radiation monitoring? The NSHC indicates that this automatically happens in the case of RVLIS, but implies that PASS monitoring of the containment is not initiated under condition G.
FLOG RESPONSE (original): NSHC LS-17 has been revised as per the attached.
FLOG RESPONSE (supplement): NSHC LS-17 has been further revised to provide examples of instrumentation available to detect inadequate core cooling.
ATTACHED PAGES:
Attachment 9, CTS 3/4.3 - ITS 3.3 Enci 4 43 5
4
.. - - - . - - ~~. - . _. - - - -. . - -. _ - - -.. . . - - -
IV. SPECIFIC NO SIGNIFICANT HAZARDS CONSIDERATIONS NSHC LS 17 l 10 CFR 50.92 EVALUATION FOR tTECHNICAL CHANGES THAT IMPOSE LESS RESTRICTIVE REQUIREMENTS WITHIN THE TECHNICAL SPECIFICATIONS I l
Consistent with NUREG 1431 Rev.1. this change deletes the requirement to initiate the preplanned alternate method of monitoring containment radiation [or reactor vessel water level] within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when two channels are inoperable. This makes ACTION [33] of current TS LCO [3.3.3.6] the same as ACTION [32]. except that a plant shutdown is not needed if the 7 day A0T is not met for these functions with preplanned alternates. Containment radiation indication is used to assess whether the fuel cladding and reactor coolant pressure boundaries have been breached such that a significant portion of the core activity inventory is available'for release to the environs.-[ ] The preplanned alternate for this variable uses the PASS system which is administratively controlled outside the TS.YImplemergationlof a'8'04 -
6IMrisamplitisivji gbO3)MK)eitgitjptedlas' req 01reOyIIT5"3J3:3 l WBBttamOMhereftOoIsafEOWLlefEt0Eac_ttvatjngLthe2ASSNdieGthan )
ggtgl1Mf16enditienL63 44" Trwh'4mHedMwNm" tnt ]
a.mIEpotelexit3hermoccupiesOCSJiridePange l l MJeSitemperatutWcWjgeTr==="hae***"nr**=erizerleve1Pand Qt@pb%1ggluepjMin@cationsFjT.The preplanned alternates for RVLIS include a como1 nation vi se wr= mt thermocouples, RCS wide range hot and cold leg temperature, wide range RCS pressure, pressurizer level, and RCS subcocling monitor indications to verify adequate core cooling.] These variables are airaady continuously monitored under the LC0 and do not require an action directing that they be initiated.
The proposed TS change has been evaluated and it has been determined that it involves no significant hazards consideration. This determination has been performed in accordance with the criteria set forth in 10 CFR 50.92(c) as quoted below:
"The Commission may make a final determination, pursuant to the procedures in 50.91, that a proposed amendment to an operating license for a facility licensed under 50.21(b) or 50.22 or for a testing facility involves no significant hazards consideration, if operation of the facility in accordance with the proposed amendment would not:
- 1. Involve a significant increase in the probability or consequences of an l accident previously evaluated; or
- 2. Create the possibility of a new or dif.ferent kind of accident from any accident previously evaluated; or
- 3. Involve a significant reduction in a margin of safety."
The following evaluation is provided for the three categories of the significant hazards consideration standards:
CPSES No Signipcent Hazards Consideration - CTS 3N.3 43 1/29/99
l l
l l
l
' ADDITIONAL-INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 3.3d GEN APPLICABILITY: CP REQUEST: Generic JFD Comment
- Section 3.3.1 Comment: The allowable value and trip setpoint of the reactor coolant low flow function (function 10) should be explicitly stated as a percentage of minimum measured flow perloop.
FLOG RESPONSE (original): ITS Tables 3.3.1-1 and 3.3.2-1 have been revised as required to ;
include the appropriate units of indication.
FLOG RESPONSE (supplement): The units for Reactor Coolant Flow - Low have been i revised and a Bases description provided to clarify the meaning of the units. !
ATTACHED PAGES: j Attachment 5, CTS 2.0 - ITS 2.0 Enct2 2-6 Attachment 9, CTS 3.3 - ITS 3.3 EnctSA 3.3-18 Enci5B B 3.3-20 and B 3.3-20a l
i
k ~A>" -~
~
TABLE 2.2 1 (Continued) ._
REACTOR TRIP SYSTEM INSTRlMENTATION 1 RIP SETPOINTS FUNCTIONAL UNIT TRIP-SETPOIM ALLOWABLE VALUE clis ig s .'.'.x ;. M
- 8. Overpower N 16 2112* cf "T"' 5114.5% of RTP* g
- 9. Pressurizer Pressure-Low
- a. Unit 1 E1000 psig 21863.6 psig
- b. Unit 2 'E1000 psig 21%5.2 psig
- 10. Pressurizer Pressure-High
- a. Unit 1 22305 pais- $2400.8 psig
- b. Unit 2 22305 psig 52401.4 psig
- 11. Pressurizer Water Level-High $ 2% of $93.9% of.
instrant sp;n instrument span
- 12. Reactor Coolant Flow-Low
. a. Unit 1 E^0* cf instrant 188.6% of instra..;
span span G,caism:.twfiqq 0-3.3.d-GEN
- b. Unit 2 r^0* cf instrant 288.8% or astra..;
span spongig,3. g oon:Cg(
- RTP = RATED THERMAL POWER CPSESMarkup ofCTS2.0 2-6 . 1/2989
RTS Instrtmentation 3,3.1 Table 3.3.1 1 (page 3 of 9)
- Reettor Trip System Instrumentation
- APPLICA8LE MODES f*te S ECIFIED REQUIRED SURVEILLANCE ALLOWA8LE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE'*l 1 8. Pressurizer I
-Pressure
- a. Low 1'd 4~
M SR 3.3.1.1 4686 ;^^! , :;
SR 3.3.1.7 $3863'.4 ' u B-PS Mn i
- SR 3.3.1.10 psig l
= !.:.t.10 (Unit 1) l 61865.2 peig ,
33.3 55d (Unit _2)
- b. High 1,2 4 E SR 3.3.1.1 ,2596 4 !!0"; ,,... 7 g.pg 7 SR 3.3.1.7 ( 2400.8 SR 3.3.1.10 pelg 0 3.! .1. % (Unit.1)
K:2401A pois n3.3-55 m - l (Unit 2)
- 9 Pressurizer Water . t i" 3 M SR 3.3.1.1 95:6 s-9iMt e^ ggpg'c :.,
~~
. Level High SR 3.3.1.7 193.95of SR 3.3.1.10 instrunwit 0 3.3d GEN span l
l
-10. Reactor Cootont 89:2
' v3:3C i Flow - Low- SI e.g' EB-PS**al
. : , ,, ; . ;.,,,,,, 1N 3 per- NN SR 3.3.1.1 tesyJ mm t-905 ,
loop SR 3.3.1.7 US) j SR 3.3.1.10 0 3.3d GEN
% *, . . t . %
mgj RSM:W t ;, . - L .,,,, 4" 5 per M ; 3. .1.; 89:2 3-90N W : '
b?. E323 :42a
.m .,.,.,.i.
(continued)
(a)f ",,..:...."; %.;.. J. , l ; ., . ; l l ; ; ,,'. .-, , . . ; ; - ,,_, . . ; . ! , , . ' , ^. ". '. -.L ; e k'e ' _
. . -f-- , -- J . , ,, .o ,. ; ,,,, , , ,;
B3:3s08fi
^ ;-, - .;,,,J.1 , -.J Li ;',4 - !;. Mf6TIMiB;~JhgD(MMMfsNo,$tJm s (th4 V . , M MM l (g) Above the P 7 (Low Power Reactor Trips Block) Interlock.
I i,H, , ^.r - n.. . ^, if ., i_; ,m. ,. ..., ~'.,',F, ,.-i.
. .. ;".h. ,d - ' . _ _ , . . _. .
t 3.3-42 A l
L+ *
.. ICPSES Markup ofNUREG-1431 - ITS3.3 3.3-18 _ 1/29M9 E - - p
. _. ._ . _ __ ._ . ~ _ _ _ . _ _ _. __ . _ . . _ . - _
i RTS Instrumentation B 3.3.1 BASES level. channel failure cannot cause the safety valve to lift before reactor high pressure trip.
In H00E 1. when there is a potential for overf1111ng the pressurizer, the Pressurizer Water Level.-High trip )
must be OPERABLE. This trip Function.is automatically J enabled on increasing power by the P 7 interlock. On '
decreasing power, this trip Function is automatically blocked below P 7. Below the P 7 setpoint, transients that could raise the pressurizer. water level will be slow and I the operator will have sufficient time to evaluate unit l
' conditions and-take corrective actions.
- 10. Reactor Coolant Flow-Low
- s. R :: tor Cociant fic;;--Low ' Sin;1: L;ce) CP.3.3 009 The Reactor Coolant Flow-Low ' Single. Le;O trip Function ensures that protection is provided against violating the DNBR limit due to low flow in one or more RCS loops, while avoiding reactor trips due to l normal variations in loop flow. 4t!oEthelPM l NAMLeByectoGdp"EloERg! Melt (or, m3.3.nz 40rJALEagosts21szam.omat1911mpategzed WAdmLhirMniMinGEEG30' MOT sumslwsA EUI~i.itOtC C I G n 2 J M Above the P 8 setpoint. .;hi;h is .-4 existely 40% R" a loss of' flow in any RCS loop will actuate a reactor trip lit!!!B0f!dalliitheschtsfipcDoggegaMHhelteta!
6,mc;. 6. gtgMgijgggB. Each RCS loop has three flow detectors to monitor flow. The flow signals are not used for any control system input.
EDEllWQgGBRERWIKfM3RRBlSIEWt!8le]
mt Y1H M 99 M MEDEM2EEI91Bunglig BRSBIIRRRRBBBlutNt3RDEBASETE15390med3n MtssgegegMCAR1GLM.*===esithtMIFatual B-shEatgideg alGBMiiME21UtiveI!GREAleGBit1DgithantM EiMENDRmaltsagntfitsisgantstatW9EtloR UBBBIRitahMahfDelWJMQWBBORJ!el1EIM JtgplDIJEllldjgt(
1BAtt1910grmalB!sttTheW11mNg1RhelRCSROEtlM Mt@iotDxpt'eMMAWtuntJgstiindjMted mg
'CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3 20 1/2989
. . . . . ~ - - . - . -. .- ... .-- . . . . - . .- .. ~. -
N RTS Instrumentation i B 3.3.1 BASES' 4
0 3.3.d GEN O(3 . J : t. 3 E. s.l.f . 6 3 l FiEEEEEEElg1RgggtssengglF;jl$Et1Elmp! gel 815Nt3RRIBORLMIMMMtgittew.1glEWlthe acc1gussetusto -
1 .#
The LC0 requires three Reactor Coolant Flow-Low channels per loop to be OPERABLE in H0DE 1 above EN CP 3.3 012 In H00E 1 above the P 8 setpoint a loss of flow-in one RCS loop could result in DNB conditions in the core bestyseIofithelhjgheripower3 e9el. In H0DE 1 below the P 8 setpointiandlaboveitt@71setpoint, a loss of-flow in two or more loops is required to-actuate a reactor trip (runctica 10.b) because of the lower power level. and the greater margin to the design limit DNBR. Be]Mithe' PRitetpointKalliteactot;trj ps on;1w10Nlarslautpmaticall.y; bloc!gidisince~;there;1s ingfnciemheatiptoduction3orgegratelDNB
- conditings]
- b. next:r c=12 rioW - L W 'TW: Lax Th; R;nter 000lxt il;W-L;W 'TWO Leep;) trip funtien n;;r;; th;t pret;;tica i; presid;d ;ge.ia;t viel; ting th; 000 li;it du; to 1;W fl;W in tWe er
.er; RCS inp; whil; ;;;iding r;;;ter trip; dx to
, aeral v;ri;ti n; in 1;;p fl;W.
CP 3.3 009 1
w
- CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B3.3-20a U29/99 1
- i. .
l l l
i 1
ADDITIONAL INFORMATION COVER SHEET 1
l ADDITIONAL INFORMATION NO: Q 3.3.] APPLICABILITY: CA, CP, DC, WC
- REQUEST: ITS Section 3.3.2, Notes to Required Actions G.1 and H.1.
Comment: The note allowing surveillance testing in Actions G and H allow bypass of a train for any surveillance test. The existing condition [23] only allows bypass of a train specifically for testing per j specification 4.3.2.1. This excludes bypass for CTS 4.3.2.2, response time testing. This relaxation i is neither noted norjustified in the CTS markup.
- FLOG RESPONSE (original): DOC 1-66-LS-45 has been developed to justify the inclusion of response time testing during the bypass of an inoperable channel or one other channel for DCPP and CPSES.
- FLOG RESPONSE (supplement): Based on a telecon with NRC staff on January 20,1999, NSHC LS-45 has been revised.
ATTACHED PAGES:
Attachment 9, CTS 3/4.3 - ITS 3.3 Enci 4 66a l
(
i IVjISfECIFIEN07SIMIEICEIMZARDSICONSIDERAIIONS 0 3.3.J UEEllEiiE men o uni Epnnsy t yyg i N i W M REGI M ATIW S TMfw;changeM1digleteltlIpeferencjitrJRecifigatjoJ1U.12and13;2;13q tilR3BB!b41sRessa!i!stsIcontaineCEWttMatstymI0ltstatementszthus:permittinazagy te!RtwateededMelastorMiogr ofzthe2!@petatyltzchanneir*TheIcISXa11owsIcertain i
itlopEsbleicliannelszetIforiscentpJantsIoneIotegchanneMtolbe; bypassed;forLtestjng;per i I
spg!ficatic003;1;13t13Z1g1Teielintentipfftheibypastisitolallov a testj%that will i getsfreatatheIchanne11has;bestrestorsd;to!ilE05MBIEfconditjenfandican;belreturned l l t!alstricenwallomstbypass;twatitesugothantpoenleyalosted;forutsijapact;onitte !
sajpKanMFlies1TSL1asibeen3fetetejnedithetit!!!DepactiofitheZallowedibypassesfAs ,
E1999slR4iett!8tithefjppa.sslisRot[setpoint7Wetificationiorrreennnes time? verification j hagMJispecticOtheT$afetyianalWeineJypesAsurvejllancesl performed;ur .
i l Mcessoignewn3 3; Required]ActionlNotesXareinotJ11mitediby;WCAP 10271; or21_ts I supp}ementsEWCAPfl0211.Tandlitsisupplements"sade1 assumptions;onJthe<totaliduration an l analogZehanneEis; bypassed'per3earifor.le_ sting;2Thosefassumptions;on testing:jn bypas Willnotibe2 exceeded;htthelproposedichange? -
TJyje proposedKchangelhasibeenlevaluatedfglit]hasibeenIdeterminedittjatiitti.nvolyesino significantLhazardsrconsidetatlonglhis;deterjnination:haslbeen;perfotsedlin;accordance With"theIctitettalsergorthAtn301CSL50192(cEas31 doted;belog l
KhgTCcntnissfgilnqQgakeBGfine]LdeterminatLoggpRrsubnt%toLthelptocedures311 l @l91Ethat:8 ph0po$jiRQn!006 gent ((bie.nM8t!D9':LLtgnseitor y facj]fty:1) censed l UDdeCM21]bE%RM%foGaLtest]f(acjyt2lpg]yesino:slgnfffcant hazards MLderatMmulmezatjwamtheptmtrinRctordance:with: theyproposed 26tS~htjoilldLhoty l D znvgignisjtgnitLcantiggriate21 nut @Zgcattb11ttylommsmuencgEof art ac;cidengTgce11@1]Dnigteen 2] QLedtd3tllEposs*Ib1HtyjgtidBunl9tWdiffe^ refit kindrof?dccidentif@ Lag K31detstelms]DD1Lismm y zago)yt11tgnifitantitygtidrr'inwargg9fMa_fe.ty13 f Tj!JNollWing;B?aluat16Lis'providediforitheIthreiE&palels ofit_hejignificant;ha_zards cggiarelstandanisJg 1] DoesitheXchange,1javolvelaltjgnificentJjncteaselinEtheXprobability;g genseguenceslofianzaccident 7previously; evaluated!
OgetAlCptotectionIgyMeg2petfor!!LapM1Xr_emajgIWithin1thelbound_szoCil}q prevjeLus1rpettormedlsecfdentfinelMs3J@Mherdweteichingefere]ptoposed4 CPSES No Signi)Icant Hazards Consideration - CTS 34.3 66a in9/99
I ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 3.3-24 APPLICABILITY: CP, DC
)
REQUEST: Changes improved TS Table 3.3.4-1 to reflect current TS (3.3.3.2.11]. Deletes references to " controls" in the table (see also CN 3.3-94) and changes " Required Number of Functions" to " Required Channels" since the Table has been revised to include only instrumentation.
Comment: TSTF travelerrs required for deviation from NUREG-1431 unless justifieo by design. Table column header " required channels" does not agree with LCO statement. ;
Revise Table 3.3.4-1 to adopt STS format for conformance to " separate condition entry for !
each function."
FLOG RESPONSE: For CPSES, ITS Table 3.3.4-1 column header is revised to maintain the NUREG-1431 wording," REQUIRED NUMBER OF FUNCTIONS," as discussed during the August 14,1998 meeting. Additional changes to ITS Table 3.3.4-1 are made as discussed at the meeting.
For WCGS and Callaway, after further discussions with Operations personnel, the ITS Table 3.3.4-1 column header is being maintained as " REQUIRED CHANNELS." Maintaining this wording is consistent with other ITS Section 3.3 tables and with CTS Table 3.3-9. Maintaining the column j header as " REQUIRED CHANNELS" is not in conflict with the LCO statement I with the additional changes made to the Table to identify the specific instrument as a function and i each function requires only one channel to be OPERABLE. Maintaining the column header potentially prevents a confusion factor when other ITS Section 3.3 tables have the same function listed and specify the number of required channels whereas ITS Table 3.3.4-1 would specify a required number of functions. Additional changes to ITS Table 3.3.4-1 are made as d:scussed at the meeting.
FLOG RESPONSE (revised): For CPSES and Diablo Canyon, the ITS Table 3.3.4-1 column header is being revised to " REQUIRED CHANNELS," for consistency among the FLOG (i.e.,
WCGS and Callaway) as suggested by the NRC staff reviewer during the telecon on January 7, 1999. The use of this wording is consistent with other ITS Section 3.3 tables and with CTS Table
! 3.3-9.
For Diablo Canyon, the title of Table 3.3.4-1 is being revised to " Remote Shutdown System," and associated text is being revised.
ATTACHED PAGES:
L Attachment 9, CTS 3/4.3 - ITS 3.3
- Enct 2 3/4 3-52 I
Enci 3A 21a
! Enci38 19 EnctSA 3.3-52 Enci 6A 3 Enci 6B 4 h
~ - . - . - . . . - . - - . _ . _ - .- - . . .
TABLE 3.3 5 7 01 A REMOTE SHUTDOWN HONITORING INS"L"*Et"' TION o.7 01 E
7 01 A Q 3.3 24 REAB06 TOTAL NO. GENNEES OF-GMNNEES "" ' " L N LOGAHON
!!WIRET LS CHA.NN.Ey' HSP 0 1
.1. ' Neutron Flux Monitors HSP UEeep 1/ Loop
- 2. . Wide Range.RCS Temp.-T,
' 3. Wide Range RCS Temp. T, & W 1/ W p' 1 1
.;4. Pressurizer Pressure HSP HSP- 0 1
- 5. Pressurizer Level
.HSP WSG 1/SG 6.. Steam Generator. Pressure HSP WSG 1/SG
- 7: Steam ~ Generator Level tlE .
B/SG 1/SQ
' Auxiliary Feedwater Flow- HSP Rate'to Steam Generator H e-hs e 1 0 7 10 HSP "9.- Condensate Storage Tank Level' 110. Charging' Pump to CVCS. HSP 1 1 Charging and RCP Seals -
Flow Indication
- HSP = ! Hot Shu' tdown Panel
. SG : = ' Steam' Generator- r
. vu s__.4----- m, ~' " , m . 4 ._ ru.-- i . noco noi e <-
uu- o .- ore v---
'y 31 31 g g
"" l J: .a... '. '.' 2, ., ~u, ..I'.J , _
. . ._. Z. ._;.;".'.
, . . "". ' .'~L.
I..~e . .. l ~'", Z.' "'. ,i,~"f'
- ,'._".~ J. . .w,
.'. T r ., s..' '1, u, , ~;
.~
i
' f;;r '4' "00 Leop ;. Thi: .Trei;ien is t; i;r.;in in effect until 0"SES Unit 2 cat;ri"00C 4 ;t the b;;innia; cf th: :;;;;nd refueling ;;t;ge for Unit 2.
W
' 3M 3-52 M989 CPSESMarkinp ofCTS 3M.3
. . . - - . . -~ .. . .. - - -
L l
CHANGE R&BE8 J6E DESCRIPTION N3R!citigtMn]lfww33 l 6 4heglE M J N iae 9 ffs 0 B M 5 3 !ista t est M t*3n!MtGER!IRBMpJ5BLnits!agistgeaI2gMtticat.$ons MED!lulRGt818tDlhan08D!rE1mmKleL*1;1%is3tH!BesM N 19]
4 01 R Not applicable to CPSES. See Conversion Comparison Table (Enclosure 38).
~5-01 R Not u_ sed 3pplicabic to C"SES. Sec Con.crsion C @ cri;0n Teble 'Enclesurc 2"'. oc n 004 01 R Not applicable to CPSES. See Conversion Comparison !
Table (Enclosure 3B). l l
7-01 A The requirements of current TS fable [3.3 5] are 0 7 01 redefined on a functional basis., with Required C4cancis EunctioDs, rather than on a per channel basis, consistent with gtheriSectjon?.3131 Tables;in1NUREG 1431 l03.324 Rev.1. The point at which the ACTION Statements are entered is unchan LS.0PERABL
_uen;headerjforzatHsiteviseditG"REQUI_REDiCHANNELS"-
consigent3_lthigher))S.,_Section13;Iables]
2 l l
1 21a 1/29/99 CPSES Description of Changes to CTS 3N.3
CONVERSION COMPARISON TABLE - CURRENT TS 3/4.3 . Page 19 cf 22.
TECH SPEC CHANGE APPLICABILITY NUPEER DESCRIPTION DIABLO COMADIE WOLF CREEK CALLAWAY CANYON PEAK 5-01 R m,. - ..v C" 3.3.0.3. Sci;;ic Instr ~ .^.; tion, i; rclecated to ; li
..a;
{Af ; 0;;
m, ~ , , ,
M(ANe 2 M/ANe g' g
Me 6-01 DCPP LCO 3.3.3.4. Neterological Instrumentation. is relocated to a licensee Yes - See No No No R controlled document. Attachment 21, page 13.
7-01 The requirements of current TS Table [3.3 5] are redefined on a functional basis [ .ir ;dy -- Yes Yes Yes A with Required Leagglicos Ch------!- The point at which ACTION Statements are carrent TS.yeg 0 7-01 entered is uncha6'lJ4NIEN,5sts,mmcgyptpoederDt js i M99htRaLREggBEAQLRltELS.*,4WatsgsmitltletMLITJ. ject _1CATables a - M 3~N
(
W _
7 02 The shutdown requirement for inoperable Remote Shutdown controls is changed from No - already in Yes No - already No - already in N HDT STAIOBY to HOT SHlfTDOWN. current TS. in current current TS.
TS.
7-03 Pet ',al. I!MgqSEEgM&MggetygBgMgqLlg;thpitsmotoJwtdown transfet N/A No N/A Yet IWA M N/A M pultchessaglglIggglsMEucyektoh8asesg s
g g,74 g LS 7 04 This change extends the Remote Shutdown A0T from 7 days to 30 days. No - already in Yes Yes Yes LS-15 current TS.
7-05 Consistent with the ITS the modifications would clarify the requirement to be Yes Yes No - already No - already in A in HOT SHLITDOWN in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by replacing the requirement with a new requirement in current current TS.
to be in HOT STAND 8Y in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHlfTDOWN in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. TS.
7-06 The Readout Location and Total No. of Channels coltens in current TS Yes Yes Yes Yes E LG Table [3.3 5] have been moved to the Bases of improved TS 3.3.4. {-} l Q-7-0C" "
7-07 Pat u;cd.isonth]y;CHNGIEtaCHECKdsiaddedator37S; Tablem 4.3:6uRCP breakers; N/ANo N#NQ N/Ayeg y 7-08 The CPSES requirement to submit a special report if the ntaber of remote No Yes No No TR-2 shutdown monitoring instruments is less than the required number would be deleted from the CTS. This requirement is covered by other regulatory requirements.
CPSES Conversion Comparison Table - CTS 3M.3 U29A>9
I Remote Shutdown System 3.3.4 Table 3.3.41 (page 1 of 1)
^'-- - ' * ^ '- ~
Remote Shutdown System * ^- -
_u,_ ,_ __ ,,, _~_-,__ _ __ _ . _ , . . ,, , _ _ _ _ , _ _.. ,_
_ . . . . , . ._a..,..__.
.. ,__-_._w_ ,w,_ _ __
_a u_ _,r,____...,.
,....,.,u.-. .. .. -. . . . . . . . . . . ~
.,_v,_..- .. . . . - , . , . ...
REQUIRED .""""'" 0" "'.C FUNCTIONHNiiHIMENF
- p. 0-3.3 24
. n.
32 er 0;.rx "..r.,; Neutron Flux Montters 1 or . ___ t___.
n_ _i__ ,_ _ n__ __
. - . . . . ., . . . _ .__n._._2.2..__.
. . . . ,~. ._2.,_
., _ ., n__ - ,.,_
. . - . . . . . . . . . . .r 2 c n_
- i. e.. . . .1 n___i..__ e.__s..__.i. . ,. . ..i.._._
. - . . . . , . s ne
~ ,e....-..
s .
22 a. Pressurizer Pressure 1 ,
< .s.,.,. m.2._ n. i.. .y.
. n s...
3e n____ n_. A____A_J n_
....1. -..L_
i__ _._A
_1_.- ..i...__... .....-
1.,.._s. u.._1... s..__ na.n.u. .aL.t.
.L. r .e . ..
. ........ . __. s m..... .
e _A__1 J _
s nA.n.u. s .
- g. . p i..e.. .i r n
. 1. ._,_.1n u.._1..._.. P__.A._.1e n_ _ , , _ _ . n___.._, . . , _ r ___ ._ _
.. ...., . .. .._ ... ... . . . - ._.-...___-6Get ...
M er RCS Hot Leg Temperature U.pedoop B be RCS Cold Leg Temperature 1"pedpop H er "J'.' O.. '.r;h ;d Condensate Storage Tank 1 tevel E Ed SG Pressure Elegg Me SG Level 1:peC56 3.3 24 8" Q 3.3 24 g AFW Flow l~ ped 6
- m. n.,..
)
N ; er Pressurizer Level 1 i l
RJ br Charging Pump Gentee4e KDEX2ergigGW X l E s ae n t D K inttsatlee l
CPSESMarkup ofNUREG-ID1 - ITS3.3 3.3-52 in989 4
J CHANGE 1 ID BER JUSTIEICATION ;
3.3 23 Modifies ITS Surveillance Requirement 3.3.4.2 to include power circuits per Current TS 4.3.3.2.2. This change.is made to match the plant design which includes transfer switches for power circuits as well as control circuits.
J 3.3 24 This change revisp 4=pmved TS Table 3.3.41 to reflect current TS [3.3.3.2.1]. Q 9 ate C f-Meals tgjegiops' 3 gt; deletes ,
references to " controls" in the taole] (x; ;1sc CN 3.3 ^.,4). and !
ch;ags T; quired Nu;ter 0; ;sacticas" to 0 quired Ch;anals" sirce the t;bl; ha ban raind t; includ; only instra..tstica. [ThCcolung header 3!gSHRED;lRDEIEll"8. ER31CTIONS*Atsireyjgg@3EglIRED.iCHANNELS: '
consistegtlw1DI.t!theGU5] Sect 19);3231 tab]M3nd3tithlCM1TattleE3W5.2 Revj singitolumKt!anderstpifijEjQlRRED_CHRIEIEL5"lis3QtMt:enflict[with l thell.O!tateneig1Rjgige?AddjMogallchangeslande30lthalabl0to ;
Ldentifntheispecif1Giftstatant.iasTa;tunegapa e raird, the t;bic is acw ;;rcist;nt with the fenet of the othcr t;bles in ITS Section 3.3 ITS :ad is t;;hricelly the =: :s the current TS req @nt .
3.3-25 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B).
3.3 26 Not applicable to CPSES. See Conversion Comparison Table ;
(Enclosure 68). ,
3.3 27 This change modifies SR 3.3.3.2 and SR 3.3.3.3 to allow for different i surveillance frequencies for the hydrogen monitors then other PAMS components. 'The manufacturer for the CPSES hydrogen monitors specifies a more frequent calibration frequency than required for the other PAMS
. instruments. The more frequent calibration is required to assure function operability.
3.3-28 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B).
3.3 29 Not applicable to CPSES. See Conversion Comparison Table
-(Enclosure 68).
3.3-30' Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B).
3.3 31 The current TS require the response times associated with the
[undervoltage and degraded voltage diesel generator start functions and the] containment [ ventilation] isolation functions to be verified against the specific response time values contained in the [TRM]. The ITS is revised to match the current TS and the response time values are
[ Ntained in the TRM]. As is done with the Reactor Trip System and the ESFAS instrumentation..this method is an appropriate way to control response times. [SR 3.3.5.4 and SR 3.3.6.8] are added to require the response time verification.
CPSES Differencesfrom NUREG-1431 -ITS 3.3 3 12/18/98
CONVERSION COMPARIS0N DBLE FOR DIFFERENCES FROM NUREG-1431, SECTION 3.3 Page 4 of 22 TECH SPEC CHANGE . APPLICABILITY NLABER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 3.3-20 . 2d;d n;t; 2 n [ Cont;i.-..t h; C;dictica 0li#. ";. :;;)]
VesN/A VesN/A VesN/A VestjgA c; lib ;tica i- !TS *." [3.':.3.':] to b; _ ai;t at .;ith
- - . ..t "; T;b h [4.3.3.3.5 fc;tnot;]. Notused 3.3-21 ITS 3.3.3 was revised to reflect current TS 3.3.3.6. No - see CN 3.3-71. No - see CN 3.3-70. Yes (see Ar.endment Yes (see ULIEC-3023 Containment Isolation Valve Position (and Notes) and No. 89) dated 5-20-94 and Condensate Storage Tank Level were deleted. [ Combined the Amendment No. 103 power and source range neutron flux entries into a single dated 10-20-%)
neutron flux entry.] Consolidcted the Thermocouple / Core Cooling Detection System entries. Changed number of required channels for RCS temperature to 2 for both hot and cold leg temperature. Changed Containment Pressure Wide Range to Containment Pressure Normal Range and added Refueling Water Storage Tank Level. Steam Line Pressure, and SG Water Level (Narrow Range) Functions as these are current 15 requirements. Changed the required number of channels for SG Water Level (Wide Range) And AFW Flow Rate frou 2 per SG to 1 per SG and added corresponding notes to Conditions A and C.
3.3-22 Consistent with current TS [3.3.3.5]. [RC" tra k r Yes No - not in current Yes Yes indication i; cxch.d:d frc; C".".""CL C"CC"! ad [ reactor trip breaker and RCP breaker indications are excluded from]
TS.
lQ-3.3- d CHANNEL CALIBRATICNS in ITS SR 3.3.4.3 since these SRs have no meaning for [these] functions.
3.3 23 CPSES-specific change that modifies ITS Surveillance No Yes No No Requirement 3.3.4.2 to N 1ude power circuits.
3.3 24 Changes impro TR Tahb '114-1 to reflect currEr.t TS -
S := C., Yes Yes Yes
[3.3.3. . _stedjnstrumentat 6ngs;FJsnctions_ana 1 3.3 103.Yes [0-3.3- 24 l es refer.mces to " controls
- in the table. [Thecol n -
" REQUIRED1 NUMBEf(OFAEUNCUG55*sisJgvised i to N lREQUIREDplANNELS* consistentMtlLothqtdJESection,3.3 tablpstandaitfLCTS 2 Tabler3;3-h] ';u cuc = 3.3 04) =d N _ ~ . . .f. .~lNN. - E..~9.~m.
E. m mm .m 3 6. 2.-~m3N._I.
m .~ , _m G r _ ..t tion CPSES Conversion Comparison Table -ITS3.3 1/29/99
I
' ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 3.3-55 APPLICABILITY: CA, CP, DC, WC REQUEST: Revise ITS SR 3.3.1.16 and SR 3.3.2.10 to verify " required" response times,
' ~
accommodating those channels that have no response time requirements per the current licensing basis. [As such, line-item references to these SRs in Tables 3.3.1-1 and 3.3.2-1 can be deleted. A similar revision to the ITS 3.3.6 SR Note has alsc been made regarding SR 3.3.6.8.] .
Comment: Reject - The ITS proposes generic changes to the STS by deleting '
i SR 3.3.1.16 for applicable functions in T3.3.1-1 and modifying SR 3.3.1.16 that are not included in an approved TSTF.
Adoption of WCAP-13632 for eliminating selected sensor response time testing requires staff review independent of the Conversion TS review.
TSB management sees no benefit to making this change because the proposed STS -
format introduces ambiguity in identifying TS required testing. Additionally, this change is generic and the staff has not received a TSTF request to review these changes. Bill
. [Beckner) notes that the staff is Yaty sensitive about changes to response time testing requimments and although the staff approved moving response time lists to owner-controlled documents, elimination of TS required RT testing requires a TS amendment in either the old STS format or in ISTS. .
FLOG RESPONSE (original): Based on meetings with the NRC held between September 15 and September 18,1903, Diablo Canyon will also be taking this change. The Note preceding ;
the Surveillance Requirements in ITS 3.3.1 and 3.3.2 has been modified and the wording in ITS j SR 3.3.1.16 and SR 3.3.2.10 has been revised to cite the licensee controlled document where the response time limits are contained. In addition, surveillances originally modified under JFD l 3.3-31 will be revised to be consistent with the changes to ITS SR 3.3.2.10 since the affected surveillances measure ESF RESPONSE TIMES.
For WCGS, JFD 3.3-55 is now being adopted in its entirety, which also results in their adopting JFD 3.3-31.
FLOG RESPONSE (revised): Based on a telecon with NRC staff on January 12,1999, the
' FLOG will adopt the STS wording of SR 3.3.1.16 and SR 3.3.2.10 and will emulate that standard wording in any additional response time surveillances adopted as a result of converting the CTS to ITS (e.g., Callaway SR 3.3.5.4 and SR 3.3.6.6 will not reference the
' FSAR). ITS Tables 3.3.1-1 and 3.3.2-1 will be revised to cite the response time testing surveillance only where it is required by the current licensing basis. Where not required by the current l' censing basis, SR 3.3.1.16 or SR 3.3.2.10 will be struck-through, as applicable. The SR 3.3.1.16 and SR 3.3.2.10 Bases have been clanfied regarding some Functions (e.g.,
ESFAS Safety injection) for which the licensee controlled document containing the response time limits must be consulted to ascertain testing requirements. For example, not all circuit paths fed from an SIS (e.g., CCW start and turbine trip at Callaway) have response time testing requirements. Since this is a revised response, the attached pages include all changes from
. the original response for which NRC approval is requested.
. . . - . - . ... . .--.. - . . . - - . ~ . . . - ... .. . . . , . . ..- . . . .
H !
+. !
H ,
<\',
ATTACHED PAGES: ,
j; .
.y Attachment 9, CTS 3/4.3 -ITS 3.3
- Enci 2 3/4 3-1 and 3/4 3-17.
Enci 3A 1a ;
EnciSA 3.3-11,3.3-15,3.3-16,3.3-17,3.3-18,3.3-19,3.3-32,3.3-33,3.3-34,3.3-35,,
3.3-37,3.3-39,3.3-40,3.3-41,3.3-42,3.3-56,3.3-56a and 3.3-60 :
Enci5B B 3.3-50, B 3.3-59, B 3.3-60, B 3.3-116, B 3.3-120a, B 3.3-121, B 3.3-169 m . and B 3.3-172 M Enci6A' 3 and 6 Enci 6B . 6 and 9 .
1 V
L l.
c s + + , +. - e
3/4.3 INSTRUMENTATION 1 63 A 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION Q 1 A GEN
[ .
LIMITING CONDITION FOR OPERATION i
3.3.1 As a minimum, the Reactor Trip System instrumentation channels and i
interlocAs of Table 3.31 shall be OPERABLE. i c .
l
, ~APPLICABILITY: .As shown in Table 3.3 1. ,
i 1 e
ACTION:7] )
As shown in Table 3.31. 1
, i SURVEILLANCE REQUIREMENTS 'l 1
i l
~4.3.1.1 Each Reactor Trip System instruicentation channel and interlock and I the automatic trip logic shall be demonstrated OPERABLE by the performance of the Reactor Trip System Instrumentation Surveillance Requirements specified in Table 443 1.
?-
4.3.1.2 Th[;gcdCTOR TRIP. SYSTEM RESPONSE TIME of each' Reactor ]03.355 77 trip function snan be dc ~n;tr ted ver.ified to be within its limit at 41,g
' 'y i
least once por 18 months Ion;a STAGGERED M ._ BASIS (**. Cach tcst shall )
include et icest enc train ;uch that both train ;rc tc;ted et least once 'l per 30 renths and era chenrel par furetion such that all chenacis c.rc tcsted i et ic ;t once cycry N ti;;;c; 10 r.enths whcra N i; the t;tel nus:r-ef I redund:nt chonncis in ; :pc;ific "ccctor trip furetion s shown in the _ _ _
" Tot:1 N . ;f Ch;nacis" cela;;;n of T;bic 3.3-1. [1902ELGM i
'3 Sepaf, ate AClI K egt g lsIal,Jo@jdiforJgach_i[ unction)j 4141?AV4
- 2*
, N_Ligt.Ioglan[N1161detectArga!3;tec10dedfftceltespggseltimeltfstjng? T02klGh4 i
l i
l lJ k .
yr s t j ,
CPSESMarkup ofCTS3M.3 3M 3-1 in989
INSTRUMEKTATION SURVEILUJiCE REQUIREMENTS 4.3.2.1 Each ESFAS instrumentation channel and interlock and the automatic actuation logic and relays shall be demonstrated OPERABLE by performance of the ESFAS Instrumentation Surveillance Requirements specified in Table 4.3-2.
0 3.3 55 4.3.2.2 Th rQ:j,QNGINEERED SAFETY FEATURES RESPONSE TIME of eacn
. ESFAS function .woil ue i .e sst ated verified to be within the limit at " I#D m
least J_.1..J, once .&
per 18 monthsE.
1 m . A. _- &_.J.
.a;SInn_.BASISf.'&-
...L &L.L L AL & J .- -_
A J"a d test .&
shall 1_..& -_--
sasuswww ub sbudb va m be u aaa duwe s bs ru b vu bi n bs u a s sw un w kwahuu ub iwwwb vi sww g. .,o3
_-_ *1 f --.-AL. .J __- .L._--1 . . _ _ f.. &J._ ....L AL & .11 mL.__-1. ..
W Mt yws vv suv a i bs s a us su vs sw ws sus as au s yws 4 us sw b a va s wwws i bs su b uau wssusurw ia us %
& _ ., & J & 1.s.& .... _-- kt &J--. in _-_AL. ..L.__ kt J. &L- _.._L._ mt bwdbbu ub swudh vr tww ywa si b s pN J Av usuvs s bi s a .rs aw s w su ud b535 &v_bus& .1a suus-w a vs
. J.. J._& .L . _ _ - 1 . l_ . ._--JsJ. Perae t.. .LJ._ .. .L-.- J. AL- *T A.1 kl . _t 3 svua ruus a b ws suu H tw I e aai u dyww 5 B iw wvs os a us tw b g vs I us w s svvvi a ain bstw svbua s yv . Vi e t . _ ._ _1 , = __1..- _t T.L1 - e e o vs sus si rw i a vv s urin a v4 sumuw w.w s. .
4 TLJ- J_ J. aus. J J &m n _-_AL s ,A sovisksi f-_
. . . . .ws
.* J 1 1 .a ss s_mw-s ai s ,
._JL eus e A. _-_.J J_
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_ _., __. b.us,,i s .. LL_
&m w-ws .uvu
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_, Lu_
i v.
,____J = 1 31-A vs a e b s, by a wsuu 5 I e aie wsawwb us Ib s i bssw wvury a w b a vi a vi b5 N ww w visu
__,.._,J__ ... .__ ,__ n ,-_ .L. ,,,_..J__ ,..__hJ__. ._J s W s uw a s a sy vubuyv s vi ,via
,_ JBa,, s. , e us ., s N i V savuseisy s us sw b vi sd usIV J&J.LJ _ 1..
J. sssbsu .J,-_
s vi s es , su s e .
e.s.m rreeet nL .. aan v _ a . .m J 1 P . J. . . & _
s u s w b,. . v.Jsm .aw m&w J. w-_s a wm,, 5 s s s .m o . v 1. u. A J. s,. m.m s , 4sul. ,. . , mu u bes
._J r _ _ _ _ _ _ _ . . n J _ . _1 e-_-_.&__ ru . _ a. J . . . - r= & J__- & n__...__
ussu unN s yws twJ viwdus wwi tw B ubus vyk s u b i vs a vss uvs s b u i a suurve I b 8 i wJdui w oJ_ , n___..._J s e s, ,u, .. same3 sms a s w.s us b n__,..__ , _.
hv .
._J us.u e, . _
- w..s
, J__ n__-..__
wss~ . s meus w bewt r__& J_--_& e__...n..__ __ r__& J____& n__.... oJ_L , . -_J uvs e bu a s suruss s b vys u) s unry vu s uvi s be s a usswa s b s a wJJul w s I i ys a A, ut au TL, .. s..
ss .~ s un ~ s v. B.
&J-_.
. 4 E L. _..__ __
s s s wrva ses b a s,~ . & J _ . ., ..L4_L i s a wa s us w s ,
J_J&J.&
s i s. s u wwu J
L ,. . t m .s
.t n-..._ If ntAf ._J A n ru f e. ,--..._J. e . .. & _ l t_ J - - . . 1 & . _a vs a vvvws g v . s r% ussu 7vvy vu l wyuus uJ VJ a buns vi suw s v u s buyw / .
8 No..t r. equi _r.e. d:to_be~. perf_o_r..med ff_o.r
. _ . - ~ t..he_turbin_e~ d.r..i..ve_n ~AFW pu_mp_until_.24
~2-40 A " ".
^
- - hoursuatter;SGipre,s_surejs3reatetithan1532.psig.
CPSESMarkup of CTS 3N.3 JN 3-17 U2989
. - . - - - . . .. . . . - - ~. . . . . . .
l CHANGE Nt#EER HSlE DESCRIPTION definition of STAGGERED TEST. BASIS. However, several trip functions do not require response time testing, as indicated by N.A. in the tables of response time limits
[previously relocated to a licensee controlled document.
A note. which'is currently located in the CPSES TRM, is I added to denote that response time testing of the neutron i and N 16 detectors is not reauired]. The improved TS specify thatmQresponse time testing De performed '
on a STAGGERED TEST BASIS and do not impose any requirementsas to which train should be tested. -
4 Therefore. Shh crd rguired" i; ;dded to tbs 0 3.3 55
~
Crr;r.tTS;r.dftherequirementtoensurethateach. !
train is tested every [36] months is moved to the DC ALL 001 Bases for ITS SR 3.3.1.16 and SR 3.3.2.10.
1 03 LS 1 Not applicable to CPSES. See Conversion Ccaparison Table (Enclosure 3B). l l
l
)
i I
l l
l l
1
,4 4.
1 1
RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS
........................................N0TE- ---- -- -- -
Refer to Table 3.3.11 to determine which SR ;,.m u ., , 74 .-41"";
_ _- m ______ __ _ . . " ' " ^
D1 ~ M m
~-
r.. 3.3 55
? .. m ra. c=~.m -~a z. .--~a.n ~... w . 9
-_m._,,......, ,,y
-- '*' h".*JbU *a."* wt**"hk .
==*J.
_... _... m . ...... f SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 4
i i
SR 3.3.1.2 - - - -
- NOTES - - - - - - - - -
- 1. AdjustNISan{Ni16JPower;Monitorchannel m ' 3.3 389 if absolute difference is > 2%.
- 2. Not required to be performed until 12 24 s3.3 961 hours0.0111 days <br />0.267 hours <br />0.00159 weeks <br />3.656605e-4 months <br /> after THERMAL POWER is 2 15% RTP.
Compare results of calorimetric heat balance 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> calculation to Nuclear Instrumentation System i3.3 38 4 (NIS)an_ din 36;PoWerjjlonftorlchanneloutput.
SR 3.3.1.3 - - --
NOTES- - - --- - -
- 1. Adjust NIS channel if absolute difference is 2 3%.
- 2. Not required to be performed until g~g 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after THERMAL POWER is z 19 Sgt RTP. m3.3;9M Compare results of the incore detector 31 effective measurements to NIS AFD. full power days (EFPD)
(continued)
CPSESMarkup ofNUREG-H31 - ITS 3.3 3.3-11 129/99
RTS Instrumentation 3.3.1 SURVEILLANCE FREQUENCY SR 3.3.1.12 Not"emed] F3'150M
.u.n. -. e This Surveill;r.c shcil inclui verification of "c= tor Cocient Systc;;; resistence terper;turc itator t/s,.- . Teci, 'T;u 7:.tc.
o__,__ r. .uur, ,o ;
,m...,,, .. . . .. . , r_i , , o.m..
n . , m.u.. . .
.. a..._ -
SR 3.3.1.13 Perform COT. 18 months SR 3.3.1.14 - - - - - - - - - - NOTE - - - - -
Verification of setpoint is not required.
J Perform TADOT. 18 months 18 4 neI -
u,i.
SR- 3.3.1.15 .- -- --
- - - NOTE- ----- -- - --- --- Only requircd Verification of setpoint is not required. When not
............................................... perf;r;,;d withia picvious 31-days Prior to 3 3 143 exceeding n 3.3 007 Perform TADOT.
the~ P.dR interloeg W!!e!!elerithe unit;has'been110 i
tD2El3Tiffj!ot petLotaedi1n Rted@s212f!yg reactor startup SR 3.3.1.16 -- - - - -
NOTE - ---- - - - - - s3;3 383 NeutronJ_ndJils detectors are excluded from response time testing.
e -
m.a g w. .j VerifyC;rLJR DNONSE TIMES are 4s 18 months on within 11mits.C:"j 03r^J.;T a STAGGERED 3.3 55 J 0 3.3 55 TEST BASIS CPSt$ Markup ofNUREG-1431- ITS3.3 3.3-15 1/29/99
i RTS Instrtmentation 3.3.1 Table 3.3.1-1 (page 1 of 9)
Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER . . Ntte "
SPECIFIED REQUIRED SURVE!LLANCE' ALLOW 4BLE' GE490145" -
FUNCTION ,
CONDITIONS- CHANNELS- CONDITIONS REQUIREMENTS VALUE=t
'1. Manuel Reactor 1,2 2 s SR 3.3.1.14 NA NA Trip y 3 *' , 4 *' , S *' 2 C SR 3.3.1.14 NA NA Of . .
.t
- 2. -Power Range Neutron Flux
- a. .High 1,2 4 0 SR 3.3.1.1 li11U7X - '0 % ::: PE $ef$ M SR 3.3.1.2 RTP SR 3.3.1.7 +++re SR 3.1 1.11
! . . " . "!. ' , t g.pg q' st 3.3;1:16
- b. L ow . 1(C), 2 4 E en a.,.... .5-25#-et SR 3.3.1.8 5;27.7% RTP P 3.3 55 SR 3.3.1.11 9772
. 0. ' . T.q. 0 3.3 55 st 3.3.1.16
- 3. Power Range Neutron Flux Rate er High Positive - 1,2 - 4 E- SR 3.3.1.7 5:,6.3 6:6 s-!Htte Rate SR 3.3.1.11 % RTP ....;;
with time constant c B'PS m constant 2-t-see a 2 sec
- , . .-: . _...;;.. +;e + e
- 3.3.].[, ; ;;.::: :: r-est* *te E3:3-011 Ree. - ...... , . . . . . . - . . . . . . -
- .
- .".'0 constant constant t-fet-see . ;;; ...
- 4. Ir,termediate Range ' 1 , 2
- 2 F,G SR 3.3.1.1 i:31'.53 ; :: :77 g g.pg g Neutron Flux SR 3.3.1.8 5HE RTP SR 3.3.1.11 a" 2 R ::33.j.! ; ::: ::r ; ::: ::r
%;8sW95M r .: :. :. ..
(continued)
(c) :..: _ . . .;.. u. ; . : : : . . v;_. .;.; . , .;. :. . .; ,- ta : ;4. ;.; _ 4 ;; . , . :. .w. . .;
y3;g g
~
- ;, _..../ ; , .,
- ;,, ;;.. .
- :. ThonessMcatueMt2tOhG.fettifDefettsystesGetti.nel WiesaanumamerimogugrtflCeetteDate7 i, (b) With : - ... 7. ;,, ;. ..:.. . ;;;; ; .;...,: ; Rod Control System capable of rod withdrawal otett'AneJC 3.3 122 L . W.LMEKMSREDilNitSM '
TR 3.3 006
- i. (c) Below the P 1C (Power Range Neutron Flux) Interlocks.
(d) ' Above the P 6 (Intermediate Range Neutro;. Flux) interlocks.
- .;
- ;. ;_ ;; ; t, ;;..;.. : . .;; :: . ;.... . ;_; :. .;.. ;.a. .
03c3 951
+
., ; CPSES Markup ofNUJtEG-1431 - ITS 3.3 3.3-16 U2939
.RTS Instrtmentation 3.3.1 Table 3.3.1 1 (page 2 of 9)
Reactor Trip System Instrtsmentation
- APPLICABLE MODES OR OTHER NHP p' ggq' SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE SEMGM~
FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE M
- 5. Source Range 2* 2 I,J SR 3.3.1.1 5 %4 E5 t-+-6-E5 qq" ,v;pg Neutron Flux SR 3.3.1.8 cps epe SR 3.3.1.11 13,3.j$ ej -
SR 3.3. : .;t, 4 3*,4",5* 2 J,K SR 3.3.1.1 5 7.4 E5 t-h9-E5 e og g y~
SR 3.3.1.7 cps epe SR 3.3.1.11
= :.:.: . ;t, 3!3:3 554 a~r.4~r-s~ e t. = :.:.:. m w -:3.34Gi -
= ,.:.:.;;
- 6. overtemperature M 1,2 4 E SR 3.3.1.1 SR 3 1 1;2 Refer to Note 1 Refer-to Note-t ogyg] ~^
N-34
- SR 3.3.1.3 fPose tPose SR 3.3.1.6 3:5-i%t 5:5-i%t _3.3 38a SR 3.3.1.7 SR 3 m t;10 U3:3 50d
- :.:. u -
.: ' . . ; . ;a SR 331;36 l 3.3 55 Q 3.3 55
- 7. Overpower e 1,2 4 E SR 3.3.1.1 Refer-to Refer-to egggg gay Lew sa;3.3;f;2 - wete4 wete-2 SR 3.3.1.7 tPose tPope NS-.I sR:3.3sM10 5 + 2- 5:5-25t 23.3-501 s;: :.:. .= ) it14.3x
...,,..,...ie RTP.
SIC 3;3;f;16 0 3.3d GEN (continued)
~ () ;;.. : ._. ' e ;..;. . ;;. . . . r.. . l . e I a,J ..-. a .; 6 -, - .; . . . . a , id ; -.;,; . 'J. ; 4.r. :: . , - . ^, i,~ ; . a
- (3) Below the P 6 (Intermediate Range Neutron Flux) interlocks.
- ;;;;'. u.. ;;n. .. .. . ;..
- . .
- ;m., . .. . ... a . . J . . ; ,,,,,..a ...a . ;r:,, ~; a..
, .. ;;. :., ; .. ;;.e ;.. . ;:: ;; . n aa: . :,.: ;u:: .:.;;. : :.a...;; .. .
. J CPSESMarkup ofNUREG-1431 - ITS3.3 3.3-17 < 1/2939
RTS Instrumentation 3.3.1 J i
Table 3.3.1 1 (page 3 of 9)
Reactor Trip System Instrumentation l
APPLICA8LE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE LFUNCTION ' CONDITIONS CHANNELS' CONDITIONS REQUIREMENTS' VALUEM
- 8. . Pressurizer Pressure
- s. Low 4' M SR 3.3.1.1 4686 ^0^,,..,'
SR 3.3.1.7 $"ja8F.4 ,iB-PS d i SR 3.3.1.10 psig s..,..... (Unit' 1)
SR 33;E16 ij1865.2 3.3 55 J pets 0 3.3 55 l (Urtit:2)
- b. High' 1,2 4 ~E SR 3.3.1.1 0596 di s"(g.pg"w SR 3.3.1.7 ,f.2400.8 SR 3.3.1.10 psig 3.;. .nu- (Unit'1)
SR ;3.3.1',16 . s12401.4 pois (tktitJ2)
/ 9. Pressurizer Water l'O 3 M SR 3.3.1.1 . r9iME hg.pgg Level - High SR 3.3.1.7 ,693;95 of s SR 3.3.1.10 instrument 0 3.3d GEN
.a span l
'10. . Reactor Coo 1 ant , 69:2 gggg.g Ftow - Low- N8K of fluftseted e iB-PS'ied .
.. ; ; . , ; . ;. .,,,,. 1*'h 3 per NN SR 3.3.1.1 teop fteel e-909i toop SR 3.3.1.7 (Urtit"13 SR 3.3.1.10 it8B'~8E
. of Q 3.3d-GEN
. , . . , . . . . . i indicated 73.3;1 @ took;ficil -
(llatti)
- , . . , , -- 4~ 5 per n
- - :.:.:.- e9:e r-909i
+=P ^^ 2 2 ?_ in3i3f42d (ContIliued)
(a)a:.... . . ;,,:2. ;;. . ; ; ., . ; n : ,,; .-.. . ;. ; . , . .; . : , , ,,, ,; , t, ; ;-.;,; . ;. : -: . -- ,,; . . , . :. ;,,,, ,-.:
if 323p089
- , ;...,
- .; , ..: ;,, :.. -,::. DiggtmbtongiarAf t.neerthef.UmitMeefetfeWtemis' tting! e See!the N U ffp;5etpolets?
(g) Above the P 7 (Low Power Reactor Trips' Block) interlock.
i.H. , .^, .. q,e : " j ^ , . ,_, ;- ..- ;.. .; .. ;. .,:-i.
, ., ,_....g. H. . ... . _ . , _ . ._ . , . . . . , . , , _ ,
. .. .... . . . . _ , E3 42A
,s- , . . .
J CPSESMarkup ofNUREG-1431- ITS 3.3 3.3 18 U29/99 w
.c ,
3 RTS Instrumentation .
c 3.3.1 in TA M 3 J.1-1 (page 4 of 9)
Reactor frip System Instrumentation APPLICA8tE MIDES SURVEILLANC l OR OTHER- E ~
SPEC!f!ED REQUIRED REQUIREMENT ALLOWA8LE
~W3*'S-08M FUNCTION COND!i10NS' CHANNELS CONDITIONS S VALUE"8 l i
lla mggj S j 7 ,, ;:- ; ;;. ..:..c l Posit +en )
4" % rep' 0 = 3.3.".14 NA NA
- e. ^ : . ,; . L.,,,,
4" 4 per M = :.3.".14 NA NA
.. T Lei,;,. rep j
- 12. Undervoltage 1 W1 M SR 3.3.1.9 2 4753:V ; ' = v s.
'; g.p3 3 - I per bus SR 3.3.1.10 4M6 RC" .)
A 5.3.7 7.. )
(sa 3.3.1;16,/
'13. Underfrequency' 1 t!E,1 M SR 3.3.1.9 a 57.06 Mr a 57."; ;;2 ,eg.pg g RCPs per bus SR 1 3 1 10 !hht .
.; :.3.1. T SRI 3;U16 3.3 55 ;
Q 3.3 55 1
.i 1
- 14. Steam Generator - 1, 2 (Tper SG E SR 3.3.1.1 1r-5iH!
-(SG) Water Level SR 3.3.1.7 f,,t-56-4 23.1X'of ye g.pg'g~
Low.Lowtu sa t t 1 in rierred i rangR q$l$.$3 '
sRJmj;f tr tr aint sped
,~
(uni.tm iWME#t naneil rehts 0 3.3d GEN fHetrumiM span (Urtit!R)
(continued)
' (:) :.. : _. . ;;,,;. . ;;. . ; ; ; . : . ,,; .-. .;.; . .c -, . .: . ; . . .; , ;,t : ;,;. v.: . . . . ;r ; . . .
- , ;..___: , ..; ;,, ;t.; .::. ItKMidiktRNtaEdhtt41ictlCUptWiefetK@stsCuett'es; sed 23:3 08A N 3t E sotpoint4 (g) ' Above the P 7 (Low Power Reactor Trips Block) interlock.
. ;;.; __ . _ ;; r : ;r_ c : -._. . 7 : ,; :. .;.. : .,.;..
r_. n.. r : ;r .c :.c. ::. ;. . ; ; m. 3c3'014
- -;; __ _ _ jr 7 7 ;;.
- _;.. T. . ::, L; .. ;e. ;_; . ;,.;
- m. 27 tie"uppUtabtmNsIfoObsiFAlennt(sItEJebMI3:2il.'nf(WrCastrJctiWJ 3.3 52 CP.3.3 008
. CPSES Markup ofNUREG-1431 ' ITS3.3 3.3-19 in989
. , y,... -
a .- . .-
)
F ESFAS Instrumentation
- f. 3.3.2 l j
SURVEILLANCE REWIREMENTS
........................................N0TE--
l Refer to Table 3.3.21 to determine which SRsCSini;#.;g'".CJ;;.;,;-Xl%g
@p)1y for eacn Eare runctionQ ES j -
3.3 55
..__._m,_. . . _ , _ _ _ _ , _ . . _ - , _ _ . . _ _ _ _ . - _ _ o.3.3 55
. _mu ~ u eg--- ,-, a .a _4 =. = m=- --3
-_...__ = - . %.
dons = I=$
..............'1Ys*
w l SURVEILMNCE FRE@ENCY l
I SR 3.3.2.1 Perform CHANNEL' CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 1
SR 3.3.2.2 Perform ACTUATION LOGIC TEST. 31 days on a STAGGERED TEST BASIS .
1 l
l SR 3.3.2.3 t0T" - I Th^ centinuity d;d ;;;;y be excluded. e3.3 60a j l
A Ojs OO O D - h -- APTf f ATTrut f At* T t* Tf-PT PT Af*PPfif*fi Tf-PT I La a vi m nuswniavn a.V%s a v i6wa. w i nussi.s wu a6wa BASIS Not3ed.j SR 3.3.2.4 Perform MASTER RELAY TEST. 31 days on a STAGGERED TEST BASIS SR 3.3.2.5 Perform COT. 92 days i
SR 3.3.2.6 Perform SLAVE RELAY TEST. 92 days MD"N l
l 3 3*5 SR 3.3.2.7 -
-- -- -- -- - -NOTES- -- --- -
CP 3.3 005
\
IgVerification of relay setpoints not required. l I
- 2. Actuation,1fXfj nalLdetices:notlinc]uded 31,92--days s
............................................... 0 2 17 Perform TADOT.
CPSES Markup ofNUREG.1431 - ITS3.3 3.3-32 1/29/99 i
ESFAS Instrumentation 3.3.2 URVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.2.8 - - - - - - -
NOTE - - - - - - - - - - - - - -
Verification of setpoint not required for manual initiation functions.
Perform TADOT. 1Rmonths yzgnm SR 3.3.2.9 - - - - - - NOTE - - - - - - - -
This Surveillance shall include verification that the time constants are adjusted to the prescribed values.
Perform CHANNEL CALIBRATION. 18; months p sg g.:
SR 3.3.2.10 - - - -
- NOTE - - - - - - -
Not required to be performed for the turbine wggwg driven AFW pump until 24., hours after SG-pressure is 2 1000-532 psig. W84SM
[, .
Verify #"~" """ ESFA%ESPONSE TIMES are 18 months on within limit (p,MM;G;;.;Q a STAG 3ERED 3.3 55 0 3.3 55 TEST BASIS s
SR 3.3.2.11 - - - - - - - -
NOTE - - - - - - - - - - - -
Verification of setpoint not required.
Perform TAD 0T. 18'.NQp:thtj n- :: ysyg.614 i
- e, rec; tor trip i bre dar cyci;
$9Q3,12112 - . Perform CHANNEL CALIBRATION. 9 months li:341263 3
CPSESMarkup ofNUREG.1431- ITS 3.3 3.3 33' 1/29/99 e !
.. 'l-
ESFAS Instrumentation 3.3.2 '
o ' Table 3.3.21 (page 1 of 10) '
. Engineered Safety Feature Actuation System Instrumentation .
' APPLICABLE i' MODES OR i
SPE ED REQUIRED SURVEILLANCE ALLOWBLE FUNCTION COWITIONS CHAMELS COWITIONS REQUIREENTS VALUE"8 h 1. Safety In,)ection.
- Jg
-0.(ManualInitiation. 1,2,3.4 2 B SR 3.3.2.8 NA M ya 1.2.3.4 2 trains C SR 3.3.2.2 NA M 5 l,
= b. 7 Automatic Actuation Logic. SR 3.3.2.4 L and Actuation SR 3.3.2.6
. Relays
- c. Contairment 1.2.3 3 D SR 3.3.2.1 s).8peig ;
- . p;i; j Lg.pg g
, Pressure - High 1 SR 3.3.2.5 iHNi sti' SR 3.3.2.9 i ,,0.2.2.1.
- SR 3.3.2.1 a
(
'd. Pressurizer 1.2.3* 34 0 SR 3.3.2.1 a 1803;6 e4850-pe+g g g.pg u b
Pressure - Low SR 3.3.2.5 psig >
SR 3.3.2.9 4869
, , , ,. 3.3 55 i: M}y Q 3.3 55 i
t
, e. Steam Line 1.2.3*- 3 per : SR 3.3.2.1 686 e-6's Pressure steam SR 3.3.2.5 J R593.5 ps4g'* W 84PS M a line .D SR 3 3.2.9 / psipu fu Low ,,0.3.2.1 (Unitil).
5i578;4 SRf3.3;24 9819 "
1 (Unit 2) fet-H+gh m,_,
4;sh3 3-pee 9 [:" 2.3.2.1: 2 [I^0 p;i; r--EGM r3J3 0131 4
............ steen ,., ,. .,. .,. .,, pe+g .
1 Preseuce une
. , ,2.:
, ,.2.3 1-q gn,,
" ~ "i 7. St;u il z '- 4,4,4
- e-pee 9 " 2.3.2.1 fe+ fe 932181N T;;:n.-Lix; steem = .32a Hee ;"., , J a a
. 0;ir.;i_... ;'t' 4v3,3* 4-pee 9 SR-3-&-B.4 i [55^.0l*" ; [55 ]*"
T,,, Lu Lu 4eep " :.: 2.5 f3:34011 SR-3-a-e-9
~'
"" 2 4.2.10 (continued)
(a) " i. x x '; ";;;. ;it
. .r. ;'i; i- pl ...;;i; ; ;;y 2i ; .ly l ,.#1; ni;; _r...li;; ; '.;;rt t t 3:3
~'
Study _.ll;;y ;.;;d by t'.; ...'t Yht'Allguablg3alue;def1feslthell jettjpg';sefety:SysteeJetting{ Se(
tWMeis"fairitheJdVsetpoints? 3.3 63
-(b) Above the P 11 (Pressurizer Pressure) interlock an{pe}qwfillnunless;theJunct19911s"b.)ocked.
. (c) . Time constants used in the lead / lag controller are 1 a50secondsandt,s3 seconds. 0 3.3 63 an . , _ _ .._.
._. . _ . _..n...,,
....,,....,....,m., > _ _ ... _ , , _
m.- ,_. ,,,,.
r,,, , ._.
,_.2 y,.
m ,%_ ,dl
- ..,.. . ..r..,., ,__.,.,. ,,. ....
. . .. . . . .. g ....... .. .
__.m. .....,,,m.,. . . . , . . , . ... ..,. ,.... . ,, _ m _
....m ._ . .. ... ,., ....,, . ,.,.-_. . ....,
.. _- _. .,,_. k 32391,4
..,_..,m .... ,.., - . m . . ,.
,m ,, . ,__2 m
4a., . .__.m....
m.... ... ,_
- . ,; c. ; ; _. . ;; ;
.. , . , . .. ; . . :. :c; O
CPSESMarkup ofNUREG-1431. ITS3.3 3.3 34 1/2989
- x. - -- . .
, . - ~ .- . - . . - - - . .. . . . .
ESFAS Instrumentation 3.3.2 Table 3.3.21 (page 2 of 10)
Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE N P3:37081 FUNCTION C0f0!T!0NS CHANNELS CONDITIONS REQUIREMENTS VALUE"
- 1. Safety Injection (cont.)
4,-er-4* 9 '? 2.0.2.1 fet if+ 33;3:01M 3
, i;
" _St;; ' , . F1;.
_ , .'-, . . _ ~ _ _ .
iHMee eteen e.
.. , ..,.,..e.e Hne SR4r34r9 e,,. .. . ...
0-i nii.-t .;it'__ __ 4v-3,-3* - 4-per 9- 0 6" t-E953 v3;3;010
. ____. ,__ . . ~ __. . . - . . eteen
." 2.3.2.1
, . . . . , ps4g psig
-kew Hne ,
- "., 2 . 2 . 2 . ".,
e , , , 4
' 2, Containment Spray
- a. Manual Initiation 1.2.3,4 2 per B SR 3.3.2.8 NA E train. 2 trains
- b. Automatic Actuation 1.2.3.4 2 trains C SR 3.3.2.2 NA E Logic and Actuation SR 3.3.2.4 Relays SR 3.3.2.6
- c. Containment 1.2.3 4 E SR 3.3.2.1 2_18'.8psig s-le-95 g 3.p3 w
- Pressure SR 3.3.2.5 4e-31 ps4g High - 3 SR 3.3.2.9_.
3'3 55 SR;3.3R.1Q - -
y 0 3.3 55
":;'. - 'T : Lc; hera Es3-sets E " 3.0.2.1 a :12.21' ; :12.^5: g3:34015 Mentet e M e) SR44:e-5 pe+g pe+g (continued)
(a) ;.i;.c '; " t:-. ',;n't ;g;i'i; i pi ....; tim. ny ....t i =1; .'";.d'; '.';1= 2p..m a; = Rtsi-t S3.3-083 St_dy = tt ,t h ;y _;;d by tr.; ='t De3Upsabl#llJHueidennes;th:31sdting: safety;systes39tting;see WENet3pD m.. o ,, t,h,edpis(t.pointC ,_m.
m_.._
,, m_ , _. .. .v . . . . . v, n
_ .._ _..~,. __ , ._.. .,>_,,__> __ .. __ ...,_ _>>._,m._,,,,,,. p3.3 011,
. _. ._. _. . . . _ . _ . . m.., . .. ,_
_ ,,__ m,_.
. . ~ .
.m. ...
._ , , _ _ . ,_ ,. , m .,._ ,,,,,,
__.~_. ,,_ ..
_ .. g..
- s. ...w....g
...N.. Ig
.,.,',r,T
,,,L
.. ..m.1._ ..W'. .m.
__ g . . f..i
.2
__ .. b. 7J, .... . b.
s ..V . ..J, 3.,;3-01,(g,.
-_____,.,.~_.,,,,,..,.,.J".
. . - .m..,,..
,__m
> > _ _ _ .. . . , , __ , , _ . m ___ ..,. ._>
..m, __ ..
.._~_m..._...,,,.,.~m. .. . , , . . . , , . . .m._
.,,.-_,,,,,.~..,,,g,.
..2
_ . . ~ . . . ..
..~._s_,
..~_,.. .-r..,..m.._
.m.
s., , ved-to-fi.~.,, . m. .,..m... .
, . . . _.-~ , , _ . .s3.3;012. f
. ..,,. , m. ,__2 CPSESMarkup ofNUREG-1431- ITS3.3 3.3-35 1n9/99 E .
. . ~ . . . . .- .- . -. .. . -. .- - .-. .. -
ESFAS Instrumentation 3.3.2 Table 3.3.21 (page 4 of 10)
. Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR.
'OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE N ^
COWITIONS CHA10ELS COWITIONS REQUIRENENTS VALUEta N
FUNCTION
- 4. Steam Line Isolation .
(continued)-
- b. Automatic Actuation 1. 2(" . 3") 2 trains G SR 3.3.2.2 NA NA Logic and Actuation SR 3.3.2.4 Relays SR 3.3.2.6 c.! Containment 1. 2(" . 3"' 41 D SR 3.3.2.1 [6.8psig sHHHi g.gg.p$yp Pressure - High 2 SR 3.3.2.5 6 pe4s ,
SR 3.3 3 Q.
, : . 2. 2.10' SR 3;3:2l10 I
' d.- Steam Line Pressure - 1. 2 "' . 3 per D SR 3.3.2.1 685. eH95 u m
-(1) Low 3*"" steas SR 3.3.2.5 f 59iMi ps49'*
line SR 3.3.2.9 594.0 3.3 55 m 2; J. T M19'" o.3.3 55 SR:3.342;10 J (Unit 13
'2 E578.4 pq1g'd CP 3.3-016
. (Uniti:2)
I (2) Negative 34"" 3 per D SR 3.3.2.1 P178f8 t-HG qg$$g
'?.
Rate - High steam -SR 3.3.2.5 ps1 pt#ses*
. line SR 3.3 2 0 a 401-6
- . : . .15 po#eee SR3,3,;L10
- . "i;'. ::;; ik; ' Tx 4#*v-4* e tee 9 SfH H hert fe+
- S3.3N019 steen-h4aee eteen = :.:. .S
+4ne Z :.3.2.0 2 0.2.2.10
' 0;ixii.c. .;it' 4#*v. 1-pee 0 0" 3.2.2.1 a (ZO.0;"i i ;Z: *i T,,,- L;.: L;; a*"* wp = .:.2.5 m :.:.2.
b = :.3.2.10 T w www Dwe . t .F M. D 7FW FT WW wwu r T I I WF W .w pf .
r.t ::.:y -.. :_%2c .x:A tr.: .:'t. TIO]1steloslar.deficKtheJ1 siting:sofety:systen 3,3 63
- t.:s,81 4831 ~ 5lWJhEsiisisi".fgEthGJgi;#itsii)fal#rl 0 3.3 63
- (b), Above the P 11 (Pressurizer Pressure) Interlock ap(teloWJj11;IunlessitheJunctiords blocked.
4 W?.Bl%M
- 3.3!63'
{c), . Time constants used in the lead / lag controller are 13 a Sg seconds and t, s 5 seconds.
(g) Below the P 11 (Pressurizer Pressure) InterlockEllqmpqt7jgdrKIp1pckelljelorfilliteeKsafspy CP-3.,3 ED N31RKPressiq1ti}glC15M gg ,qggg (h). Time constant utilized in the rate / lag controller is e {030 seconds. 4ggggg-D (i) Except when all NSIVs: ant;their.Mata()qigJrgpdijitigEpst3splationalm are closed and ;#3.:3'462G gggmegg
< CPSESMarkup ofNUREG-1431 - ITS3.3 3.3 .t 7 109/99
I ESFASInStr$ mentation i' 3.3.2
(
- Table 3.3.21 (page 6 of 10)
Engineered Safety Feature Actuation System Instrumentation APPLICABLE -
MODES OR OTHER TRIP 4--
- ' ;3J$$ M
, SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION . C0WITIONS CHANNELS COWITIONS ' REQUIREMENTS VALUEW
- i -
t St x Lin; !.cl;ti;n l M i f "i @ Ots : ile.; 4,3*,- 3* E-pee 9 " 2.0.2.1 ; [100]; ;f e-{-}-ef I steen 0" 3.3.2.5 f;11 ;t;= -4tM -
" .3-011,.
! 44ne 0." 2.0.2.0 ;w ;t full steen C.",2.2.2.10 ind ;;; .; h presstere full ind steen presst8ee
. 0;taci,L...; wit', 0;f;ty ";f;r t; Tancti; 1 'S;f;ty !nj;; tion) f;r ;1' ' 't;;ti= fun:t4ons c3>.3-01El inj ;ti;n ;nd r;,,.i. - ..^.:. -
- 5. Turbine Trip and Feedwater Isolation a'. Automatic Actuation 1 . 24 8 , 2 trains H (G} SR 3.3.2.2 NA NA 37; g;p33q Logic and Actuation {4}* SR 3.3.2.4 Relays SR 3.3.2.6
- b. SG Water . 1 , 248 .' 3 per I{0} - SR 3.3.2.1 ,84-04 s-40-44 ygggy Level - High High {4}" SGS SR 3.3.2.5 s84j3*)f
- , (P 14) .
SR ,i ,i ,',> 0 narrwJenge
, . . . . .o.1
_ span 3.3 55 SR32M10 ( 1 na g tange Q 3.3d GEN spar; l (UnitA i
t c. Safety Injection Refer to Function 1,(Safety Injection) for all initiation functions l and requirements.
(continued)
(a) -,___,_m.,,__.
m_
_ ,,_2.
7,..-,.,,,. . ,. _ .,.. ,___. . . . . . _ . , . . , , , , . . . - . , . . . , . . , . _ - . , .
m,__ __ , _ .
, , , . , , , . . . . , - . ,..y,,,
'y333;gg g
- t 'y _r. '.1;;y xd by t'.; ;;'t. IKgloweblaglos!!t).gsche:11mitint*fttrsystem;settinga see nyangay3pencipygpernen ta8-PSul
, (j) . Except when all MFIVst-NFRVe-and'associpted,tepasQe]W!( are closed:endideitetjvatedfordsolatediby 4 m'3:3664M IPl O g!B M B R ee t. ..,w_,. .f4.w M_ --. > ,__ _. ..,.. m..... ww _
. ,. . . . _ _ , . . _,,__ . m ,
=w,.._x. . . _ ..m a -
.u w
. . .- r- ...m.--._.g..
2 .
.c .e --a m. _ , _m .,., .,. %--.__s_
_ w ,, m ,u , .. .r
. _s a_ . - -- ,m gg _a__ 3 3.3 65
._==g.- .my .
, g_5-..g g- m - g y 7 -g. ;--..; u-.-- n 7. .~.. g
_ . . __ -_-m_u.m.r u - - . -.m,a. ._,. u,_ . s_ 7 . __. _am
. . _. . _- .s _ m, _ .-s.w - ~ - . _ - . u-s .. - Q 3.3 65 Mwwn,w . . . ,a
, K-.UM%. .f *T , Men **N.A Fa* eM+* IS"4.*** ?.M N \ee%. n s r *""TI"T.-*. .
Obeset#19CtedAntasJudepuntolthos>ptar;)mptcontro.11erijuusoe_declaredanopetablei 4
+
d CPSESMarkup ofNUREG-1431- ITS3.3 3.3-39 U29/99
ESFAS Instrumentation 3.3.2 Table 3.3.21 (page 7 of 10)
Engineered Safety Feature Actuation System Instrumentation i
I l
APPLICABLE I MODES OR OmER .
7?3:3-081 SPECIFIED REQUIRED SURVEILLANCE . ALLOWABLE TRfP FUNCTION CONDITIONS CHANELS COWITIONS REQUIREMENTS VALUE"8 SEH W MF ,
Y j
- 6. ' Auxiliary Feessater a, ' Automatic Actuation 1.2.3 - 2 trains G SR 3.3.2.2 NA M Logic and Actuation SR 3.3.2.4 Relays (Solid State SR 3.3.2.6 j Protection Systeel I
(,
- b. ' t;=ti; f.;t x tion
, 4-273 0-teevns. G M M ;.3.3 01 '
';;i; =d f.;t= tion Rt.4 eye-fBc}enee-ef "1=t m'i:
Not;Used; l
- c. SG Water Level- 1. 2. 3 4 per SG D SR 3.3.2.1 v30-44 M y g.psgy Low. Low SR 3.3.2.5 223;1.tof - - - - - - --
SR 3.3.2.9 na_rrow, range I
3.3 55
- 2.2.2.1. way -
0 3'3 55 I SRJ.3i3;t10 (Unitti) !
133 A of - . -
narrowJange 0 3.3d GEN l 1
span (Unit:2) l l
(continued) l (a) cat: r '; ";t . i,wt .s; : i;;b_a. :ti = =y .=t:i =1y "b=tk '!:12 ca.4:n; = Rt;;i-t St.dy _ ttch;y nd by tt.: ='t TheAlowable3tiue:detim;.the3)fejtimyafemsystasjettinga see e3.-3;083
- tutseeliifM3tMCItfKset# Int:1 l!
l l
L 1
L i-CPSES Markup ofNUREG-1431 - ITS3.3 3.3-40 if29/99
ESFAS Instrumentation 3.3.2 1 Table 3.3.2 1 (page 8 of 10) 1 Engineered Safety Feature Actuation System Instrumentation APPLICABLF.
NODES OR OTHER SPECIFIED . REQUIRED SURVEILLANCE ALLOWABLE N T 3'.3 4 FUNCTION COWITIONS CHANNELS C0WITIONS REQUIRENENTS VALUES 1
- 6. Auxiliary Feedvater '
(continued)'
- d. Safety Injection Refer to Function 1 (Safety Injection) for all I initiation functions and requirements. l
)
- e. Loss of Offsite Power 1.2.3 {+} 1 per F SR 3.3.2.7 i 2010 " e-{49 bus train SR 3.3.2.9_ .:it' ; 0.0 & 3
,2.2.2.10 eee-time with g;355 3*3 55 SR 3.3.2.10 de+ey NA r-4-8 t,me 1B-PS:
de+er ,
l J
- f. '...i.. lt;;; "; xt x he is3-per + = .2.:.' a ::::t bu; e-E+034
- =1; a-Aused. ben = :. .:.0 ve m se bus 33.3-01S
= :.:.2.10 ve m se 1
(continued) i 1
(a)' ";,i; ;^*; it;. " #t ,r C'"iC i;i C- ICIICCC Zy --' Ci CCly "Ib'UIC 'ICIUC dCPU'di $ - SCIPCi-I St.dy ..._21;;y x by tt;
_ ;'t. TheJ110webleJalue, defines _.the limitjng; safety system settingi See 3.3-081 eKameinifoche: Trip'setpointsi
< CPSESMarkup ofNUREG-1431- ITS3.3 3.3-41 12989
ESFAS Instrumentation 3.3.2 -
Table 3.3.21 (page 9 of 10)
Engineered Safety Feature Actuation System Instrumentation i
APPLICABLE MODES OR OTHER t3:3-R1 SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE RW FUNCTION CONDITIONS CHANELS COBOITIONS REQUIREENTS VALUEW EETAG M'"
- 6. Auxiliary Feedwater (continued) f
- g. Trip of all Main 1.2 2 per AFW J SR 3.3.2.8 t-f-}-pe4s ; ;; pi;- 9ga ,
Feedwater Pumps pump 0" 3.3.2.9 N4
, g, ~g
" 2.0.0.10 i
3.3 16" t3.3 55" ,
- h. ^.wi'i =y Tx d.;'t-e- he-3 E F-F 5" 2.3.2.1 i. 20.Si pic t-E-1 3.3 01i r.;;; :=ti= Te ,- :" . .c.' ; :20.5:: W en ! ;ti m "r;.ur; 5" 3.3.0.0 fpsie}
kow Notjlsed; C" 2.0.2.12
- 7. Automatic Switchover to Containment Sump
- a. Automatic Actuation 1,2,3,4 2 trains C SR 3.3.2.2 NA E -
Logic and Actuation SR 3.3.2.4 Relays. SR 3.3.2.6
- b. Refueling Water Storage 1,2,3,4 4 K SR 3.3.2.1 a n -end ;; ; g g.pS 9 ,n Tank (RWST) Level - Low SR 3.3.2.5 r-E--}4 end -
Low E'38.98 a ; 0 3.3d GEN
^ .:.
C" 11 . 2 ^ 8 instrument a r3:r:10 > span (Unit,"11 3.3 55 SUA2.Ja 03355 CE14 7m . _ .
spatr3 a3 3 126M i mK21 Coincident with Safety Refer to Function 1 (Safety Injection) for all initiation In,jection functions and requirements. 1 (continu?d)
(a) "ni;47'; Lt; 'Jn't ;g;ific i ;;1-...; tim; ny ...;' =1y ."lar.ti; '.';12 ipnding = 0;tpi-t St.dj att.;d;1:;;y x;d by tr.; mit. TheJi]gdebleJalue defjpesithe;]imiljnglatety.systes;stttinsi see -3;3-08a tipiEtii4elfoC7.$he'Tr!P Sstsidlnts!
CPSESMarkup ofNUREG-1431 - ITS 3.3 3.3-42 1/29/99
LOP DG Start Instrumentation 3.3.5 SR 3.3.5.3 Perform CHANNEL CALIBRATION. viith atp^ int 18 months 111 m ..L1- 11.1.._ zaAL~- ^ J a.wattusL1:"as_;1 u naavnuviw wusuw ggey avwwge.w ,j su s rggg g=.gegsg
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- *. :, .""* 'W'*"W*
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- r
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..--g Ann u r*1. . . 1 r* L.. im . _. _ J J .._J._..mia..-- i ww.A 7vv v wsuwa Aw uua sun ys su un swu s vu s b uyw ;
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F SEEMLEA VerjfyMR,;LLOPADGIst)tt3sf.;3 s ..te64en 18;nonthslonla ESF3 RESPONSE~~- TIMES - -
~~a. u. r.e" titit..hirr21.1.-
mit._s.T~;"u-.ic.
Ct d STAGGERED.~T. EST
- 3.3 31
.'. s==
w s c..
. 3_, n. m. BASI ~~
..- j'" s #
'0 3.3 55 CPSESMarkup ofNUREG-1431- ITS3.3 3.3-% U29/99
I l
l LOP DG Start Instrumentation 1
3.3.5 ,
l l
N is m ax fi M le]3lE 5 Eilbag g glf;1] )
12!BME9EEMglomer3LWMMqEGlpjltagetLRStarijflgtsmo!$atfog 3.3 115 !
CP-3.3 011 masa sunumme Aue==e BEIC[101l OgggELS REQUQEIEllT5 VALE l
1T4 Automatic Actuation 1Mc 2f, trains 3.3.5.'1 NA 1 and3ctuatjon,;Retes I;22 Mferred]ffsite sous 21petbus 3.3.;5;2 515900.V busyndervoltage 3:3'5;3
. andj E4900J
- 32 Alternatefoffsite;sourg 2;peribus 3 3.5;2 5'5900,.V buslundervoltage 3.3;5;3 and E 4900 V i.4; 6.9;kv_ Class l1E sbus 2
- peribus 3.3.5i2 2:1935..V undervoltage 3.3:5;3 and
.3.5 4 si3450.;V i
15; 6'.9,,.ky: Class 1E; bus 2;per_ bus 3;3.5.2 215933 V J degraded;, voltage 3. 3;5' 3 QMr 3.3 31
- 6;j 4801V,,CleM21E; bus] 2jperibes 34,522 E4431V 0 3.3-55 loWigrjd;daderMltage] 3J3
- 5~.3_3 .
Of+.bg !
1 1
@ MJiCMIE,bysj 2fperipus 3;315;g j E435:V i degraded 3!l,tage] 3:3.5!3 /
i EEEZAD*fflCCMEREEI.MENIETJKffMA~TIIaTTSXf3 f.
J CPSES Markup ofNUREG-H31 - ITS3.3 3.3-56a U2989
1 Containment 3Latgggg ";.,; ;r' 0;t.;;;;t Isolation Instrumentation w gS N 3.3.6 SURVEILLANCE REQUIREMENTS
....... ...........................N0TE- - ---- - --- ----- - ---- - --
- m.
.....,~ ..... ..
____- _- -_~ _--- -
.m., ^'-,
3.3-55 0 3.3 55
.-A, ,.4, ass.umumspegewaglHei6Meeflessagne?s7;6;ritoldatenytteEWrtetriptswu .
fusasiangentenmusclipatistergentsigKfspotspA SURVEILLANCE FREQUENCY SR 3.3.6.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> l
SR 3.3.6.2 Perform ACTUATION LOGIC TEST. 31 days on a STAGGERED TEST BASIS SR 3.3.6.3 Perform MASTER RELAY TEST. 31 days on a STAGGERED TEST BASIS SR 3.3.6.4 Perform COT. 92 days SR ;3.3.6.5 Perform SLAVE RELAY TEST. 92 days es8em 4
..._: a.. s ., ..,_.s_,
= 2. _.,._..,-s TW3 ,8 3 hub 5 3s -4 db . p 3s8b se a s. b aUgu5sLu.
,o __i n, s. _ s. .._ _. v, ~a nn. . . Notx.Used ....L.. . . s..c3.-8-76.8 SR 3.3.6.7 Perform CHANNEL CALIBRATION. 18 months % :!BwN '
.__. m. . . _ _ , , , , _ -- . _ . - , . , - - - - . , - .. _m _2 ,n- -
m_ .
m.mzu . .2 mm z,?s,w *?2x. u._-1.-.. "-s, an= =.!vu *w.=wu u*
_ , .-L- m. ram W_. '. -. -'tg
- r e--- ._ ;---- ._ c. _m arw: .a.. n 3 3 31
-- _y?x,,ww.
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- m ,u. .. -
0 3.3 55
.u..,...1......exu-y m ... . .u aux ., B_ASIE CPSESMarkup ofNUREG-1431- ITS3.3 3.3-60 1n989
RTS Instrumentation l B 3.3.1
. BASES.
l to perform maintenance to one of the diverse features a M. The ellcur. tic ti;;;c f;r pcrfor;;;ini; ;;;; int'g car.n;c 0'3 3'117 i of the diver;c fceturc; is 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />; for the ree;;ns stated !
under Condition R.
1 I
The Completion Time of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> for Required Action U.1 is ;
reasonable considering that in this Condition there is one remaining diverse feature for the affected RTB, and one OPERABLE RTB capable cf performing the safety function and given the low probability of an event occurring during this interval. j Mai k'ith twe RTS train; insperabic, nc :utc;;;; tic c;p;bility is !
eveil;bic to : hut de 7, the rcector end i;;xdiete plant shutdown j in ;;;;rd .n:c with LC0 3.0.3 is rcquired.
e SURVEILLANCE The SRs for each RTS Function are identified hv +ha (De REQUIREMENTS column of Table 3.3.11 for that Function @tyE.II;1Q A Note has been added to the SR Tabla e+=+4na + hat i Table 3.3.1-1;1 determines which SR " .:;.7.: gcEn3];;;
_1.L;'_,i.; ';@ apply to which RTS Functions Rf!ERESPONSFJHE
_ _ _ m _ m eo ~, - .- , ,-
_ __ _ _______ m _ , _ _ _ . . m.
1-m~u-w -m-ex wam w.er~~mmummemma n Note that each channel of process protection supplies both trains of the RTS. When testing Channel I Train A and Train B must be examined. Similarly, Train A and Train B must be examined when testing Channel II. Channel III, and Channel IV (if applicable). The CHANNEL CALIBRATION anJ COTS are performed in a manner that is consistent with the i assumptions used in analytically calculating the required channel accuracies.
Rcricwcr's Notc. Certain Frequcacies arc based on opprevc1 topical j r;pit;. !r, Ord;r for ; liGT,2; t^ Z^ th-Z ti,,-,, th- 1i27.-^^
must justify the r rc quercics as rcquired by the staff Stn for the topical rcpert.
SR 3.3.1.1 Performance of the CHANNEL CHECK once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ensures that gross failure of instrumentation has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one (continued)
Markup ofImproved TS Bases -ITS3.3 B 3.3-50 1/29/99
RTS Instrumentation B 3.3.1
- BASES o
- Surveillance. Performance of this test will ensure that the TR 3.3 007 turbine trip Function is OPERABLE prior to . ... f b ja M M t dir6 the ra cter criti al. This t ;t cuanet b; g ifer ;d with tk in cter ;t pw;r ;.d = ;t therefere be
- i. grfe d p-ict t; ract;r :ti.rtup.
1 SR 3.3.1.16
' ndividual channel / train SR actuation 3.3.1.16 responseverifies times are- that th(len man or equal to the max
- values assumed in the accident analysis. Dg"EgqMted3rjp -
4 ja,Jtiatjggjglgglg1Gspan tin testir;Ma
- acceptance criteria tog
[55-E - ~ ~ '_^ ^^ lare included in Technical Requirements CP.3.3 ED1 i Manual. W.7eManLditaasitta_Msatecy O'3 3 55 4 -wJy=wsmsailmw3%8HDPMMthlresponse3M11s.tetas i~ NKi;;LiggNMa#R1ss@WstianTenuttestets'impp1Wdiere lN
- 1s511stedlerthif415tTTndividual componenGesponse t1mes are not modeled in the analyses. The analyses model the overall
- or total elapsed time, from the point at which the parameter o.i.i.4
- i. exceeds the trip setpoint value at the sensor to the p;iat ;t
> . .m _t mu_ _ _.. m ____<_ .u. ___..,__2 ,.__u ___, . .i_
8
.vu a i be I bsph by u ym we I b 3 buws rbe berb : bqu 3 5 Eu a us sw b vs .u i ebubb
~
(i.e., centrol ;r.d :h:t i.;. red fully inx rted in the r; =ter eeretuntj)~ 3 cissisfsstatioriarf3gjppelGLol]30]tage.
4
- For channels that include dynamic transfer Functions (e.g., lag, j lead / lag, rate / lag. etc.), the response time tat my kites.tiggy M rformed with the transfer Function tjag_
+
. gggi.aisia;st t; er.e. with tk 7;;;1tir; =nured re;pa;c tinmu_
.___2 uyyi vyi . _.. re .wm .a ________
udyviids .. .,__
3
. wvi yvi wu vv . %. n i wwi s iu ww i .y , wins r; p.;e tin tot sa k prierr;d with th; tim sa:t=ts set t;
. their i,si=1 v;lua, provided th; required r;;p x ti is c ;=13tially =1cul;ted n=:ir; tk tira s=t=ts ;r; set at their nominal values. Th; rap.x tin =y k =nured;by ;
4 series of ;;;rieppirs t a ts such th;t the entir; ra pax ti x is
= =ur;d.
{
r x;p 7.: - ;;
.\;.
- a . .... . m p .s
~ ... . ..
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- 4
. . . . . _ . _ . _ , _ _ . . _ , , ~ . . . . . . , , .
f 'i ..
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_, m .. u - ---v-.r . r.- m- a. a- ., 4 l
. .~ _ _ _ _ _ , . _ ,. l 0 1.1 4 1
l CPSES Markup ofNUREG-1431 Bases - ITS 3.3 3 3.3-59 U29199
l RTS Instrumentation B 3.3.1 h
BASES'.
. As appropriate, eghannel's response est 0 3.3 55 be verified every 3 uiium on a STAGGERED TEST BASIS. f
.y .. .
.. . ,; 3 u;
- . , p. -
. , ...i,.
.O . Q.) 1. ( .. . ' l .
,,] ,i .f ;ay Testing of the final actuation devices is included in the 0 1.1 4
- 6. EL19Mathtgesponse times Mcannot be M itereined-during unit .
operation because equipment operation is required to measure L
. response times. Experience has shown that these components ,
usually pass this surveillance when performed at the 18 month Frequency. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.
SR 3.3.1.16 is modified by a Note stating that neutron and cP.3.3-ED1 EggaugJdetectorsa~ s~jg;7,.;Cp.i stgi!are excluded from RTS RESPONSE TIME testing. This Note is necessary ;
.because of the difficulty in generating an appropriate detector input signal. Excluding the detectors is acceptable because the i principles of detector operation ensure a virtually instantaneous response. ResponseitimeIqfsthelgeutr.onif_1utor:
E16;siggT,fgrticGfgehannelishaHVueasuredifrom dejectorJggl!pEpMr_LtoJghelf1rstrelectroniciccuponentgq th rchan g g REFERENCES . 1. T=.Otepter[7].PAREGhppteMJ
- 2. r=. Crapter [:]. tis"ZSheptemSJ
- 3. .r = , Orepter [15]. I_EEEL2Z9 191}]
- 4. IEEE-2701071.102FR2iOM93 5J M REBg E SI]B!DP M
- 6. "TS/ESI"4 0;tpint "etteilegy Study.lShD191 M
- 7. C " 10271 " ". Suppic a nt 2. ",s. 1. Jure 1000."aM Us_edJ
. .T;;t.ai;;l "; quire cat; ";nu;1. 0;; tion 10. "";; pas; Ttmes r"!ROiglM23etteM85iO92fMitedlmayl2_3E1.985]
8] """""~~"'""~~~""'".."_~m~.~.".'"m~_~m".".'.'e.+ +-4 .
CP-3.3-ED1 1' 915 IWe.stingMWEilia$sint9IethodolMylior2PMt.ictie Syls egg r4amthe2m%ilgi1GrJteitajeElmMN1121231 cP.3.3-ois Rells10pIEMilrJ1!89J -
CPSES Martap ofNUREG-1431 Bases -ITS 3.3 B 3.3-60 ' 1/29M9
. . - .- . . - . - - - . - - . . . . . . . . - . . . - _ - . . . - . - . . . - ~ . - - - - - . - . , . - . . -
ESFAS Instrumentation B 3.3.2. i BASES !
t L1. L2.1 and L.2.2 I Condition L applies to the P 11N interlocks.
0 3.3 ED2 With one :? ; 4 ~ .D . channel (s] inoperable,'the i operator must verify that the interlock is in the required statefortheexistingunit' condition $gggqqgjgnj[gjgt pgtm. This action manually.
accomplishes the function of the interlock. Determination must be made within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is equal to
' the time allowed by LCO 3.0.3 to initiate shutdown actions in the -
event of a complete loss of ESFAS function. -If the interlock is -
not in the required. state (or placed in the required state) for H the existing unit condition, the unit must be placed .in MODE 3 I within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 4 within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
The allowed Completion Times are reasonable, based on operating, 1 experience, to reach the required unit conditions from full power conditions in_ an orderly manner and without challenging unit systems. Placing the unit in MODE 4 removes all requirements for OPERABILITY of these interlocks.
F j
. ~
i
. SURVEILLANCE The SRs for each ESFAS Furw+4aa we idantified by the SRs
! REQUIREMENTS. ' column of Table 3.3.21.C';ML;.
A Note has been added to the SR Tabla +a 9-* t"+
Note that each channel of process protection supplies both trains of the ESFAS. When testing channel I. train A and train B must be examined. 'Similarly, train A'and train B must be examined when testing channel II, channel III, and channel IV Mf ;
.,,,,li s tic'. .The CHANNEL CALIBRATION and COTS are performed in a l manner that is consistent with the assumptions used in j i' analytically calculating the required channel accuracies, j
^^^; C *- %;d. '0;Tt;iT. IT;;.;T.;i-^ ;T; ',;-;d ^7. ; si-/;-d tepi=1 re prt:. :. erder for ; licera;; to use t'a ; tim ;. the lieerac ;u;t justify the Tr;;;;rcic :: r;quir;d by the st ff
- e. ___ m ,
- 1 .~n ,__<_m.._,_,>.._._,.
. . . . . ~ . m. . .
4 n6 i (continued) !
I CPSESMarkap ofNUREG-1431 Bases -ITS3.3 . B 3.3-116 1/2939
ESFAS Instrumentation l B 3.3.2 l BASES N cE.i.isi l
SR 3.3.2.1q 0-1.1 4 This SR imsum verifies thdi.;;;Mindividual channel ESF l l
RESPONSE TIMES are less than or equeT to the maximum values 0 3.3 55 assumed in the l
l l
i 1
i l (continued)
CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-120a 109/99
.. -. . - . . _ . - .- ._~ =_ .. - .-
ESFAS Instrumentation B 3.3.2 BASES 1-accident analysis. Response Time if_r ~xrific;tica] g.1,1 4 MM acceptance criteria ara ine1 e ___Mad w in the Technical R irements Manual (Ref - , - - , _ _ .
y m ,g 0-3.3 55 1
._.m _ . . . . . _ . . . _ _ _ _ _ . _ _ _ _ . _ _ _ _ . _ . _ . _ _ ;
i M_= -_-
__ -_ g m ,
j cMine JJ iggq3heNc _ i Ma;6'Madgjp:'EMif90 testing'aised?he j M6";MJyMHth~ttilfPpndividual component response j times are m a-sci;d '- t h ;..;. jses. The analyses model the overall or total elapsed time, from the point at which the : parameter exceeds the Trip Setpoint value at the sensor, to the point at which the equipment in both trains reaches the required functional state (e.g., pumps at rated discharge pressure, valves in full open or closed position). For channels that include dynamic transfer functions (e.g., lag, lead / lag, rate / lag, etc.), the response time testing)ay bej verific;tica iCny P.,e performed with the transfer functions ; set t; ea; with the ra;ulting n aur;d ra p= x tin c pered t; i th eppreprieta TSA" ru pea;c ti c. Altera;tcly, the r;; pea;; tin test ;;n bc perferr;d with the tin ceastsats set t; their as;;;ini v;1ue provid;d the 7; quired ra p;a x ti n i; =;1yti;;11y
;;1cul;t;d ;n=ing th; tin cen;t=t; ere set at their nominal i values. The response time may be3easJggd verified by a series of overlapping tests such that the entire response time is men.sted seeseed-mentild.
m aa. _ - - . , - - _. _ - . ~ m __ ] _ _ . _ ~ . e s
, . . . _ _ _ _ _ . _ _ _ _ - _ . . , . - 0 1.1 4 af .i [ ,;?
.c . ; .s 4 jj.sa g 8, } , .e
.....___..____.....'_'..'._'tga' 4
3-0 3.3.ED2 __... _ - , _ _ - _ - ..--,_mm ,.. , m
- - . _ _.-- -.-u._ -. w . m ~,. m . - _ ~ u.v n. u m (continued)
CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-121 1/29M9
- r. , _.- . - . _ . . . -.- . _ . _ . - _ . _ .._ _ .~.-.-. __. _ _ _ -_ -. .
f Containment "gg ad E;'est MM Isolation Instrumentation-8 3.3.6 , , , BASES (continued)' s
..C.1 and C.2 l Condition C applies to ;11 Cat;i.. .w..t - ~ T Z ."ar;; ad Exhs ;t
~
(!=1; tim Tur.; tie.a' ;..d 7.44. ;;x; th; 'Hin erie..;; tis ;f th; 00"0
. r.d tri nt;r ud ;is- ;l;y ' r th;n Tritia.;. It ;i n 1,
_ m ___ mu_ ,_2,..__ _, _., 2_,_ - - _22_ 2__ -- a.__>__ _&____,_ wwws b e e,b e hv N 3 w 5 I we w wa su.as s b s y a E g. wu s w b a vu s v. swr u a wwl sery wriws su es e op . or the inability to restore ; ;ingl; f;iled MI6 l channel to OPERABLE status in the time allowed for Required ; Action A.1. If ; tr;in i; i.~grebic. ;;;;1 tipi; ;hsnel; ;r-ir~rcr;bi;. ;- the Required Action and ' associated Completion Time of . Condition A are not met, operation may continue as long as the ' Required Action to place and maintain containment par;; r.d ;;h=;t yegtilat@g isolation valves in their closed position is met or the aEEl icable Conditions of LC0 3.9.4. " Containment Q-3'3 73 t Penetrations," are met for each valve made inoperable by , failure of isolation instrumentation. A;botalal,1cus:the co!gaijug!!g'ArgeweW11eflyahes2tgKenneGy.m ;fi;wtp3
;;1.acgiglianet211$ggaseouslefDegtimonitotig 1_ettrumettaticFs'agtignantgILjnlatt_MAfithqECMfgThe Completion !
Time for these Required Actions is Immediately. i t
- A Note states that Condition C is applicable during CORE ALTERATIONS and during movement of irradiated fuel assemblies within containment.
. SURVEILLANCE ' A Note has been added to the SR Tab,le tn clarify that -
REQUIREMENTS Table 11 A-1 determines which SRsJ ""5 pply to =nw sun--f,-1= ]N
.a olation Functi _ ,
0 3.3 55
~
- M 4 4 SR 3.3.6.1 c Performance of the CHANNEL CHECK once every 12 hours ensures that a
- gross failure ,.
of instrumentation _, mm_ has _____m__ not occurred. m_2
/, C"_."_"L _ CliECn _ _ , _
- 2. ..~,--_,...,.---__2.._.w__,
- w -rw . . v. b, ~ ev. _ b ,
2., _~; ,, _ w b, w __ _ .u.~...~.
- v. , w, ~ bw g ; -i;;;il;r p;r; ;.tcr en ether ;ter.rel;. It i; b;xd en th; n :- ptien -
mu_m ,__i_.._m m____,_ _ 2 __,__ mu_ ____ ____m__ m _ _, 2 _. 2 Y bt tw b i.ud bl w ws sb bu sus si rw 4 e cruvi s a kwl uypy bu1E ww w ywuu wDW, di Tww I w 5www I' eppraintcly th; n ,. =1 2. Signific=t dai; tion- b;tsu the tw instraat ch ancis cou'd be an indicatica of cacessive instru ~at w drift in se of th; cha,xi er of ..~ thing sca er xrica. A
. CHANNEL CHECK will detect 4
I (continued) f CPSESMarkap ofNUREG-1431 Bases -ITS3.3 B 3.3-169 in9/99
- - . - . . - - .- -.. . - ~ - . ~ _ _ . -. . . - . - - - - . - - . - - - - . - . -
I l Containment ";rg er.d Ed.;;';t Ventilat_14g Isolation Instrumentation B 3.3.6 i f l BASES (continued) , Thc ircqucacy is bcsed on the knc.u relicbility c' the rur.ction cr.d AL. __J..J._.. . . . . J 1.L1. __J L.. L_-- _L_.- A. L. .m.. A.L1. A L _ _ . . _L betw s buus wwun ny uvueeuwew, usrw a su s a -- s 5 durvTna bv ub uwwbybuwaw bu n wwy a ____.A2
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- 2. .~ .
SR 3.3.6.7 f A CHANNEL CALIBRATION is performed every 18 months, or approximately at every refueling. CHANNEL CALIBRATION is a 0 3*3 G-1 L complete check of the instrument loop, including the sensor. The test verifies that the channel responds to a measured parameter within the necessary range and accuracy. j l i l l The Frequency is based on operating experience and is consistent with ; the typical industry refueling cycle. ! l
..~.
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- . . , - , . . , , . . _ _ . _ . _ . .,...__;,____ ____= , _
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*a YLM ---2
. REFERENCES 1. 10 CFR 100.11.
i 1
- 2. NUREG-1366, July 22,1993.
i t i r i-
- - CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-172 1a989
- - _ _ _ ,_ ~ _ _ . . _ _ . _ . . _ , . . _ ... _ _ .. . _ . _ . .._. . __ _ _ _
[ u CHANGE f IDBER JUSTIFICATION
'3.3 23 Modifies'ITS Surveillance Requirement 3.3.4.2 to include power circuits
'per Current TS 4.3.3.2.2. This change is made to match the plant 4 design which includes transfer switches for power circuits as well as control circuits.
j 3.3 24 This change revises improved TS Table'3.3.41 to reflect current g,3'3,3 o TS f3.3.3.2.1]. m.: e . . m , u St. A23333M[gg$leletes
- references to " controls" in the table. (x; ele; CN 3.3 ^A). ad .
;ter,a "";gired "--Mr ;f Turatier t: ""egired Ch;areir ; ire; th; j t;bi; hn Lar, raind t; ir 1;d; aly in;tr ,.7,t; tim. W ]ptggg a l!st(sg g p j ' g g . y S g v.1 .
u, TA83RECLDf14CtMTil tI_lQW6M31!angegjlglel1;ghlableito idspetsfmelagsgegangs!!slaraitunctiam A; raixd. the t;bi; i; ar; .a;i;t;at with the fe. et ;f th; other tabla in 5 Suti= 3.3 ITS erd is tec; .ically the . a as the currcat TS require ats. l' 3.3 25 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3 26 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3 27 This change modifies SR 3.3.3.2 7.r.d 0" 3.3.3.3 t'o allow for. CP.3.3-017 ! different surveillance frequencies for the hydrogen monitors than ; other PAMS components. The manufacturer for the CPSES hydrogen l monitors gens &@0dttlet] specifies a more frequent calibration frequency l than required for the other_PAMS instruments. The more frequent ! calibration is required to assure function operability. 3.3 28 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). 1 3.3 29 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). ; 3.3 30 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B).
-3.3 31 The current TS require the response times associated with the 0 3.3 55
[undervoltage and degraded voltage diesel generator start functions " Ghdtra: cent:1, ; ii.,....,; ens ; ;n;etim furetion;Eto oe ver1rleu ava mn wm wm.nic response Ilme values contained in the [TRM].. The ITS is revised to match the current TS and the response ! time values are [ratained in the TRM]. As is done with the Reactor l Trip System and the ESFAS instrumentation. this method is an l' appropriate way to control reenanw times. [SR 3.3.5.4 and
- NficationsiteTab1MW6j5 " 3.3.5@ are added to require the j response time ver1rication.
J CPSESDifmnessfrom NUREG-1431 -ITS3.3 3 129M9
. . ~ . -- . . . ~ . . - . - . . . . .- - - . --
l l < 1 t I 1 L CHANGE NUMBER JUSTIFICATION 3.3 53 .Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3 54 Function 18.b (P-7) of ITS Table 3.3.11 is clarified toggkjlSJ IIMA~4DBLmp;g. COTS and Channel n.3,3 34 Calibrations apply to the P 10 and P 13 inputs, not to the P 7 logic funetion. EoMgEgggggggs]Lat,eitsstetLDndeErX3Ilj!23This change is an administrative clarification to address the relationships between these interlocks in the plant's design. [There3.s;nohwsingi( TS surve111anceMrKfarlf3Jin1Tablel4I311;T1The:II5;approachlof listjng2SR;3I3l115D0slastjfunctionl18;b.;hasJpteviously1beenlapproved fotJostled i
~
3.3 55 .his cher,se revi,a ITS Z 3.3.1.10 and SR 3.3.2.10 t; verify ~rcquired" _..___..u_.. .n.~-.~, _ _ __- - - .... a . u -- w~- maune .euuw--uum- w-u . --~ ~ m th;x chemcis that Mx n; r; pass tin requir;.i ats pr th; currcat ; li ensing M sis. [As such. linc itc; refer;nc a t; thcs: SRs in l T;bles 3.3.1-1 ad 3.3.2-1 n bc dcicted. T M currcat TS do not iintify which functions Mvc ; rcquired respax ti;c.] The respas ti= li;its =d the iintific; tion of these functicas th;t Mvc required rapax tins r currcatly listed in : liansa l centrolicd deca ,.at. n;t in the caricat TS. This cMasc =kes-the ITS censist;nt with this upct of the currcat '";. [A si;ilar 0-3.3 55 revisien to the ITS 3.3.5 Sn Net; has;;1s; bc a ade rc;;rding SR 3.3.0.3.] Thjgelig)pg",revis4311Hilables231W1Illand13!312111to de])teJappogG81HNst19gygfilM1Hr! cellist _jggs3 SEMI 3R716Dindl ._ 313W101f.oC19125WINW1pantReihajeppitesnonseltiseitestig towLregetsInstidagguttalt31cominglbas1ELTheIce.sponse;tiglimits i and.3he3Rbst1ggggggMfMse2Justjesi$httlhaye2esponspitfee testig:gnquirementsweMJElistedlin3[thC1LMJJ m 3.3 56 This change revises ITS 3.3.2 Condition J to reflect current TS Table [3.3 2]. Action Statement [23a which has been revised and renumbered as 23f in the CTS markup] for Functional Unit [6.e]. [The required action is to place the channel in trip within 6 hours rather than to restore operability within 48 hours.] 3.3 57 Not und. ;ongif6j@jfjtXthi&q5Z(IlliGin6tE252ctifat16r]IgfifMal CP 3.3 005 defjgslggt11nc]Ud6d"@lt*8ddedItOSR913I22?] g' 3.3-58 'Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). t i l 3.3 59 Not applicable to CPSES. See Conversion Comparison Table f (Enclosure 68). CPSES Differencesfrom NUREG-1431 -ITS 3.3 6 in9/99
CONVERSION COMPARIS0N TABLE FOR DIFFERENCES FROM NUREG-1431. SECTION 3.3- Page 6 cf-22 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 3.3-31 The current TS require the response times associated with Yes Yes "; will rct;in
. Yes the [undervoltage and degraded voltage diesel oenerator 5"; in ITS 3.3.1 Q-3.3- 5 -
start function _m.~ --a _ . .. ..-... e;c;til; tion nd 3.2.2 T;bl;;. t.-m;t;n ru .ctir;4to be vern icu ava.m um speci Yes ' Q-3.3-32 response time 23 contained in the [TRM]. The ITS is revised to match the current TS and the response time values are [ retained in the TRM]. As is done with the Reactor Trip System and the ESFAS instrumentation, this method is an appropriate way to m*" . , -- ties. [SR 3.3.5.4 ande=1onsgqlables343,53 5" 3.0.5.g are added to require the re w .x ..- ._ ' "-: .. t . . . 3.3-32 Improved TS H Table 3.3.6-1 is changed to be consistent Yes No - see CN 3.3-73. Yes Yes with current TS [3.3.2 Functional Unit 3.c and current TS 3.9.9].' Subfunctions [b-d] of Containment Radiation are stricken since only the gaseous H channels provide the i Q-3.3-32 actuation function [and the bracketed setpoint is changed to reflect plant- specific requirements]. [The ".ctu; tion L;;;ic u;; ;; lit to rc'icct the SS"S. with only = t 4
@licability and "0" SST,*S r.. tion; nd ;;;;;i;ted Sl1 7;gic;_c.t; in th; cu. . m.. 5.]
3.3-33 Improved TS Table 3.3.7-1 is revised to reflect the plant No - see CN No - see CN 3.3-78. Yes~ Yes design. The CREVS is actuated by radiation monitors 3.3-102. located in the air intakes, by a containment isolation - Phase A signal, by a containment purge isolation signal. by a fuel building ventilation isolation signal. or manually. The bracketed setpoint is revised to reflect current TS Table 3.3 6 requirements. 3.3-34 Revisions to add an LCO 3.0.3 exception Note 1 to ITS 3.3.8 Yes No LCO does not Yes Yes g Q-3.3-34 E reflect cur _rentJS, indu;try tr;acicr 5" 35. apply. EmnummmmemE ' 3.3-35 Improved TS Table 3.3.8-1 is revised to reflect the plant No - not consistent No - LCO does not Yes Yes design. Only the gaseous channels provide the actuation with plant design. apply. function. The bracketed setpoint is revised to reflect current TS Table 3.3 6 requirements. CPSES Conversion Comparison Table -ITS3.3 1/2989
CONVERSION COMPARIS0N TABLE FOR DIFFERENCES FROM NUREG 1431, SECTION 3.3 Page 9 cf 22 TECH SPEC CHANGE APPLICABILITY-NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK. WOLF CREEK CALLAWAY 3.3 49 ITS SR 3.3.1.8 is revised to extend the conditional COT Yes Yes Yes Yes frequency for power and intermediate range channels from 4 hours after reducing power below P-10 to 12 hours, based on operating experience regarding the time needed to perform the COTS. It stands to reason that if 4 hours are allowed for 2 Source Range COTS.12 hours should be allowed for 6 Intermediate Range and Power Range COTS. 3.3-50 ITS SR 3.3.1.12 is deleted per the current TS. Wiere cited No - see CN Yes Yes Yes in Table 3.3.2-1, a change to SR 3.3.1.10 has been made. 3.3-101. 3.3-51 ITS ACTION B.2 of LCO 3.3.7 is deleted, since DCPP cannot Yes No No No operate CRVS with both pressurization systems running at the same time. s 3.3-52 Added Note [(1)] to ITS Table 3.3.1-1 per the current TS as No - adopted ISTS Yes Yes Yes an operator aid to note the dual RTS/ESFAS functions of SG format. Water Level Low-Low. , 3.3-53 The REQUIRED CHANNELS description for Functions 2.a and Yes No No No 3.b.(1), of ITS Table 3.3.2-1, are revised per DCPP CTS to note that only two switches (one per train) exist and that both must be coincident for manual initiation. 3.3-54 Function 18.b (P-7) of ITS Table 3.3.1-1 is clarified to VesNo Yes M; r.d;;tcd 15 Yes g] add3 SR;313,1kSiand; delete;SRj3;3.11 Land SR h3;M13. COTS fermet-yes and Channel Calibrations apply to the P-10 and P-13 inputs, not to the P.7 loaic function. 3.3-55 nb !Z 0" 0.0.1.10 ;d S^ 0.0.2.10 to wrify 'rewircd" M; 0"; will Sc Yes Yes 0"; wi'l Yes Tc
.x tia; R M&. leg- -r--,0;CilaL"Mr rct;i cd '- IIS Tctai ~d '- !TS E Q-3.345 l i
x-.~d; ting t% a cM.. 41; tMt Mx n; ;@.x ti;c T;bic; for rcquired Tabl;; for r;,uir d ] ! r;q t. _ ..;; p;r i k cur.ci.; 'i;;..;ing b;;i;. [?; ;uch, Tunction;. Yes function;. f
'inc i,~ . m .crac. ~ ..~ - ~ . _ . . . . . . . . . . ~
0.0.0 1 c;n k dcicted. ^ ;i;ii;r revi;;;n to the ITS 3.3.S S" M;tc M ; ;l;; k ir. = d; rc erding S" 3.3.S.S.] This< change 1 revises;ITS;TablesJ.31:1;and t 3;3,2 ltto; delete / response 31seitesting;surve11]ancenistingsASRfA311i161and i SR 1 3,2i 10)d otithose lpnctionsa tha Q eM m esponse Jjse
-T -
qgting; requirements; perithe;currentR1 cessing;besis: -- w CPSES Conversion Comparison Table -ITS3.3 1/29/99
.. ~ ~~ .- . - .-- -_ . .. .- - -- - . . . _ .
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 3.3-63 APPLICABILITY: CA, CP, DC, WC l l REQUEST: Revise ITS Table 3.3.2-1 [ Note (g)) per current TS Table [3.3-2) Note [b). This l revision is a clarification to the operator that describes the circumstances under which the l [Steamline Pressure Negative Rate-High function may be blocked when below the] P-11 permissive. Comment: The wording of the applicability notes (b) and (g) in the ITS is more limiting than the CTS applicability, therefore, the change is more restrictive and should be documented as such. The CTS notes that the functions must be operable in Mode 3 but may be blocked below the P-11 setpoint. The ITS does not require operability below the P-11 setpoint in Mode 3. The blocking instruction to the operators belongs in the Bases. FLOG RESPONSE (original): NRC deleted the reference to note (g) at the 9/15/98 meeting. ITS Note (b) has been revised to reflect the intent of CTb # note requirements for DCPP, Callaway, and WCGS, and the (a) note requirements for CPSES, as described in new DOC 2-22-A. ITS note (b) now states that the Functions are required above P-11 and are required below P-11 unless blocked. ITS Note (g) is revised to reflect the CTS ## note requirements for DCPP, Callaway, and WCGS, and (b) note requirements for CPSES. ITS Note (g) now states that the Function is required below P-11; however, it is blocked below P-11 when Si on Steam Line Pressure-Low is not blocked. In addition to these revisions, the CTS ## note for DCPP, Callaway, and WCGS, and (b) note for CPSES, are revised to move the descriptive information related to the automatic blocking of these functions to the bases via DOC 2-50-LG. FLOG RESPONSE (supplement): Based on a telecon with NRC staff on January 12,1999, ITS Table 3.3.1-1 note (b)is revised to read: "Above the P-11 (Pressurizer Pressure) interlock and below P-11 unless the Function is blocked." No additional Enclosure 2, 3A or 3B changes < are needed from those submitted in the original response. The Bases discussion for the affected functions has also been revised to identify which signal is being blocked. ATTACHED PAGES: p Attachment 9, CTS 3/4.3 ITS 3.3
~
Enci5A 3.3-34 and 3.3-37 Enci5B B 3.3-74, B 3.3-75 and B 3.3-88
~ . . -. . . - - . . .- . _
ESFAS Instrumentation 3.3.2 , 4 i I l l Table 3.3.2 1 (page 1 of 10) l l Engineered Safety Feature Actuation System Instrumentation APPLICABLE ! MODES OR l OTHER i SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE U3!35084 l
' FUNCTION COEITIONS CHANNELS CCM)!TIONS REQUIREENTS VALUE" .
t i i
- 1. SafetyInjection ]
- a. Manual Initiation 1.2.3.4 2 B SR 3.3.2.8- NA M
- b. Automatic 1.2.3.4 2 trains C SR 3.3.2.2 NA M Actuation Logic SR 3.3.2.4 and Actuation SR 3.3.2.6 Relays I l
- c. Containment 1.2.3 3 D SR 3.3.2.1 F3.8.psig ; 2.5 p;i; y g.ps q Pressure - High 1 - SR 3.3.2.5 3-86 SR 3.3.2.9 en,-
. ....a SR 3.3.2.10
- d. Pressurizer 1. 2. 3
- Bf D SR 3.3.2.1 i11803 6 . ; 10% p;i; e7g.ps y Pressure - Low SR 3.3.2.5 psig -
SR 3.3.2.9 4639
,o , , , ,
-.,.....o. 3.3-55 SR 3;3.2.10 Q 3*3 55
- e. Steam Line 1.2.3* 3 per SR 3.3.2.1 636 e-675 Pressure steam SR 3.3.2.5 s 593.5 P64f*> m B PS ',~
line D SR 3.3.2.9 psig"3 m Low SR-3-34.49 (Unit:1) SR J 3,2,10 s.;578.4 Ps1g(G (Unit;21 fEHHgh her3 3-pee 9 (0" 3.2.".1] ; [10f,] p;i; t-{97-} 13&OIN
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. . . . . - . . ~ . steem k.ne . . .....
em , , , , 0-i =i ..' m t' her3* 4-pee 9 SR-64-Eri t {Z".C]"" i $2]'i (, - - L;.; L;.; 4eep :" :.:.2.: 93.3;0121
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w CPSESMarkup ofNUREG-1431 - 1TS3.3 3.3 34 12 9199'
. ~ . .
ESF.G Instrumentation 3.3.2 Table 3.3.21 (page 4 of 10) Engineered Safety Feature Actuation System Instrumentation APPLICABLE H0 DES OR , OTHER l SPECIFIED REQUIRED -SURVEILLANCE ALLOWABLE
" 03MM.
FUNCTION CONDITIONS CHAlelELS CONDITIONS REQUIREMENTS VALUEW . I I
- 4. Steam Line Isolation ;
(continued) i
- b. Automatic Actuation 1. 2" > . 3" > 2 trains G SR 3.3.2.2 NA E Logic and Actuation SR 3.3.2.4 Relays SR 3.3.2.6
- c. Contairment 1. 2"'. 3"' 41 D SR 3.3.2.1 sl6,8.psig e4-36 _e3.p31a Pressure - High 2 SR 3.3.2.5 6-61 ps4g SR 3.3.2.9 C 2.2.2.10 SR 3.3;2.10 l
- d. Steam Line Pressure 1,2 "). 3 per D SR 3.3.2.1 635 t-6M - g.ps, a (1) Low 3*"" steam SR 3.3.2.5 05984 ps4g*
line SR 3.3.2.9 594.0 3.3-55 2 0.2.2.10 psig'" Q 3.3 55 SR 3.3.2.10 (Unit:1) (578.4 : psig(d CP 3.3 016 (Unit.2) (2) Negative 34"" 3 per D SR 3.3.2.1 sl178,75 5-140 y B.p$ a Rate - High steam SR 3.3.2.5 psi ps44ee* line SR 3.3.2.9 441,6 m 2.2.2.10 ps#see SR.3;3;2.10
- . "i s ::: = ri u '- T.: 4,a%3* e-pee o a 2.:.r.1 M m a3c3 0 N
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T,,, --- L= Lu 3** 4eep {}.j.{.6 C :.2.2.n (continued) $3:3-084 (a) ' nevi s r *: ";t:-. L'ait w;i'i: i:pi-.. :tta ny _.;;i, ;;1y f'1w:.tk nix a ..r din; :n Rtp:11 ::.dj ntbik;y =:d by tk c 't ThelllM1eyal.u[ defines;the31miting ;safetyisystem 3.3-63 591$1992 ses ths;Beseiilf6ifthi3fp~Bitp61i)(C ' O.3.3 63 (b) AbovetheP11(PressurizerPressure)Interlockand,bglow:P-317pnless heJunct_1on biccked. WPB 2? t c3.3e633 (c) Time constants used in the lead / lag controller are ti a SQ seconds and t, s 5 seconds. CP 3.3 ED (g) Below the P 11 (Pressurizer Pressure) InterlockQaweyerg]ney)[b]ockeQeloG11:WeO8fety 1Alection3s3eesteasjifucpressurpM10et>]ockedl T3.34124 (h) Time constant utilized in the rate / lag controller is s R50 seconds. ag;pg q'3 (1) Except when all MSIVsiand,the1C3ss9ciatedJpstreadJrJp;po41sg]ationJalles are closed;and w eg. c
~.313-62a CPSESMarkup ofNUREG-1431 - ITS3.3 3.3-37 1/29/99
ESFAS Instrumentation ! B 3.3.2. l BASES j l
' APPLICABLE d. Safetv In.iection-Pressurizer Pressure - Low l SAFETY ANALYSES, (continued)
LCO, and , APPLICABILITY This Function must be OPERABLE in H00ES 1, 2, . l U* 3 and 3 (above P 117end~belthiCPjJ173]g_ Lod Sa1at1 D M imwu-s w u.ma m miEl Flinctiep)3h; w mmgate me consequences of an HELB inside containment. This j signal may be manually blocked by the operator below 1 the P 11 setpoint. Automatic SI actuation below this pressure setpoint is then performed by the Containment Pressure-High 1 signal. This Function is not required to be OPERABLE in H0DE 3 below the P 11 setpoint. Other ESF functions are used to detect accident conditions and actuate I the ESF systems in this H0DE. In H0 DES 4, 5, and 6. )
' this Function is not needed for accident detection i and mitigation. ,
- e. Safety In.iection-Steam Line Pressure j Mt Steam Line Pressure-Low Steam Line Pressure-Low provides protection against the following accidents:
l
= SLB:
a Feed line break; and
. Inadvertent opening of an SG relief or an SG safety valve.
Steam Line Pressure-Low provides no input to any control functions. Thus, three OPERABLE channels on each steam line are sufficient to satisfy the protective requirements with a two-out of three logic on each steam line. (continued) CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-74 U29M9
ESFAS Instrumentation B 3.3.2
'. BASES APPLICABLE ~ H+ Steam Line Pressure-Low (continued):
SAFETY ANALYSES,. LCO.-and .. With the transmitters typically located APPLICABILITY inside the steam tunnels, it is' possible for _ them to experience adverse environmental l conditions during a secondary side break. j
. Therefore, the. Trip Setpoint reflects both 1 steady state and adverse environmental i
. instrument uncertainties.
,, This Function is anticipatory in nature and has a tgial lead / lag ratio of 50/5.
. ~ .
Steam Line Pressure-Low must be 0 3*3 63 OPERABLE in MODES 1, 2, and 3 (above P 11 an6 be1oW 9511,*:en W k jafasy [Injectjony;steamitne Pressurev Low _ LFunction'istoym.mau) when a secondary side break or stuck open valve could result in the rapid depressurization of the steam lines. This signal may be manually blocked by the operator below the P 11 setpoint. Below P 11, feed line break is not
.a concern. Inside containment SLB will be terminated by automatic SI actuation via Containment Pressure-High 1, and outside containment SLB will be terminated by the Steam Line Pressure-Negative Rate-HirA )
signal for steam line isolation. This Function is not required to be OPERABLE in MODE-4. 5, or 6 because there is insufficient energy in the secondary side of the unit to c;,; = ncident. IDipficc_qtern) (2) et : ' i : "rs =: ::i ' Oiffer ntial n____..__ o u.___ c.___ i,___ St = Line "rc ;;ra llip. Oifferential
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' &PSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-75 1/29 M l i
H ESFAS Instrumentation f( B 3.3.2. BASES-l
' d. Steam Line Isolation-Steam Line Pressure
'(1)' Steam Line Pressure-Low i I
J Steam Line Pressure-Low provides closure of the i MSIVs in the event of an SLB to maintain at least one - unfaulted SG as a heat' sink for the reactor, and to limit the mass and energy. release to containment. l This Function provides closure of the MSIVs in the event of a feed'11ne break to ensure a supply of steam - l- for the turbine driven AFW pump. Steam Line Pressure-Low was discussed previously under SI L Function 1.e.l. L Steam Line Pressure-Low Function must be OPERABLE-in MODES 1, 2. and 3 (above P 11), with any main steam L valve open, when a secondary side break or stuck open L valve could result in the rapid depressurization of the steam lines. This-signal may be manually blocked by the operator below the P 11 setooint. 0 3.3 63 mm:_ m tud w p;tigg .._ , ;g,gge:pgq _M $I8in 3 - ;' LEst!
, an inside containment SLB will be terminated by. automatic actuation via Containment Pressure-High 2. Stuck valve transients and outside containment SLBs will be terminated by the Steam Line
,, Pressure-Negative Rate-High signal for Steam Line Isolation -- (1) Staam Line Pressure-Low (continued) below P-11 when SI has been manually blocked. The Steam Line Isolation Function is required in 0-3.3 G 1 MODES 2 and 3 unless all MSIVs are closed and M. This Function is not required to be OPERABLE in MODES 4, 5 and 6 because there is insufficient energy !' in the secondary side of the unit to lgMR SEENU cP-3.3 ED2 L L (2) Steam Line Pressure-Neaative Rate-Hiah
~
Steam Line Pressure-Negative Rate-High provides closure of the MSIVs for an SLB when less than the P-11 setpoint to maintain at least one unfaulted SG as (continued) CPSES Marksy ofNUREG-1431 Bases -ITS 3.3 B 3.3-88 10939
i ! ADDITIONAL INFORMATION COVER SHEET i
' ADDITIONAL INFORMATION NO: Q 3.3-73 APPLICABILITY: CP l - REQUEST: The CPSES CTS actions for inoperable functions are retained in the ITS.
Comment: To retain the CTS Action, manual initiation must be listed with T3.3-2 Action 15 equivalent actions in the ITS. FLOG RESPONSE: As agreed upon during the meetings held between the NRC staff and the FLOG members during the week of September 14,1998, the ITS 3.3.6 Condition B, Required Action B.1, Condition C, and Required Action C.1, including all associated Notes and completion times, have been revised to more accurately reflect the CTS requirements in the iTS format. Similar changes are made to ITS Table 3.3.6-1. No changes to the CTS requirements are necessary.
- FLOG RESPONSE (supplement)
- The completion time for Condition B was inadvertently not l revised to be "immediately" in the previous response to O 3.3-73 and is now changed in this supplement.
ATTACHED PAGES: Attachment 9, CTS 3/4.3 -ITS 3.3 Enct5A 3.3-58 l l l
i 1 t Containment @elitilgjg "urg; :nd Cf.:.;;t Isolation Instrumentation r% PS M 3.3.6 ACTIONS (continued) l CONDITION REQUIRED ACTION COMPLETION TIME B. - -
---NOTE --
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o l ADDITIONAL INFORMATION COVER SHEEi ADDITIONAL INFORMATION NO: Q 3.3 - APPLICABILITY: CP . l. REQUEST: ' The modifications to the improved TS are consistent with both the intent of the improved TS and the CPSES CREFS design and current TS. Comment: Revise the Note to Required Action B.2. Copy the Note to proposed Required Action A.2. {CP} Add NUREG actuation logic and actuation relay surveillance test requirements for
. CREFS actuation.
FLOG RESPONSE (original): The Note in Required Action B.2 has been revised to adopt the - l
' STS format. The revised Note is also applied to Required Action A.2. Because the CREFS
. logic consists of a single relay, there is no setpoint to be verified during the performance of a TADOT per SR 3.3.7.6. The surveillance SR 3.3.7.2 (a Channel Operability Test) was added to '
- the Automatic Actuation Logic and Actuation Relays Functional Unit. These actions are consistent with those agreed upon at the meetings held between the NRC staff and the FLOG members during the week of September 14,1998.
FLOG RESPONSE (supplement): The Bases description for the Automatic Actuation Logic and Actuation Relays and for SR 3.3.7.2 are revised to be consistent with the CPSES plant specific design for actuation logic.
- ATTACHED PAGES: i
' Attachment 9, CTS 3/4.3 - ITS 3.3 . f L Enci58- B 3.3-175 and B 3.3-179 .
> i 1
l l l:
yr O L D CREFS Actuation Instrumentation B 3.3.7 1. i BASES t l
- 2. Automatic Actuation Loaic and Actuation Relays (continued) a- Automatic Actuation L i i consis
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- 3. Control Room Radiation i
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a For sampling systems. channel OPERABILITY involves more than j OPERABILITY of channel electronics. OPERABILITY may also
- require correct valve lineups, sample pump operation-and K filter stor egr: tier,. as well as detector OPERABILITY, if these supporting features are necessary for trip to occur under the conditior.s assumed by the safety CP-3.3 ED p analyses.
1
- 4. ' Safety In.iection L Refer to LC0 3.3.2. Function 1. for all initiating u Functions and requirements.
l1 l l CPSESMarkup ofNUREG-H31 Bases -ITS3.3 B 3.3-17S. U29M9
. - = . - - . .. . . ... -. --
CREFS Actuation Instrumentation I L B 3.3.7 l BASES deviations between the two instrument channels could be an indication of excessive instrument drift in one of the channels or i of something even more serious. A CHANNEL CHECK will detect gross I ! channel failure: thus, it is key to verifying the instrumentation conoinues to operate properly between each CHANNEL CALIBRATION. j 1 Agreement criteria are determined by the unit staff, based on a combination of the channel instrument uncertainties, including indication and readability. If a channel is outside the criteria, it may be an indication that the sensor or the signal processing equipment has drifted outside its limit. The Frequency is based on operating experience that demonstrates channel failure is rare. The CHANNEL CHECK supplemer. less formal, but more frequent, checks of channels during normal operational use of the displays associated with the LCO required channels. SR 3.3.7.2 A COT is performed once every 92 days on each required channel to ensure the entire channel will perform the intended function. This test verifies the capability of the instrumentation to provide the CREFS actuation. The setpoints shall be left consistent with the unit specific calibration procedure tolerance. The Frequency is based on the known reliability of the monitoring equipment and has been shown to be acceptable through operating experience. IMECUTJuntiBallpratinicgNat@]lDMDirlMtRotoolt.orj - CP 3.3 ED MtifjM110Li;WREE Z"TSDDriitanf'and tECREEEE3B&11gHtt01m@jt4!!gggggggleslitej,yu! Obb unfer x.rnanAngic3M!8gtigqLigilMINR] SR 3.3.7.3 Not'Usejd SR 3.3.7.3 i: the grf;r=nce of = AC"JATION LOCIC TER. The train bcing testcd is pis = d in the bpass condition, thus prcycating inadvertent actuation. Through the sc:icutc= tic tester, 011 p;ssibic logie-coabi=tiens, with and without applicabic Fraissivcs, are tested for =ch protection-function. In edditica, the = ster relay coil is puls; tested f;r continuity. This verifi= that .the logic acdules arc OPERASLC =d there is an intact voltcg: sig=1 path to the = ster reicy coils. This test is l perfer= d cvery 31 days on a STACCEREO C T SASIS. The Trcquency l i justificd in L'C'J' 10271 P A. Suppic;=t 2. Rcv.1 (Ref.1). s CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-179 1/2989
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 3.3-96 APPLICABILITY: CA, CP, DC, WC REQUEST: [ Note 2 for ITS SR 3.3.1.2 is revised to replace the bracketed 12 hour time constraint with 24 hours. No such time limit is contained in the current TS, which has an SR 4.0.4 exception. The performance of ITS SR 3.3.1.2 should be provided sufficient time to perform the initial comparison and gain adjustment, equal to the SR frequency.] Note 2 for ITS SR 3.3.1.3 is revised to replace the bracketed 15% RTP power level constraint with 50% RTP. The specified power level in ITS SR 3.3.1.3 should reflect the applicable safety analysis basis consistent with the [ Applicability and] Required Actions of ITS LCO 3.2.3 (AFD) and LCO 3.2.4 (OPTR). Comment: Reject - Scope issue - because ITS Note 2 to SR 3.3.1.2 and Note 2 to SR 3.3.1.3 proposes 24 hours for delay in performing the SR which are generic changes to STS that are not included in an approved TSTF. The justification is inadequate. Adequate justification would be the format is not usable, or the requirements represent unsafe practices or may result in an operational hardship. Note [DC] ITS markup missing "3.3-96" annotation. Reject 50% RTP in Note 2 to SR 3.3.1.3. FLOG RESPONSE (original): The justification for the proposed changes, originally provided in JFD 3.3-96, will be modified to include more detailed information conceming the application of the CTS 4.0.4 exception to these surveillances. The following has been added to JFD 3.3-96:
"These proposed changes address the current practices conceming the application of the CTS 4.0.4 exception to various STS surveillance requirements.
For DCPP, the plant-specific revision to SR 3.3.1.2 necessary to incorporate the CTS is described in JFD 3.3-47. For Callaway, CPSES, and WCGS, the proposed change to STS SR 3.3.1.2, Note 2, is provided to thco'rporate the SR 4.0.4 exception provided in the equivalent CTS survtiljance, contained in CTS Table 4.3-1, Note (2). The current practice conceming the application of the CTS 4.0.4 exception is to defer the first required calorimetric measurement and the associated normalization of attemate power indications until a scheduled testing plateau is attained during the post-refueling outage power ascension. Typical post-refueling outage power ascensions include a power increase to approximately 30% RTP; although, the current practice of some plants is to achieve a power plateau nearer to 50% RTP. Using typical power ascension rates of 3% RTP/ hour,5 to 12 hours are required to reach the first scheduled power plateau above 15% RTP. Based on plant experience, after a specified power plateau is attained, approximately 2 hours are required to stabilize the plant and perform the calorimetric measurement. Two additional hours are required to make any necessary adjustments to the Nuclear Instrumentation System ( ) power indications. The proposed 24 hour time frame also provides a reasonable allowance during which the affects of equipment failures may be addressed. For example, if the plant computers are not available, some additional time is required to manually collect the data and perform the required calculations. The proposed 24-hour allowance after increasing THERMAL POWER above 15% RTP provides a reasonable time to attain a scheduled power plateau, perform the required calorimetric measurement, and > ' make any required adjustments in a controlled, orderly manner. Plant procedures provide guidance concoming the use of all available power indications [(e.g., NIS and loop AT)] during a y
power ccension. Any significant inconsist:ncies would be resolved through the performance of a calorimetric measurement. Based on the current, conservative operating practices and the fact that secondary plant calorimetric measurements are typically more accurate when performed at higher power levels, it is not necessary to require a formal calorimetric comparison to be performed prior to exceeding 15% RTP. The note has sufficient limitations to ensure the plant is operated in a safe manner. Note 2 to STS SR 3.3.1.3 addresses the conditions required to perform the incore-excore comparisons of AFD. The STS includes an allowance of 24 hours (within orackets) after exceeding a specified power level for the first performance of this surveillance. The proposed change to the time allowance of STS SR 3.3.1.3, Note 2, would adopt the 24 hour allowance, but specify the power level to be 50% RTP. The change is predicated on the current practices conceming the application of the CTS 4.0.4 exception to the CTS (e.g., for Callaway, CTS Table 4.3-1, Note (3)). Current practice is to perform this surveillance at a power level below 50% RTP. Based on plant operating experience,24 hours is a reasonable time frame to limit operation above 50% RTP while completing the procedural steps associated with the surveillance in an orderly manner. The deferral of the power level above which UR 3.3.1.3 is required to be satisfied is also consistent with current operating practices conceming the application of CTS 4.0.4. Due to such effects as shadowing from the relatively deep control rod insertion and, to a lesser extent, the dependency of the axially-dependent radialleakage on the power level, the relationship between the incore and excore indications of axial flux difference (AFD) at lower power levels is variable. Thus, it is prudent to defer the calibration of the excore AFD against the incore AFD until more stable conditions are attained (i.e, withdrawn control rods and a higher power level). The AFD is used as an input to the overtemperature reactor trip function and for assessing compliance with ITS LCO 3.2.3, " Axial Flux Difference." Due to the DNB benefits gained by administratively restricting the power level to 50% RTP, no limits on AFD are imposed below 50% RTP by LCO 3.2.3; thus, the proposed change is consistent with the LCO 3.2.3 requirements below 50% RTP. Similarly, sufficient DNB margins are realized through operation below 50% RTP that the intended function of the overtemperature reactor trip function is maintained, even though the excore AFD indication may not exactly match the incore AFD indication. [Further, current practice at many plants is to administratively reduce the Power Range Neutron Flux - High setpoint until this and other surveillances (e.g., peaking factors) have been completed and it has been demonstrated that the plant is ready for sustained operation at full power in accordance with the design and licensing basis.} In summary, the proposed changes are more restrictive than the CTS, but are consistent with the current operating practices conceming the application of the CTS 4.0.4 exception to the equivalent CTS surveillances. The proposed changes allow power ascensions and associated testing to be conducted in a controlled and orderly manner, at conditions that provide acceptable results and without introducing the potential for extended operation at high power levels with instrumentation that has not been verified to be acceptable for subsequent use." FLOG RESPONSE (supplement): Based on feedback received from NRC staff during a telecon on January, 12,1999, the Bases for ITS SR 3.3.1.2 and SR 3.3.1.3 have been revised to capture salient points from the justifications provided in the original response. ATTACHED PAGES: Attachment 9, CTS 3/4.3 - ITS 3.3 Enci 58 B 3.3-52 and B 3.3-52a
.. - - - - . . ~. . .-.-....-.-.- - . . . - - - -
RTS Instrumentation B 3.3.1 BASES power is a 15% RTP and that 12 EhourgMg 4s allowed for performing the first Surveillance after reaching 15% RTP. At @
.....,.._______....._......._.._..,.4_ . . . . ,
MU A.; 1.1 -.oc b 1 d u A d r_s qlged esamesumaner-meauemmene esmerni 9mmfrewbrinehtfMemmMal l w s - .nanenemmi-amme - t R hj! G REggt!R g t 6 3 Mujugoggt3 se h The Frequency of every 24 hours is adequate. It is based on unit operating experience, considering instrument reliability and operating history data for instrument drift. Together these factors demonstrate the change in the absolute difference between NISZNils and heat balance calculated powers rarely exceeds 2* in any 24 hour period. In addition, control room operators periodically monitor redundant indications and alarms to detect deviations in channel outputs. SR 3.3.1.3 SR 3.3.1.3 compares the incore system to the NIS channel output every 31 EFPD. If the absolute difference is 2 3%, the NIS channel is still OPERABLE, but must be readjusted. If the NIS channel cannot be properly readjusted. the channel is declared inoperable. This Surveillance is performed to verify the fief +gMI input to the overtemperature trFEQQ Function. . Two Notes modify SR 3.3.1.3. Note 1 indicates that the excore NIS channel shall be adjusted if the absolute difference between the incore and excore AFD is 2 35 58BgtigitH9131f9g3RM ote 2 clarifies that 1 the Surveillance is required only if reactor power is CP-3.3 ED 2-164jggRTP.andthat24hoursisallowedforperformino U the first Surveillance after reaching M4 508 RTP/TiotG*2h
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'RTS Instrumentation B 3.3.1 BASES t ut . ..
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' 8!getiweggl!mpttgggggre2NfMlggtigitt,1p1f_ unction;is l mIhistaged;MeeBhopift3hGtuoteZEk!dicatigmay;norexactly unchith0fterMD11Mina11a7Lsagfdxplant aperating elgriege2lprhaws11sramreasonableJAime;framex11.mitt operatjgtatsteMRMleMleQng1the:procedura1Xstep L
isteditth:theIsurgillance31nMorderly manner % . l The Frequency of every 31 EFPD is adequate. It is based on unit operating experience. considering instrument reliability and-operating history data for instrument drift. Also. the slow changes in neutron flux during the fuel cycle can be detected during this interval. SR 3.3.1.4 SR 3.3.1.4 is the performance of a TAD 0T every 31 days on a STAGGERED TEST BASIS. This test shall verify OPERABILITY by actuation of the end devices. 1 CPSES Markup ofNUREG-1431 Bases - ITS 3.3 B 3.3-52a 1/29/99 l
l i ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 3.3-97 APPLICABILITY: CA, CP, DC, WC i
' REQUEST: The NOTE for SR 3.3.1.6 of ITS 3.3.1 has been revised to state "Not required to be performed until 72 hours after achieving equilibrium conditions with THERMAL POWER 2 75% RTP". This is consistent with the current TS Functional [ Units 2.a and 7] surveillance requirement of Table 4.3-1, as modified by Note (6) and current operating experience of l
72 hours for performing the SR.
- Comment: Reject - The JFD statement regarding equilibrium conditions: "This is consistent with the current TS Functional [ Units 2.a and 7] surveillance requirement of Table 4.3-1, as modified by Note (6)". This JFD does not appear to be consistent with CTS as the JFD states. The CTS note 6 only refers to incore-Excore calibration above 75% of RTP. The portion about " equilibrium" is added to the CTS Note (6) in Enclosure 2 as redline.
Provide data to support the statement that operating experience shows 72 hours is required to perform the SR. FLOG RESPONSE (original): For Callaway, CPSES, and WCGS, the justification for the proposed changes, originally provided in JFD 3.3-97, will be modified to include more detailed information about the current practices conceming the application of the CTS 4.0.4 exception to this surveillance. For DCPP, plant-specific justification is provided in JFD 3.3-06. For Callaway, CPSES, and WCGS, the following has been added to JFD 3.3-97:
"These proposed changes address the current practices conceming the application of the CTS l 1
. 4.0.4 exception to STS SR 3.3.1.6.
i The proposed changes to the STS SR 3.3.1.6 Note a~e provided to incorporate the SR 4.0.4 exception provided in the equivalent CTS surveillance (e.g., see Callaway CTS Table 4.3-1, l _ Note (6)). For CPSES and WCGS, the current practice conceming the application of the CTS l 4.0.4 exception is to defer the multi-point incore-excore calibration until a scheduled testing plateau above 75% RTP !s attained during the post-outage power ascension. Based on plant l L
~
experience, it is necessary to perform this calibration at power levels at or above 75% RTP. , l During a post-refueling power ascension, it is usually necessary to control the axial flux difference at lower power levels through control rod insertion. For example, at CPSES, it was l i
- determined that a multi-point calibration performed well below 75% RTP resulted in excessive i
. incore-excore axial flux difference deviations at 'ull power. The deviations were attributed to rod
- shadowing effects on the base flux map and, to a lesser degree, the dependency of the axially-
- dependent radial leakage on the power level.
To collect the data necessary to satisfy this surveillance requirement, it is first necessary to l obtain equilibrium conditions at the appropriate testing plateau. A full-core " base" flux map is ! obtained. The control rods are then inserted into the core to initiate a swing in the axial flu'x j difference (AFD). Several partial flux maps are then collected at various values of AFD. Based on plant operating experience, failures in the flux mapping system can result in extended data collection times. The plant is then retumed to a stable condition. The test data is then analyzed and reduced, and the appropriate calibration data for the excore data is calculated. The excore
.-a.. n -
s 4 e < -e -- ry - w y -
detectors are then adjusted, as necessary. Based on plant experience, after equilibrium conditions are achieved at the specified power plateau, approximately 24 hours are required to perform the base flux map, initiate the required AFD swings, and collect the required data. The data is typically analyzed and the appropriate excore calibrations are completed within the following 24 hours. Based on plant operating experience, an additional time allowance of 24 hours is provided during which the effects of equipment failures may be remedied and any required re-testing may be performed. For Callaway, a similar sequence is used during the post-outage power ascension; however, a single-point incore-excore calibration methodology is utilized ratt.er than a multi-point methodology. Since an AFD swing and partial flux maps are not required, the time for performing the flux map and collecting the required data is less than the 24 hours discussed above (typically 4 to 6 hours duration). Similar to CPSES and WCGS, the subsequent _48 hours allow for the performance of excore calibrations and provide an allowance during which the effects of equipment failures may be remedied and any required re-testing may be performed. [Further, current practice at many plants is to administratively reduce the Power Range Neutron Flux - High setpoint until this and other sunreillances (e.g., peaking factors) have been completed and it has been demonstrated that the plant is ready for sustained operation at full power in accordance with the design and licensing basis.] In summary, the proposed changes to STS SR 3.3.1.6 are more restrictive than the CTS, but are consistent with the current operating practices conceming the application of the CTS 4.0.4 exception to the equivalent CTS surveillance. The proposed changes allow power ascensions and associated testing to be conducted in a controlled and orderly manner, at conditions that provide acceptable results and without introducing the potential for extended operation at high power levels with instrumentation that has not been verified to be acceptable for subsequent use." FLOG RESPONSE (supplement): Based on feedback received from NRC staff during a telecon on January 20,1999, the Bases for ITS SR 311.6 have been revised to discuss equilibrium conditions and to capture salient points from the justification provided in the original . response. ATTACHED PAGES: Attachment 9, CTS 3/4.3 - ITS 3.3 Enci5B- B 3.3-53 and B 3.3-53a
RTS Instrumentation B 3.3.1 BASES
~
The RTB test shal1 1nclude' separate verification of the undervoltage and shunt trip mechanisms. Independent verification of RTB undervoltage and shunt trip Function-is not required for the bypass breakers. No capability is provided for performing such a test at power.. The independent test for bypass breakers
' is included in SR 3.3.1.14. The bypass breaker test shall include a local Mshunt trip. . A Note has been added to
- indicate that this test must be performed on the bypass breaker prior to placing it in service.
The Frequency of every 31 days on a STAGGERED TEST BASIS is adequate. It is based on industry operating experience, considering instrument reliability and operating history data. SR 3.3.1.5 SR'3.3,1.5 is the performance'of_an ACTUATION LOGIC TEST. The
' SSPS is tested'every 31 days on a STAGGERED TEST BASIS. using the semiautomatic tester. The train being tested is placed in the bypass condition. thus preventing inadvertent actuation. Through the semiautomatic tester, all possible logic combinations, with
- and without applicable permissives, are tested-for each' protection function. 'The Frequency of.every 31 days on a STAGGERED TEST BASIS is adequate. It is based on industry operating experience, considering instrument reliability and operating history data.
SR 3.3.1.6 SR 3.3.1.6 is a calibration of the excore channels to the incore channels. If the measurements do not agree, the excore channels
+
are not declared inoperable but must be calibrated to agree with the incore detector measurements. If the excore channels cannot be adjusted, the channels.are declared inoperable. This Surveillance is performed to verify the ffcEG8H input to the overtemperature efM Function. A Note modifies SR 3.3.1.6. The Note states that this Surveillance is required only if reactor power is > 50 jZip RTP and that fe4} Eghours is allowed for performing the first surveillance after reachingM11brgp3fggittern 504 RTP m w _ , u D tH!j 0 3.3 97 _. M3RE1510!N pqg.. ,. .. r .- . . , . , ..% 3,3 .m pag!r f.na % wo r w- 1,malgaLolitgestal I fhlEdifffMGWNamaeM0L*ttiroach;contr.elmed j q CPSES Markagr ofNUREG-1431 Bases -ITS 3.3 . B 3.3-53. 1/29/99 i _h______-___.___ __
. . . . _ . _ . _ . . - . . _ . . . - . ~ . . -. . . .- . . _ . . . _ . . _ _
RTS Instrumentation B 3.3.1 BASES' N ' 1NBC$ llNMMM3!an 0-3.3 97 i . .
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- provide .
Mlff9stLitslWWitho0t11ntroducingithe]~pptentfa.1;for extende!LapetetiggiatIhighjpowerdleyelsMth;jnstrumenta_ tion:t haCnot'bieAngPtfied!!to"beyaccontableTfor:submupMt Use' u benefitigalDetDy1 operating;atguced;powerMevel s;i si;sulficient
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. CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B3.3-S3a 1/29/99
._ . _ .. _ . . _ . . . _ . _ . . . _ _ _ . _ _ - _ - ~ . _ . _ , - . _ _ . _ _ _ _ _ . _ . . _ . . _
ADDITIONAL INFORMATION COVER SHEET
- ADDITIONAL INFORMATION NO: CP 3.3-ED1 (new) APPLICABILITY: CP ,
REQUEST: Based on feedback received from the NRC reviewer, the following Bases pages for LCO 3.3.1 have been revised as noted on the attached pages. In addition, a licensee identified correction was made on page 7 in enclosure 3b. In addition, Bases page B 3.3-59 and B 3.3-60 were modified to provide > clarifications based on plant input. A1TACHED PAGES:
- Attachment 9, CTS 3/4.3 - ITS 3.3 Enci3B 7- 1-37-A is actually 1-37-M Enci5B B 3.3-1, 2, 4a, 7,12,16,17,18, 23, 24, 33, 34, 36, 48, 49, 55, 56, 57, 59, 59a and 60 f
a e i M. I f b F 4
._ _ ,, _. ., c 6 _ , , . -
. . . , ; m n ce m. - . _y -,
- .-..n . - - ,.. -
- ~ . . .- . - ,.
..- CONVERSION CONPARISON TABLEi- CURRENT TS!3/4.3- Page' 7 cf 22' ~
1 e a
=
h ,t APPLICABILITYi
. TECH SPEC CHANGE ;
n .i Nl#SER DESCRIPTION ~ DIABLO' COMANCHE WOLF CREEK Call.AWAY - CANYON' PEAKi 1-33 The BONS actuation SR is chtaged to allow the use cf an actual signal.;1f and No - not in- No - not in No - not 'in - Yes' . TR-1 when one occurs, to satisfy surveillance requirements. current 15. current TS. current TS. 1 34 : Callauay's current ACTION Statement S.b requirements for two inoperable source No No No YesL ' A: range channels are divided between the reactor. trip, indication, and. BONS functions served by the source range channels.- New ACTION Statement 4.1. added- ' to current TS Table 3.3-1 retains _ the requirement to open the reactor trip Q-1-30 breakers to serve the reactor trip function. - The ACTION Statement 5.b requirements that are not related to reactor trip are moved to ITS 3.3.9. See i ' also CN 1-30-N. A gndalsbje;4,3 liSS' , em. a-am maan a s2 No-alreadyT 1-35' This change moves response time limit tables to the updated FSAR per Generic- Yes. No - already No - already ' ,
? . LG Letter 93-08 and NUREG-1431 Rev. 1. moved to TRN. moved to USAR moved to FSAR Section 16.3. Section 16.3.
l' 1-36 This DCPP specific change adds a requirement to perform a Channel Calibration on Yes No - No No 1 LS$3 Functional Unit 17 every 18 months. 1- In the current TS. the minimum Channels OPERABLE" is one less than tfiiiilitat--- . s Yes Yes- Yes- ' Q 3.3-4d- ' q Number of Channels" for Functional Units' [18.c] (P-8). [18.d](P-9).' and q [18.e](P-10) in Table 3.3 1 and Functional Unit [10.a](P-11) in Table [3.3-2]. j For these Reactor Trip System and ESFAS interlocks, current ACTION Statements [7 ; and 18] for an inoperable channel are based on the Minimum Channels OPERABLE" ! columns in Tables 3.31 and [3.3-2]. In the improved TS. only the " Total Number N .j of Channels" information is retained in the LCO and that column is relabeled as ! l the 1equired Channels". as discussed in CN 1-04-LG and CN 1-43-A. Required Actions in improved TS 3.3.1 Conditions S and T and improved TS 3.3.2 .:
- i. CP-3.3 El i !
Condition L are tied to the Required Channels. 6 889Btyddd$ltestgegj6)piLMitte3351ggdfe; tug - I 1 n.. a. .. :r . .s.x:
,~. .;; . .; , " b %- ;;~ T ~;;;d " nit; ; ; . ..;;;d 17 tr.; ;, . .,; ";. l Refer also to CN 1-51-LG for P 7.
i 1-38 The scurce range channel operability requirements in NODES 3. 4. and 5 when No - see CN 1- Yes - Yes - No - see CNs 1-l R incapable of rod withdrawal are relocated to a licensee controlled document. 09-N relocated to relocated to 10-LS-32, 1-307 }' TRN Chapter 16.3 N.'and 1-34-A. of the USAR. CPSES Conversion Comparison TnNe CTS 3M.3- _ H2939 l
RTS Instrumentation B 3.3.1 B 3.3 INSTRUMENTATION B 3.3.1 Reactor Trip System (RTS) Instrumentation BASES BACKGROUND The RTS initiates a unit shutdown, based on the values of selected unit parameters. to protect against violating the core fuel design limits and Reactor Coolant System (RCS) pressure boundary during anticipated operational occurrences (A00s) and to assist the Engineered Safety Features (ESF) Systems in mitigating ! accidents. The protection and monitoring systems have been designed to assure safe operation of the reactor. This is achieved by specifying limiting safety' system settings (LSSS) in terms of parameters directly monitored by the RTS, as well as specifying LCOs on other reactor system parameters and equipment performance. The LSSS, defined in this specification as the Trip Setpoints Allowable; Values, in conjunction with the LCOs, establish the threshold for protective system action to prevent exceeding acceptable limits during Design Basis Accidents (DBAs). During A00s, which are those events expected to occur one or more times during the unit life, the acceptable limits are:
- 1. The Departure from Nucleate Boiling Ratio (DNBR) shall-be maintained above the Safety Li;;;it (SL) voluc to pr;;;nt f,eportura fre;;; aucle te boiling (=);Zdeparture;f, om r nec.13atibo111ngItttjp3DRBBDUnity
- 2. Fuel centerline melt shall not occur: and
- 3. The RCS pressure SQfetyT,L)mity of 2750 psie 2735 CP-3.3 ED1 ps.Tshall not be exceww. ~
~
Operation within the S+s limits of Specification 2.0, " Safety Limits (SLs)." also maintains the above values and assures that offsite dose will be within the 10 CFR 50 and 10 CFR 100 criteria during A00s. continued CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-1 1/2989
j .- I: ~ L 'RTS Instrumentation '
- B 3.3.1 BASES .
l L .. . .. l' BACKGROUlm Accidents are events that are analyzed even ,though they are not ,
'(continued) expected to occur during the unit life. The acceptable limit during accidents is that offsite dose shall be maintained within L an acceptable fraction of;10 CFR 100 limits. Different accident categories are allowed a different fraction of these limits, based on probability of occurrence. ~ Meeting the acceptable dose limit for an: accident category is considered having acceptable i consequences for that event.
The RTS instrumentation is segmented into four distinct but' 9 interconnected modules ;; illa:treted in ri;;r; [ ],a5 CP 3.3 ED i, descrit!adKMFSAR, Chapter E7-} (Ref.1) . and as L identified L below:
- 1. Field transmitters or process sensors: provide a measurable electronic signal based upon the physical characteristics of the parameter being measured:
- 2. Signal Process Control and Protection System, including;the
- 7300igocessMustrumentationiandiCogtrol Ann; Pret;; tion i System, Nuclear Instrumentation System (NIS)~, field contacts, and protection channel sets
- provides signal. :!
conditioning, bistable setpoint comparison, process algorithm actuation, compati.ble electrical signal CP 3.3 ED1 output to protection system. devices,' an & control i board / control room / miscellaneous indicatTons orpares: L
.3. Solid State Protection System (SSPS), including input, logic, and output bays: initiates proper unit shutdown 0 and/or ESF actuation in accordance with the defined logic, n .which is based on the bistable outputs from the signal process control and protection system; and V
- 4. Reactor trip switchgear, including reactor trip breakers L (RTBs) and bypass breakers: provides the means to
. interrupt power to the control rod drive mechanisms (CRDMs) and allows the rod cluster control assemblies (RCCAs), or
~
" rods," to fall into the core and shut down the reactor,
- j. < The bypass breakers allow testing of the RTBs at' power.
I s G crsEShaup ofNUREG-H31 Bases -ITS 3.3 B 3.3-2 M939 3 Y, . - . . - < ,- , , . . . , . . , . . . - , , , . - . . . - . .
RTS Instrumentation l B 3.3.1 1 BASES l i
. , , , . . , - _ _ . . ~ . - . . . . . . . . . . . . . . , - . _ . . . . . . . ,
'-3 3 "3 hagEtamBtMMRAMBBEREEBGMI2WERCR$988 Met" 1!M b! M 88B B B Big g g g g e n m.semensgegens ALAFM3lWLMt 148'LMemp1DThe actual nominal Trip Setpoint entered into .the bistat,le is more conservative than that specified by the Allowable' Value to account for changes in random ,
measurement errors detectable by a COT. One example of such a i change in measurement error is drift during the surveillance i interval . If the measured setpoint does not exceed ~the A11twahlo Valna +hn hietahla h considered OPERABIF d thereven!MehlgnehWitgs!fo0mEnonconseryative witKrespectit03heIspgfitedHtiplSetpointR but:eore conserygiyeitheigth6MUowable;Valugthe'setpointinust be I adjustesito3he specified; Trip 15etpointBwithinl; calibration allowancegas'providedlinitheisetpointJ studyM l f 2 CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-4a 1/2989
RTS Instrumentation B 3.3.1 l BASES The decision logic matrix Functions are described in the functional diagrams included in Reference 1. In addition to the reactor trip or ESF, these diagrams also describe the various
" permissive interlocks" that are associated with unit conditions.
Each train has a built in testing device that can automatically l test the decision logic matrix Functions and the actuation devices while the unit is at power. When any one train is taken
' out of service for testing, the other train is capable of providing unit monitoring and protection until the testing has been completed. The testing device is semiautomatic to minimize testing time.
APPLICABLE The RTS functions to maintain the applicable Sb6afety3imits SAFETY ANALYSES. -during all A00s and mitigates the consequences of DBAs in al
'LC0, and MUDES in which the Rod;ControUsystes?lsicapable ofirod; APPLICABILITY; withdrawal'or;one;orporef, rods are notifullylinserted; RTBs are cicacd. CP3.3ED1l Each of the analyzed accidents and transients can be n 3.3 006 l detected by one or more RTS Functions. The accident L analysis described in Reference 3 2 takes credit for most RTS trip Functions. RTS trip Functions not specifically credited in the accident analysis are qualitatively credited in the safety analysis and the NRC staff approved licensing basis for the unit.
These RTS trip Functions may provide protection for conditions-that do not require dynamic transient analysis to demonstrate Function performance. They may also serve as backup orJdiyerse ' tfjps to RT'S trip Functions that were credited in the accident analysis. The LC0 requires all instrumentation performing an RTS Function. i listed in Table 3.3.1-1 in the accompanying LCO, to be OPERABLE. Failure of any instrument renders the affected channel (s) inoperable and reduces the reliability of the affected Functions. i l The LC0 generally requires OPERABILITY of four or three channels ! in each instrumentation Function, two channels of Manual Reactor ! Trip in each logic Function, and two trains in each Automatic l Trip Logic Function. Four OPERABLE instrumentation channels in a two out of-four configuration are required when one RTS channel is also used as a control system input. This configuration accounts for the possibility of the shared channel failing in such a manner that it creates a transient that requires RTS action. In this case, the RTS will still provide protection. CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-7 12989
-- . . . . - . .~ . - - . . . - - . - - . .. - .- - -- -.--
i RTS Instrumentation i B 3.3.1 l BASES i
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SAFETY ANALYSIS, v.u
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' In l'00C 1 er 2, 'tcr. there is pet;ntiel for ; ;ultipi; red drep x;ident to ;;;ur, th; ";;;r "eng; l4;utren :
e,.. . m _u o _ __m
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ww y a we.w. . w w. wm s 6. v. wu. vn .vv s b. i w. .ww T e u du.s. l s____ _, enu _ -..__1 _, _ _ n,r a v._ unne e __ i
,sw y. ww w. ww. s J...
. AwL. N w w w.i b w. u.s . a.#T . ..s . vvww w, ..V red er; withdr;wn end th; r; quired Sm"" i'; in; ices;d during r;faling ep;retion';. In ;ddition, th; ti!0 p;wer reng; det;;ter ;;nr.;t d;t;;t neutrun 1;v;13
______ nne
- y. w ww..m b 2._.. mws u.a ea _u. rvwh o
- 4. Intermediate Ranae Neutron Flux CP.3.3 ED1 The Intermediate Range Neutron Flu .
rip , Function ensures that protection is ided against an j uncontrolled RCCA bank rod withdrawal accident from a i subcritical condition during startup. This trip Function i provides redundant protection to the Power Range Neutron. j Flux-Low Setpoint trip Function. The NIS intermediate ! range detectors ~are located external to the reactor vessel and measure neutrons leaking from the core.- The NIS intermediate range detectors do not provide any input to control systems. Note that this Function also provides a signal to prevent automatic and manual rod withdrawal prior to initiating a reactor trip. Limiting further rod withdrawal may terminate the transient and eliminate the need to trip the reactor. The LC0 requires two channels of Intermediate Range Neutron Flux to be OPERABLE. Two OPERABLE channels are sufficient to ensure no single random failure will disable this trip - 1 Function. . ICPSESMarkup ofNUREG-1431 Bases -ITS 3.3 ' B 3.3-12 129/99
. . ~-. - . . - - . - .- .. - - - - - - - - . . ~
RTS Instrumentation B 3.3.1 BASES' described in Note 1 of Table 3.3.11. Trip occurs-4f-Ov;.-tc..,,erature oT is indic;ted in t.; 1;;ps.3fitJg)gg8 JE of Ihe 3 @ ] q!st] pm pressure and @g)Ritemperature signals are used for other control functions. For ths; units : thug,
- the actuation logic must be able to withstand an input
- j. failure to the control system, which may then require the protection. function actuation, and a single failure in the !
other channels providing the protection function l actuation.INote that this Function also provides a l CP 3.3 009 signal to generate a turbine runback prior to reaching the Trip Setpoint. A turbine runback will reduce l turbine power and reactor power J;1^/ g ^M ;;;h3 M M ; Eh-El371.443v LeiEAM.;;. A. reduction i r will normally alleviate the Overtemperature
#3'3" j1 eT-condition and may prevent a reactor trip. j T requires all four channels of the Overtemperature i eT-trip Function to be OPERABLE for Le ;nd fe,ar 1;;p (tre LOO i;quir;; ;11 thr;; chenrels en tre Overt;;.peratur; oT trip runction to b; 0"C"XLI for tha leep units). Note that the Overtemperature Function receives input from channels shared with oth@er RTS Functions.] Failures that affect multiple Functions require entry into the Conditions applicable to all affected Functions.
I In H0DE 1 or 2, the Overtemperature .16 rip must be ) OPERABLE to prevent DNB. In HODE 3, 4 , or 6, this trip Function does not have to be OPERABLE because the reactor is not operating and there is insufficient heat production
.to be concerned about DNB.
- 7. Overoower *T N 16 TheOverpowerofNJJRtripFunctionensuresthatprotection is provided to ensure the integrity of the fuel (i.e.,
gg no fuel pellet melting and less than 1* cladding strain) under all possible overpower conditions. This trip Function also limit required range of the Overtemperatur rip Function and provides a backup to_tha P = r Ran tron Flux-Nigh Setpoint trip.] i g N dhisVRhedausehy cnemssun nert t16deis? noti;tensitiveito2j a gem iu orgm2rqactortvessel M YI""l8lNI.1840MfpoWej fdjM1FA. h. dited11n3heOms]yMLEort4!e!d. ecrease IRIM8CiteWpeGtureleyent.gMlfgtl$omelsteas),inelbreaK accidetfj
' CPSES Markup ofNUREG-1431 Bases -ITS 3.3 ' B 3.3-16 1/29/99
, ... _ ._ _ _ . . _ _ ..__ . _ _ _ . _ _ . _ . . _ _ . _ . _ _ _ . . _ . _ _ . _ . ~ . _ _ . _ . _ _ . . _ . .. ,i gf-u RTS Instrumentation o -
B 3.3.1 , RASES u h The Overpower-eff rip Function ensures that cP 3*3 EDI
- the allowable hea'. ration rate (kW/ft) of the 1 fuel is not exceeded. It uses the AT of eech lap ,
;; ; =nur ;f r;nt; gw with ; :;wtgint thet i:;
, stratisily ari;d with th; fell;;ing grr;ter;;;;36 Of4#26 . ; SimtgtjM i .L ; a -,. + m 'u.w i M ] .l
*' r;;;ter ;;elent Ger;;; toi gietur; the Trip S tpeint 1 i '. w;,'. r.i '.;.T.-'. ty
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- ww... .b..__w._ .. i
. . r;;t ;f crer.;; ;f r;nter calat =c;;; j tw g ;;ta ; incl uding dy-,;;;;i c ,,Gxtic; for tre j l d;l;;y'; b;t ca th; ca; =d the to gr;tur; j nn;r; ...t :;y:t=.
- TP; Ow gar oT trip ."uratim i: ;;lculeted for exh leap i
;;; pr Lt- 2 ;f T;bi; 3.3.1-1. Trip aar:; if 0=rgar ]
[-
- 6T-4s indisted in tw leep. ThjE0vg'powet;H36.? power j I 1RLMcq$$3Xcg]gigatedlfoteacll1gSMoonntI.tlp; occur. sat i
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2 .. ,g - dv b uvv be. b.Tw bys w bus W .y . ye au s e us W usww a vs v b 4 ww u 'l satr;l fux tion;. At the n unit:. The actuation logic must be able to withstand an input' failure to the control i '. : system. which may then require the protection function i actuation and a single failure in the remaining channels
-providing the protection' function actuation. Note that ~
t this Function also provides a signal to generate a turbine i p runback ~ prior to reaching the All;nbl; '.';1;; Ttip i ? ' Segggg. A turbine runback will reduce turbine power and 1 reactor power. A reduction i r will normally ; alleviate the_ Overpower of 5 *i condition and may CP 3.3 ED1 i prevent a reactor trip. The LCO requires four channels for tw ad far lap unit: (th.- ; ;te..al; f;r thr;; lu,p =it:) of the Overpower-ef
- rip Function to be OPERABLE. Note that the Overpower
>T-trip Function receives input from channels shared
<> other RTS Functions. Failures that affect multiple
' Functions require entry into the Conditions applica all affected Functions.
In N00E 1 or 2. the Overpower 216' rip Function must be OPERABLE. These are the only ti at enough heat is CPSES Marky ofNUREG-1431 Bases -JTS3.3 B 3.3-17 .1n989
.RTS Instrumentation a B 3.3.1
. ' BASES generated in the fuel to be concerned about the heat
- generation rates and overheating of the fuel. In MODE 3, -
- 4, 5 or 6 this trip Function does not have to be OPERABLE.
because the reactor is not operating and there is insufficient heat production to be. concerned about fuel
. overheating and fuel damage.
E 8.- Pressurizer Pressure fThesamesensorsprovideinputtothePressurizer P sure-High and -Low trips and the Overtemperature cP-3.3 ED1 i J \ oT. trip. At M ;;its. The Pressurizer - ssure channels are also used to provide inont to , the Pressurizer Pressure' Control System- I;r th;x units.l l thusHthe actuation logic must be able to withstand an input failure to the control system, which may then require the protection function actuation, and a single failure in the other channels providing the protection function actuation.
- a. Pressurizer Pressure-Low The Pressurizer Pressure-Low trip Function ensures.
. that protection is provided against violating the DNBR limit due to low pressure.
The LCO requires four channels for two end f;;r leep units (thra chs sis f;- three leep units) of Pressurizer Pressure-Low to be OPERABLE. 1 In MODE 1, when DNB is a major concern, the ! Pressurizer Pressure-Low trip.must be OPERABLE. ? .This trip Function is automatically enabled on increasing power by the P 7 interlock (NIS power range , P-10 or . turbine impulse pressure greater than l L approximately 10t of full power equivalent (P 13)). On decreasing power, this trip Function.is automatically blocked below P 7. Below the P 7 setpoint, n; ;;x;iv;ble p;;;r disteibutiens =; x;;r
> th;t w;;1d x;x = ;;;;rn49ergis3Rsuffjcigg
!!RRt30tBANRERGEll8LMS90tME.
- b. Pressurizer Pressure-Hiah
, The Pressurizer Pressure-High trip Function ensures that protection is provided against overpressurizing the RCS. This trip Function operates in conjunction with the pressurizer relief and safety valves to prevent RCS' overpressure conditions.
' CPSESMarkappofNUREG-1431 Bases -ITS3.3
- B 3.318 1/2989
~
.RTS Instrumentation B 3.3.1 l
- . BASES ;
- i. i
~
l ut=;tially :=51:e. = =itra P =tsiat. ; la: ;f
'l= in my a; 1sep will atat: ; r;nter trip b; aux ;f
-the hi #;r p;; r 1; ni sd tra-r:dned = rgia t; th; d;; iga li;it = .
i- 12. Undervoltaae Reactor Coolant Pimns L The Undervoltage RCPs reactor trip Function ensures that protection is provided against violating the DNBR
- limit due to a loss of flow in two or more RCS loops. The g voltage to each RCP is monitored. Above the P 7 setpoint.
a loss of voltage detected on two or more RCP buses will l initiate a reactor trip. This trip Function will generate l a reactor trip before the Reactor Coolant Flow-Low +Twe~ ' Leope Trip Setpoint is reached. Time delays are incorporated into the Undervoltage RCPs channels to prevent reactor trips due to momentary electrical power transients. i
- l. The LCO requires three foug Undervoltage RCPs channels (one l per phase R@ gr tu; to be OPERABLE. iMfeguired
- channelsIE,ttatedigshpers.bes;becauseleachibusihas i on1ronelRCPJ In MODE 1 above the P 7 setpoint, the Undervoltage RCP ;
! trip must be OPERABLE. Below the P 7 setpoint, all reactor trips on loss of flow are automatically blocked ;in;; r.e , G ;;i n bi; pu;r di;tributism ;;;1d ;; a r th;t ; w;;1d :=x ; L"O ce;;ra et this 1;; p;wr 1;=1 CP 3.3.ED1 g g M " N ' M I M T W itd , L u-,C 1- _C.12. _ rwr;=J Above E the P 7 setpo1nt, tne reactor trip on len of ;w in two er er;
. 200 leep ggggg@tage23C_P( is automatically-enabled. This fureti;n ;;a th; xx r;l;y: n the ESTAS Turatim 5.f. ""ador;;1t;;; 0;=ter Cal =t P=p (RCP)"
l st rt ;f th; anili;ry f;;datcr (A".0 paap. u
- 13. Underfreauency Reactor Coolant Piens l=
The Underfrequency RCPs reactor trip Function ensures that protection is provided against violating the DNBR limit due to a loss of flow in two or more RCS loops from a major
- l. network frequency disturbance. An underfrequency condition W*
B 3.3-23 1/29199 l l CPSES Markup ofNUREG-1431 Bases -ITS 3.3 '
RTS Instrumentation B 3.3.1 BASES will slow down the pumps, thereby reducing their coastdown time following a pump trip. "c pregr en ade,quate] coastdown time _is required so that reactor heat can be removed immediately after reactor trip. The frequency of each RCP bus is monitored. Above the P-7 setpoint, a loss of frequency detected on two or_more RCP buses will initiate a reactor trip. This trip Function will generate a reactor trip before the Reactor Coolant Flow-Law fTwo t:eepstTrip Setpoint is reached. Time delays are incorporated into the Underfrequency RCPs channels to prevent reactor trips due to momentary electrical power transients. The LC0 requires three foug Underfrequency RCPs channels (1 perlRR);pr Ns to be OPERABLE. Thelrequired;channelsEare stated l'asZone petibusibecause3achibu_s;hasJonly one:RCP) In H0DE 1 above the P 7 setpoint, the Underfrequency RCPs trip must be OPERABLE. Below the P 7 setpoint. all reactor trips on loss of flow are automatically bloied since ac c;acciv bic pc;.;;r distributicas c;uld occur that would caus; ; 0"" ;;ar- ' ' W h; pc.;;r icycl CP-3.3 ED1 j inceltheMedslhot3)roducing3dfficient power <toj ate:m sicchditions A ;;; ::: " 7 sc:pc = . : c rc ctor trip on ; css ;; ;;;w ta t'.;; or ;rc "CS loops is autcastically ca:blad.aboveltheTPi?Isetpointathelreactor trKezn under_frsquenjcyHslautomatically enabled]
- 14. Steam Generator Water Level-Low Low The SG Water Level-Low Low trip Function ensures that protection is provided against a loss of heat sink and actuates the AFW System prior to uncovering the SG tubes.
The SGs are the heat sink for the reactor. In order to act as a heat sink, the SGs must contain a minimum amount of water. A narrow range low low W8tedleveQs,ignal in any SG is indicative of a loss of heat sink for the reactor. The level transmitters provide input to the SG Level Control System. Therefore, the actuation logic must be able to withstand an input failure to the control system, which may
-then require the protection function actuation, and a single failure in the other channels providing the protection function actuation. This Function also performs the ESFAS
! function of starting the AFW pumps on low low SG 1evel. l~ l CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-24 U2989 l'
[ RTS Instrumentation l L B 3.3.1 l l BASES: L - l< [
- the signal to prevent automatic and manual rod withdrawal; I
f . on increasing power, the P 10 interlock allows l the operator to manually block the Power Range i Neutron Flux-Low reactor trip: i . 1 [
. on increasing power, the P-10 interlock ]
automatically provides a backup signal to block !' the Source Range Neutron Flux reactor trip, and-also to de energize the NIS source range detectors: 1 , 4 i l~
. the P 10 interlock provides one of the two' l inputs to the P 7 interlock; and j i
l . on decreasing power,' the P 10 interlock j L automatically enables the Power Range Neutron j Flux-Low reactor trip and the Intermediate l E Range Neutron Flux reactor trip (and rod stop).
..____._.m.-
=.-._-_x an.a u w. w
_ _ _ . . m_,____ r x-. a -?n .~ l E101hasItWo , L aUa!Nh1.93410es@!tel4thaleAnyalue31s . assumapitK14ncreasinnae2]egl.s7and the cP-3.3 ED1 L emm87Alste>NDlah!a2tmenbe#Mtten decanslN83mneam8EGRiEPDBMmerenteg
= _
_ ,.=-_ -=_ .-- m . x n _- N The LCO requires jgg phannels of Power 0-3.3 44 j Range Neutron Flux, P 10 interlock to be OPERABLE in MODE 1 or 2. OPERABILITY in MODE 1 ensures the Function is available to' perform its decreasing power Functions in l . the event of a reactor shutdown. This Function must ' + be OPERABLE in MODE 2 to ensure that core protection is provided during a startup or shutdown by the Power Range Neutron Flux-Low and Intermediate Range Neutron Flux reactor trips. In MODE 3, 4 5, or_6, this l L Function does not have.to be OPERABLE because the h reactor is not at power and the Source Range Neutron Flux reactor trip provides core protection. l
- f. Turbine I = ' n F Wst:Staan Pressure. P-13 i
i CPSES Marhap ofNUREG-1431 Bases -ITS 3.3 ; B 3.3-33 . 1/2989
RTS Instrumentation. B 3.3.1 BASES , The Turbine I;r.pula fy$tatan Pressure. P 13' interlock is actuated when the pressure in the first stage-of the high pressure turbine is greater than
;;,p.aintem10% of.th; reted full CP 3.3 ED 3 power pressure. M M
- MEh1 s M is determined by one out of two pressure detectors. The LCO requirement for this Function ensures that one of the inputs to the P 7. interlock is available.
The LC0 requires two channels of Turbine I;pul-sefest S. Mag Pressure. P-13 interlock to be OPERABLE in H00E 1. , . 4 The Turbine I;r.pula Ch; ber21fstIStapq Pressure'. P-13 1 interlock must be OPERABLE when the turbine generator is operating. The interlock Function is not required 1 OPERABLE in H0DE 2. 3, 4, 5, or 6 because the turbine i generator is not operating.
- 19. Reactor Trio Breakers l
This trip Function applies to the RlBs exclusive of individual j trip mechanisms. ' The LCO requires two OPERABLE trains of trip ! breakers. A trip brai;r trein ;;nsi:;ts of all trip brukers essr,;ieted with single RE legic train that er; racked in, ciend c.nd up;bic ;f supplying p;ar t; th CR0 Syst;;;;."Jhus, the train say ;;nsist ;f th; ;;in brak;r er bypus brukcr or ;;;in braker end bypes' CP-3.3 ED1 l brak;r. d;p;nding spen th; sy:;t;;;; cenfigur ti- 8 EPA 4 51"2=USU59Id%bl%EdRLT89$0E8 I l a6)M1E30lLEtackedl1, 1 H C M h 1 M _.J Egg FCIWi! M tes'. h theMEREMMmmastatum!!matLeJKLn1bettagge 3 . ..; u
. me;;;. flEgggggg335tetCgghtguErgn] 1 T a vrtMBLt Irams ensure nu s mwe ranoom rai, T '" _
the RTS trip capability.
- 19. Reactor Trio Breaken (continued)
These trip Functions must be OPERABLE in MODE 1 or 2 W t n th; r;;;ter is critical. In H0DE 3, 4. or 5. these RTS trip Functions must be OPERABLE when the 1R 3.3 006 REs er :s:;;;icted bg,cas brukers er; cissed. end th; ORB tjlglRJjllQggpBSystem is capable of rod wi thdrawal E;;%3!@oreTr@sldr6TmtifulMinsertm] .
- 20. Reactor Trio Breaker Undervoltaae and Shunt Trio Mechanisms The LC0 requires both the Undervoltage and Shunt Trip Hechanisms to be OPERABLE for each RTB that is in service.
. CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-34 U29/99
RTS Instrumentation B 3.3.1 BASES ACTIONS A Note has been added to the ACTIONS to clarify the application of Completion Time rules. The Conditions of this Specification may be entered independently for each Function listed in Table 3.3.1 1. In the event a channel's Trip' Setpoint is found nonconservative with respect to the Allowable Value, or the transmitter, instrument loop, signal processing electronics, or bistable is found inoperable, then all affected Functions provided by that channe1~ must be declared inoperable and the LC0 Condition (s) entered for the protection Function (s) affected.] When;the198gtt1W$hanneWETable? *ams xcified CP 3.3 ED1 onlalpeC lopp2ppr2SGT3 g Gbes M train ~ot' peri u i w basisateithE;;^2^ 'marbewsseparatetyaor eachiloop Et*6M&misFeriRTB maw 7as7maaropria+='...in;the
-.._._m..-m
=ma
- m m m m =
--s_ - u- m u M i FA!g1 6 4tleir$3l!st _. 6 s m e - taig B!Galr L 2 erent i ApplicmyggggggRinittaKippetaillisyMia gimeIERSR'atismanag;npgttmaattiglig!!gmatmarithe apnifcasamesetaulmudelE!falEenieEMmi!BE9ERf
' 20Rt163BBlpW:stlMCEMWkfantta wwwaarnamummmaammanummmaammummarenumannswesenneseemananmnenw 1
e -a---M - C rw - liggtfrg$miggggigTd!glggg(3s33rdggget annicgBMER!IgumulmissexleIsattenditiewifetplodem i 13!!nd'emisgangitalganitesplegegames"wa.ttalacKMtR 18EttsameIEmittMiiE11!!#3 Rat 1MtlIMIMal Imperab1MtyIgs;. 43 msg l!pirawteya!guirm; tag;pngcf1 y; When the number of inoperable channels in a trip Function exceed those specified in one or other related Conditions associated +
'CPSESMdrkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-36 12989
.. . _. -___m . _ _ - _ _ - .__.._ _ . - . _ . _ _ _ _ _ _ __
L' RTS Instrumentation B 3.3.1 BASES 1 be placed in H00E 3 within the next 6 hours. The Completion Time l
. of 6 hours (Required Action Q.1) is reasorable considering that in
- this Condition, the remaining OPERABLE train is adequate to
- perform the safety function and given the low probability of an event during this interval. - The Completion Time of 6 hours (Required Action Q.2) is reasonable, based on operating i
experience, to reach MODE 3 from full power in an orderly manner and without challenging unit systems. The Required Actions have been modified by a Note that allows bypassingonetrainuptofhoursforsurveillancetesting. L provided the other train is OPERABLE. R.1 and R.2 Condition R applies to the RTBs in H0 DES 1 and 2. These actions ) address the train orientation of the RTS for the RTBs. With one i train inoperable, I hour is allowed to restore the train to OPERABLE status or the unit must be placed in H00E 3 within the next 6 hours. The Completion Time of 6 hours is reasonable, based on operating experience, to reach MODE 3 from full _ power in an orderly manner and without challenging unit systems. The 1 hour and 6 hour Completion Times are equal to the time allowed by i LCO 3.0.3 for shutdown actions in the event of a complete ! loss of RTS Function. Placing the unit in H0DE 3 resultslin I m 3.3-006 Condjtig_ClentM.M!rnind sILwablegemes the rcquir;n at f;r this perticuler runtion. The Required Actions have been modified by t;s; tw; Dotest !
- s. % : 1 ljgptj%3bgla110ws one channel to be bypassed for o.3.3 117 ,
up to 2 hours for surveillance testing 3!rmat*--'w! ) provided the other channel is OPERABLE 331ieThootAtime3 CP-3.3 014 (limitx12 W e+1fsad A E l- - ' rte 7, msg;311ggmgJc4 belbypaisgL3]QyGfMMkg(M1plR!!Mgg d sen*=ML*0elana!ts!aBImmCentlttWDgCMutsgescandia U, provided the other channel is OPERABLE. 2tc 2 silcus ene RO t; b; b g a sed f;r up t; 2 hours for = int; x xe en uni rvelte,c er shunt trip xchnism if th; ether RE train is Or:IJ.0LE. Be 2 hour ti;a li;;;it is justified in r,cferexe 7 ~.l. S.1 and S.2 Condition S applies to the P-6 and P 10 interlocks. With one or:noreitequired channel (s] inoperable] for en cut ef-tw; er tw; ;ut ef-f;;r ;;ixiix; logic, the associated interlock must be verified to be in its raanirad chta h e tha existing unit conditioCTO2.;Cic7;GL.i;g[;~;.i.i.Riiha ,i.e., within 1. hour or the unit must ue piaceu m nuui 5 wn.nin tne next 6 hours. Verifying the interlock status manually. CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-48 1n939
i l RTS Instrumentation ! B 3.3.1 BASES Time of I hour,is based on operating experience 'and the minimum amount.of time allowed for manual operator actions. The Completion Time of 6 hours .is reasonable, based on operating experience. to reach MODE 3 from full power in an-orderly _ manner and without challenging unit systems. The 1 hour and 6 hour Completion Times are _ equal _ to the time' allowed by
- LCO 3.0.3 for shutdown actions in the event of a complete' loss of
. . RTS Function.
T.1 and T.2
^
Condition T applies to the P 7. P 8. P-9, and P-13 interlocks. With onegggggg channelig inoperable; fe .; at ;f t ; er t.;; at ;f far sir.;idcx; b;ic. the associated interlock must be verified to be in its required state for the existing unit conditiontighggg@niofithe; permissive; annunciator; window . within 1 hour or the unit must be placed in MODE 2 within the next 6 hours. These actions are conservative for the case where power
. level is.being raised. Verifying the interlock status manually
- accomplishes the intcrlock's Function. The Completion Time of
- 1. hour. is based on , operating experience and the minimum amount of time allowed for manual operator actions. The Completion Time of 6 hours is reasonable, based.on operating experience,'to reach MODE 2 from fu11' power in an' orderly manner and'without '
. challenging unit systems.
U.1 and U.2 .1 xd ".2.2 Condition U applies to the RTB Undervoltage and Shunt Trip. [ Mechanisms, or diverse trip features, in MODES 1 and 2. With one l lL of the diverse trip features inoperable, it must be restored to an s OPERABLE' status within 48 hours or the_ unit must be placed in a MODE where the requirement does not' apply. This is accomplished by placing the unit in MODE 3 within the next 6 hours (54 hours g total time) .... _ ,. , .,,,......, ..,...... ... . ., ... ... . -.
~
(55 h=rs tet;l ti n). The Completion Time of 6 hours-is a j reasonable time, based on operating experience, to reach MODE 3 from full power in an orderly manner and without challenging unit j; systems. ! U With th; "".; ;;;;r sd th unit in MODE 3, thi; trip n.r.cti; i; ; k .;;r i;@ir;d to k 0"C" OLE 300$tt1Drf7C48 TR.3.3 006 ; r gj. .m v .- n 99 a,x. . e . c .t. m - i ; , -
- . c ;. ~ 7 . . . . g o. -c.) gygg
]
. ,e7 y .. . .. ... :
. g. . mg1,1) 1 N .. The affected RTB shall not be bypassed )
while one of the diverse features is inoperable except =for the F time required CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 T B 3.3-49 1/2939
- x. . . ~ -- - - . - - - ~ . - - - -, , _ . -- .- . --
._ _ . - . _ ~ _ _ . _ . _ _ _ . . . _ _ . _ - . _ _ _ . . _ _ - . _ _ . _ _ . _ _ _ _ . _ . _ _
RTS Instrumentation B 3.3.1
, BASES SR 3.3.1.8 is the performance of a COT as described in
.SR 3.3.1.7, encept Mit is modified by e Nte that this test shall include verification that the P 6 and P 10 interlocks are in their ired state for the' existing unit conditi modified ows this wrveillance to be satisfied if i W "^[=-Li= y LM _. .
R lE W___ T ^
. m ays o hinc.-- prsur w reactor startupMitg1321hanrsMter' m and four hours after reducing power
, belcw " 10 ;.c.J P 6MW3s)q. The Frequency of ." prior l to startup" ensures this surveillance is performed prior to critical operations and applies to the source, intermediate and 4 . power range low instrument channels. The Frequency of "4 12 hours after reducing power below P 10" (applicable to intermediate and power range low channels) and "4 hours after reducing power below P 6" (applicable to source range channels) allows a normal shutdown to be completed and the unit removed from the MODE of Applicability for-this surveillance without a delay to perform the testing required by this surveillance. The q Frequency of every 92 days thereafter applies if the plant remains in the MODE of Applicability after the initial performances of prior to reactor startupt?tgihours3fter;reducig g)tigg2DR3 and four hours ~ after reducing power below P-10 or P 6. The MODE of Applicability for this surveillance is < P-
- 10 for the power range low and intermediate range channels and <
P 6 for the source range channels. Once the unit is in MODE 3, this surveillance is no. longer required. If power is to be maintained < P-10 ggggggghgigi,ggylor l < P 6 for more than 4 hours,.then the testing required by this surveillance must be performed. prior to tlye expiration of the gil100[9Mg4 hour 11 mitt MM. i=r h=rs i: 7:nentic ti.; htime31RLtg M'3to complete the required testing or place the unit in a MODE where this surveillance is no longer required. This test ensures that the NIO source, intermediate, and power range low channels are OPEMBLE prior to taking the reactor critical and after reducing
~
power into the applicable MODE (< P 10 or < P 6) for the periods m w r 3 m g a n gt3 eggs. l i SR 3.3. 2 J SR 3.3.1.9 u the performance of a TADOT and is performed every 192@ days, cs justified in Reference 7J!. 1
- CPSES Markup ofNUREG-1431 Bases - 1TS 3.3 B 3.3-55 1/29/99 J
.- . . .- ~.. . - . . - . - . . - - _- - .. - - .- - -
RTS Instrumentation-B 3.3.1 ' BASES This SR is modified by a Note that excludes verification of setpoints from the TAD 0T. .Since this SR applies to RCP undervoltage and underfrequency relays, setpoint verification requires elaborate bench calibration and is accomplished during the CHANNEL CALIBRATION. SR' 3.3.1.10 A CHANNEL CALIBRATION is performed every HB} 18 months, or approximately at every refueling. CHANNEL CALIBRATION is a complete check of the instrument loop, including the sensor. The test verifies that the channel responds to a measured parameter within the necessary range and accuracy.TEThisiSR;is~sodified by a;30teIsta$ig3hlagEE16IdetectorslagM1uded;ftcutthe CHMNELMMAT"r.7'"UEsnlE.K3E6hir . inte MINESEdbt5Ebecauselthelunitlau_st;be;in:st31 east cP-3.3 009 MWlElim.;to: obtainJf16jladicati_on.s;pj CHANNEL CALIBRATIONS must be performed consistent with the assumptions of the =it ;g;ific setpoint methodology. -The differ;re; kta;;a th; curr ..t ";s found" velucs end th; previous t;st ";s 1;ft" v; lues ;;;ust b; censistent with th; drift ellow=c; und in th; 3;tp;iat 7.ethodel;;;y. The Frequency of 18 months is based on the assumption of_ an 18 month calibration interval in the determination of the magnitude of equipment drift in the setpoint methodology. SR 3.3.1.10 is modified by a Note stating that this test shall include verification that the time constants are adjusted to the prescribed values where applicable. ]his280rve1Danceidoes EMIMl!ERtttDM193Df31mle delayzelesIg]hes~e irelan m-3.3-oo4 asmggssaggghtgtsstEE4dy m6~.7 1RLeDeMRIMEEllTEEDILIERIMfff9MERRRN--ZidG20 b. t m _ M IIuiimumm J . CP 3.3 EDI scouplalREBERE2twateismosmMtuggggNLt2Lugpam BIRr m 3O K411g elemenjt SR 3.3.1.11 SR 3.3.1.11 is the performance of a CHANNEL CALIBRATION, as described in SR 3.3.1.10, every SB} 1Q months. This SR is modified by a Note stating that neutron detectors are excluded from the CHANNEL CALIBRATION. The C".'f5L C'LI""'TI0'i for the p;;;r rea;;; =;trea det;;ters censists of ; rer.eli;; tion of th; det;;ter; b;nd = ; p;;;r ;;1;rintri; ;nd 'i= =p Fiferr.ed _ . , . . . . . tEorahejpgerneciatelag poseccargeIchapeltj dgector31stenuleuritslagobginedstalgted:endicompaced3o CPSES Markup ofNUREG-H31 Bases -ITS 3.3 B 3.3-% 1/2989
RTS Instrumentation B 3.3.1 BASES:
. .i _ ; .
; . 1 e he CHANNEL CALIBRATION for the source i
range er.d 1.?ber ;.di;t; r;r.;; neutron detectors consists of obtaining the detector plateau er r r; .r di,cri;i nter curves, ! evaluating those curves..and comparing the curves to the' ! I manufacturer'.s mm_ c.._._21,____ data. M]) lee}M j > Wi .t nE$a@id .i i l'- bia s e wwu TW s s s us twb s:F'_ j j ( (", ;, ' j. ' "'j . ;c .[ 7. L y 1; a f i e e. 3 0 is not required 2.3 x y ;_ r ;_1__m___ ,__ p pged.g. ,__ it__ ..I w. u.,,., y-w . , u , r, W,. b,. wvs , .. entry into MODE 2 [ or 1 m_._2
-L
.w 2.._, ovb s oyo . . - . v.
-__.2-2 L L~. Lt.t e b n ,
2 6--- s..w-i - -iuww 21 L. sm. s. s w .- hv. . L__L_--
~
f;r ws/.ry irt; """C *,' because the unit must be in at least MODE 2 to perform the test for the intermediate range detectors and MODE 1 for the. power range detectors. The 1" spe sth "rqxxy L___2 __ mL_ ___2 ._ ___,-__ .u_ e.._.._2,,____ .._2__ mL_ 2.d. ww wwse vis b r us u nw w =s by yw. s us sus b s a u ., wws vs u s a usmw uu rww s w s us b ___22A2___ m L _ a. ___1.. 2.._2__ _ _1 _s ...s___ __; AL_ _ _ t - _12 .1 ,__ hvi a%s a w s vu ud ws vu b wyy 5 g . www iary u y u ut a s. vubuyv un r%s weas yvwws s b 5 u u s v3 i
. ..__1--J A.____2-_1- 2, a. L. e.._._211 ___ ..___ ___,_-_ J .2AL us u , wr vy v us ve rvu bu utteswssb I burh vui vs a s a wirwh avs t b yvs s m auNu w 4 ba s
[ the r ;;t; ;t pc.;;r. Operating experience has shown these components usually pass the Surveillance when performed on the
. -- m ~_
l 18 month Frequency.J _n__ .
=_~ m_ _ -._._i_
=,ca.mmw _ m ,&__s+.. m e s m w ,. w.www e.,
-- __-__m s..____
l _ _. s m mo m. .s _ _ _ _ . , _ , nw. bu. <w.v _m _, _ - - - - m_ _e.w 2. _ _ f.
>u
.u.m www u . e __- _-J e w - me.m ame5 =~~ ' www " ,= :-f_me a vmw
-n ,__ mL. u _m . _ _ _____ 2_A__A___ -_A_.. 2_m. <
yy gy I v5 bf WW NT .t W ey%.wb 4 5 ug fyb Ub wWh bul d E vi Ullbs g 151 b v I _ 9 J A_ -L ---.2- J ,__ LL. MTc 2 L--- A2_L-vi a usew a i sv b a wqu s s wws s vs b s iw si a d s y s esa issww a u ww _____ m i__m___ ,__ m_ unne L___..__ mL.
. ._ b2. m -.y CP 3.3 ED1
. . , , . us w- b. , .m...-.b.,.. 2, ,sw
_m nom .a . --uu.m b~ m. 1 L. 2 _i 1___i unne n ._ ___,___ iL_ &__& ,__ a. L.
- j. y% ssa ub sbudb e uvvh b wv ysi s vs sus basb budb 5m unne , ,__
bu sh i: 2_i___ 22_m_ _____ 2m__m___ __2 .L. _ _ . _ _ _____ I ti bws auswu s u ww s wi ryw ww www kvs e uivu s uvvh e a vs bu N yv wa a uu syv l s_A__A___ arL. Sn _-_rL r________. '2_ L __J _ AL. ___s &_ ww wwv bv1 d. serb AV ssrvu s wa t s c WMwvs rwg 5 ., wu =,b%s vis burb a rw w se s.V __ ,___ ALa_ e.._.._211.___ .._J__ mL, __J2AJ.__ AL A ___1 3: rs. . .mw bu s ., ,u s .. s . u , ~. ui ~s. s w. m -,~sw.m. b. w ury s ,. . uus J. 1,.,, ,_ . c u y s urgh vubuyb us e
...m___ __
e _. m 2 ., ,_ __ ..__,__ m yvbwisksus u vi m____2-usa ut fy s uu rs tvss bs uu ss s hu a w sa m 2, ___,_ - .s . 2 AL _A _ _ . . _ j
- l. A .L.owsc... . . ._21 1. m-b ~ m. _ _ .._._ . rsm- s n A b L. ~. ___A.__ uw rv
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CPSES Markup ofNUREG-1431 Bases - ITS 3.3 B 3.3-57 129/99
1 RTS Instrumentation B 3.3.1 BASES Surveillance. Performance of this test will ensure that the 73,3,3,no7 turbine trip function is OPERABLE prior to ggggRllE3HRat intrjgg t; kin; the r;xte critic;1. Thi; t;;t nr. net k g rfei d With t k r; ;te et p;n r ud = ^t therefers. M grf., d pri;r te rs;ter :t;rtup. SR 3.3.1.16 SR 3.3.1.16 verifies that the injud individual channel / train actuation response times are less than or ea"=1
- H= ==d ="a vah=c assumed in the accident analysis.Mtgqqjgggljgrjp jggiat$on6E";; pax tin t;;ti .;L^j .;
x61'12T'21. T- ~ "T^ ~ X - '. cce criteria for; CP 3.3 ED1 responss N F ^ ^^~ -de included in Technical Requirements Manual. (Refg&MgefMt3besitakeg3nithelsafety 0 3 3 55 analysesitelthosR3hannels1Mth:tesponse31seilfstedras E8UZM298poJ!8JeM$gliing~Jysqu1tementslapp10!ihetelNjA2 1s.211stnGD*KJMa Individual component response times are not modeled in the analyses. The analyses model the overall or total elapsed time, from the point at which the parameter o.1,1 4 exceeds the trip setpoint value at the sensor to t k peint et which th; ; qui p.nt r;;;h;; the r quired functi;=1 ;tet; (i.e., centr:1 end shutdce.;n rei fully in;erted in the re;ctor e8Peh8!t923a.siwfzstat1giary;grjpper; coil; voltage. For channels that include dynamic transfer Functions (e.g., lag, . lead / lag, rate / lag, etc.), the response time t;;t ny kLtesglspy b)3er$ffttMpHEMperformed with the transfer Function gg ggLtyi6xt to e a. With tk r;;ultin; nas;;d rapn;; ti=
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;=liti;;lly ;;l;;l;ted en=ir.; the tin cen; tent; er; set at their nominal values. Th; rapan tim ny k =nur;d)y. ;
;;ri;; cf ;;;rleppin; t;;t; ;;;h tkt th; :ntir; r;; pen;; ti= i; c au ed.
.____---.__,--_.mmm-__m i
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*heue2tf58tteis!tHatti 0 1.1 4 J CPSES Markap ofNUREG-1431 Bases - ITS 3.3 'B 3.3-59 1/29/99
i RTS Instrumentation B 3.3.1 BASES
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RTS Instrumentation i B 3.3.1 l
. BASES i r
As appropriate, each6nnel's response tEmust g,3,3,33 l be verified every M months on a STAGGERED TEST BASIS. t Lrami: _.. . .......,_ . tmaugstuberamein thch
. . - ._ _ _ _ . _ . _ _ . . . . ~ . . . . . . . . .
Testing of the final actuation devices is included in the 0 1.1 4 i
. m esponse :
times WB3ggcannot be ggmag determ+ned-during unit ! operation because equipment operation is required to measure response times. Experience has shown that these components usually pass this surveillance when performed at.the 18 month Frequency. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint. ;
~
SR 3 31.16 is modified by a Note stating that neutr , [16fgaunayetectors ,,m , s 3, g are excluaed num n w ncSPONSE TIME testing. inn nute 15 necessary because of the difficulty in generating an appropriate detector
, input signal. Excluding the detectors is acceptable because the principles of detector operation ensure.a virtually instantaneous response. Regggiseltjge of2tMneutror[f]Eot Nij61 sign 6LM3f3NeMister!eEshgDJ,gmeasuredifrom ,
de!l9ctoDAl*tl8C1NGJit]o thflitstielectronic[ component!1n t M chqpel! REFERENCES -1. FS?.". Ch;pter [7].FSMtgiaptergj j
- 2. T=. Ch;ptcr [03 3MELOiapterg5] !
'3. r= Ch;pter [15]. KEEEDLQ9M l
-4. :::t-270 1071. EsfRNc30 !
5.2 WCRUMMPEt30pplegegyney;37Jur! ell _990J
- 6. RTSE.0 TASS:tp;intM;thed;1;;yStudy.le.g!]nigal Rgl[I8igelitM 81 WIN D
- 7. "CA.10271 " A. Sappi; .;.nt 2. "ri.1, Jun; 1000.HgtMsed]
- 0. T;;;.c.ic;l ";quir; ,.c.;s M;nu;1. S;;tien 15. "";;ian;; .
me*? iia #-- :ic5tRLtetg5lemgl Ate 111gMjg_98_5J
^ ^ * ~ ^ " ~ ~ "
81 y^
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r ":" = = =
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A ".". .=~_.'"^"' m.usm .u ,.
^ T'e.9?.22" w
CP.3'3 EDI 19MiHM3RIRD 923 3!JL*Mn9hggCiytnoJgtil!sthod619gGpt" Protection 53tems C,3ggjlg2q193lBitJ1?Jgt,1sjg21]"igl2123.l CP.3.3-013 RgtblonNRMtilEML89J CPSES Markup ofNUREG-1431 Bases -ITS 3.3 ' B 3.340 1/2989
l l.. E ADDITIONAL INFORMATION COVER SHEET L ADDITIONAL INFORMATION NO: CP 3.3-ED2 (new) APPLICABILITY: CP REQUEST: Based on feedbad received from the NRC reviewer, the following Bases pages for LCO 3.3.2 hase been revised as noted on the attached pages.
' ATTACHED PAGES:
i Attachment 9, CTS 3/4.3 -ITS 3.3 l. Enci5B B 3.3-69,88,99,100,115,116,120,120a,121,121a and 123 Enci5B B 3.3-119 Licensee initiated change to make the description of SR 3.3.2.7 . plant specific to CPSES. i-I l
1 i ESFAS Instrument'ation l B 3.3.2 BASES active fuel for heat removal, clad integrity, and for ) limiting peak clad temperature to < 2200*F): and j
- 2. Boration to ensure recovery and maintenance of {
SDH (k,rr < 1.0), i These functions are necessary to mitigate the effects of certajn3high energy line breaks (HELBs) both inside and outside of containment asidesgibed11nj:he?fSARi[Re[23]. The SI , signal is also used to initiate other Functions such as- 1 I
. Phase A Isolation: l
. ContainmentPurgeVenti]ationIsolation:
. Reactor Trip:
. Turbine Trip:
Feedwater Isolation:
. Start of motor driven auxiliary feedwater (AFW) pumps: l
. Control rone r "' "-- 4---' "r nrgency; filtration CP 3.3 ED2 gtem3CREFShi4jggl@jZ:
. Enabling semifautomatic switchover of Emergency Core Cooling Systems (ECCS) suction to' containment sumpsi cojptident3(ithil56J2ciriloWJ t evel .
- EntonEY S Tstarg
. StatL"QffstatHif7serttiMWatgIpuppsj
. StamorcompeggticM1jngIkateripumps1
. Stan3tfLCoMelnment: Spray 2umpsgajg
. Staggf;estig!tial:ventjlatjg3yst_emsJ (continued)
, ' B 3.3-69
ESFAS Instrumentation B 3.3.2 BASES-
- d. Steam Line Isolation-Steam Line Pressure (1)- Steam Line Pressure-Low -
Steam Line Pressure-Low provides closure of the MSIVs in the event of an SLB to maintain at least one unfaulted SG as a heat sink for the reactor. and to limit the mass and energy release to containment. This Function provides closure of the MSIVs in the event of a feed line break to ensure a supply of steam for the turbine driven AFW pump. Steam Line Pressure-Low was discussed previously under SI Function 1.e.l. Steam Line Pressure-Low Function must be OPERABLE in MODES 1, 2, and 3 (above P 11), with any main steam valve open, when a secondary side break or stuck open valve could result in the rapid depressurization of the steam lines. This signal may be manually blocked by the oparator below the P 11 setpoint.
'3 3'63 Ifant3!PJ!ctplar19MTil17 ttleLStteam31gfmssum H1A!r m 3tas tbeLOP W af A l = I H R gg, hitg:tg. an inside containment SLB will be terminated by automatic actuation via Containment Pressure-High 2. Stuck valve transients and outside containment SLBs will be terminated by the Steam Line Pressure-Negative Rate-High signal for Steam Line Isolation (1) Steam Line Pressure-Low (continued) below P 11 when SI has been manually blocked. The Steam Line Isolation Function is required in 0 3.3 G 1 MODES 2 and 3 unless all MSIVs are closed ag tSi;:imi.
This Function is not required to be OPERABLE in MODES 4, 5, and 6 because there is insufficient energy in the secondary side of the unit tAyela
# ""MEMquggdlplant3go1M17 CP 3.3 ED2
'r.: = suC..'.. ::GCL",; ,q (2) Steam Line Pressure-Neaative Rate-Hiah Steam Line Pressure-Negative Rate-High provides closure of the MSIVs for an SLB when less than the P 11 setpoint to maintain at least one unfaulted SG as (continued)
CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-88 U2939
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'ESFAS Instrumeniation i B 3.3.2
,1
, . BASES. f
+
i Functior;; 3.' av' 6.g must be 0PERABLE in MODES 1 and 2. 'f . This ensures that at least one SG is provided with water to j serve as the heat sink to remove reactor decay heat and -l sensible heat..in the event of an accident. In MODES 3, 4, i and 5. the RGPHnd MFW pumps may be normally shut down. -j and thus neHher pump trip is gg indicative of a condition ; requiring automatic AFW initiation. ! l
- h. Met.itR4g l
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- 7. A^* Jtamatic Switchover to Containment Sumn
~
0-3.3 ED2 : I 4 s (continued) CPSESMarkup ofNUREG-H31 Bases -ITS 3.3 . - B 3.3-99 1/2989 J
ESFAS Instrumentation i B 3.3.2- i BASES 1 At the end of the injection phase of a LOCA,' the'RWST l will be nearly empty. Continued cooling must be provided l by the ECCS to remove decay heat. The source of water for .] th; CCCSM pumps is Mautomatically switched to the ; containment recirculation sump (. MRpriggitettig3he low ; head residual heat removal (RHR) pumps and-conte 4nnent i W ;y .rp draw the water from the containment _ j recirculation sump, the RHR pumps pump the water _ through' :
- the RHR heat exchanger, inject the water back into-the RCS, -l and supply the cooled water to the shg$sRXthe;other p ECCS - r hitchover from the RWST to t containment-I
_gu{_y g,my,_y
, .. . ..., v y.
_ p K . y.... .. v....... l~ s,; ;.eli;';; aptility. Switc_holfr"ttfithe containment i' spray _plag1tomithe[RMSTito* Kco!$ainmentisump.11s i- pertermedjenpa1} Ofter ptreetpointiisiteached.$
^
! For similar reasons, switc r must not occur uvivi n,wiw j' is. sufficient water in the containment sumps to support ESF (. pump suction. Furthermore, early switchover must not occur
- to ensure that sufficient borated water is injected from iL the RWST. This ensures the reactor remains shut down in the recirculation mode.
< a. "Mamatic Switchover to Containment Sumo-
- j. Auta=atic Actuation Loaic and Actuation Relays 0 3.3 ED2
~ Automatic actuation logic and actuation relays consist b of the same features and operate in the same manner as described for ESFAS Function 1.b.
f
- b. ~^ Jta=atic Switchover to Contairst i Refuelina Water Storaae Tank (RWST) !
L Level-Low Low Coincident With Safety Iniection and l r 2__ u__. um r __. 2 ___. c. _ i...., u2_6
)
i ! I During the injection phase of a LOCA, the RWST is the e source of water for all ECCS pumps. A low low level in the i' RWST coincident with an SI signal provides protection i h against a loss of water for the ECCS pumps and indicates i the end of the lig3] injection phase of the LOCA. The RWST p is equipped with four level transmitters. These l [ transmitters provide no control functions. Therefore, a j two out-of four logic is adequate to initiate the [ protection function actuation. Although only three j 4 j- (continued) f crses maar etsvaza-itsi sases - trs 3.3 s 3.3-ioo insivs [ 4
+w .
+ _ - ., - , . , - . . ,- . --e . - - . , ,
ESFAS Instrumentation B 3.3.2 BASES this Function requires the bistables to energize to perform their required action. The failure of up to two channels will n prevent tha eneration of this Functi ~ ~ 4.c= - -- - u .- -
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;;nditi= (n=:ing the irep;r bic ch;=;i h:2 ' ' ;'. :
9sGPlML8Miajp1:ea,.cnangehinith!Etn1pped; condition could te@lt?.1HMcDDtEsMitghoverltoithfltimp;&ptforatolthe in3ectic!DffallGWth!!M3clumenitanLttgs!ssrycingilhe Lnepetetsim!ggetm#missltesungigEt!ggghwitteenogic coK1emamentbadamettM1asatw2eenteestaatk1Womothat fail-3imagMggggggige
- t. s. i_rL.N. ._ _...____ _..._..._ . . _3..E_.B_B.N. R.BM.W_R__M__! tat _ acing 8.cff1GMi@ctitBRENRRELIElgBEEMend inil1MadERBERMBlit# EWER 1RtD!DelOHm2B!R't1*Ettip
.- e r +: : Mailed hich m Thh 0 h;as _
. I Resa, justified in Reference 8.
If the channel cannat be r;turred to 0"C"XL str.m-er us de"0PElWE igistir#Mlaced in the bypass condition within 6 hours, : 1e uni; must be brought to MODE 3 within the following 6 hours and MODE 5 within the next 30 hours. The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems. In MODE 5, the unit does not have any analyzed transients or conditions that require the explicit use of the protection functions noted above. (continued) CPSES Markup ofNUREG-1431 Bases -ITS 3.3 . B 3.3-115 1/29/99
ESFAS Instrumentation B 3.3.2 - BASES-4 L.1. L.2.1 and L.2.2 d 0 3.3 G 1 Condition L applies to the P 1 . . m _ , . interloc 0-3.3 ED2 With one mjchanne1{s} inoperable, the i
- j. operator must verify that the interlock is in the required 2 state for the existing unit conditiongstgggt@egisfithe l permit $1)Riejgeg8qatletudows. This action manually accomplishes the function of the interlock. Determination must ,
be made within 1 hour. The 1 hour Completion Time is equal to l the time allowed by LCO 3.0.3 to initiate shutdown actions in the ' event of a complete loss of ESFAS function. If the interlock is not in the required state (or placed in the required state) for the existing unit condition, the unit must be placed in MODE 3 l within the next 6 hours and MODE 4 within the following 6 hours. The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems. Placing the unit in MODE 4 removes all requirements for ; OPERABILITY of these interlocks. SURVEILLANCE The SRs for each ESFAS Function are identified by the SRs REQUIREMENTS column of Table 3.3.2 Itandlby:SR73lLI200. i A Note has been'added to the SR Table to clarify that Table 3.3.21 determines which SRs ot_hegthanIESEUtESPONSE TILEJespM9PMbeggrjficationlapply to which ESFAS 0-3.3-55 l
' Functions. E_SEgggNee::tigC.RESE0NSE1T_I,ME2etificationJs add!' esse 63lde13pg3ffedi1[SRl3g2210] ! Note that each channel of process protection supplies both l i trains of the ESFAS. When testing channel I, train A and !
train B must be examined. Similarly, train A and train B must be examined when testing channel II, channel III, and channel IV W , epplicabic). The CHANNEL CALIBRATION and COTS are performed in a i manner that is consistent with the assumptions used in ! i analytically calculating the required channel accuracies.
; Rcvicacr*3 %;tc. Certain Trcqucacic; crc based on cpproved top + eel reports. In ordcr for ; licca;cc to use these ti m . the licen;ce. ;;;;;t justify th; Trcqucacies c3 rcquired by th; ;taff SER for the topicci report.
(continued)
. CPSESMarkup ofNUREG-H31 Bases -ITS3.3 B 3.3-116 U19/99
. - . .- - ~ - -. - - . . .. .-
ESFAS Instrumentation B 3.3.2 BASES' be left set consistent with the assumptions of the current unit specific setpoint calculation. Oc "= fxad" =d "= 1;ft" v;l;;; =;t ;l;; b; rnecid ad r;;is;d for ;;;i;t;xy with ch; an ,,ti;m of the arveillax interv;l ata; ion =;1y;i; 'R;f. 5) dia ;ppliabi;. The Frequency of 92 days is justified in Reference 6. SR 3.3.2.6 SR 3.3.2.6 is the performance of a SLAVE RELAY TEST. The SLAVE RELAY TEST is the energizing of the slave relays. Contact operation is verified in one of two ways. Actuation equipment that may be operated in the design mitigation-N00E~ mode is either allowed to function, or is placed in a condition where the relay contact operation can be verified without operation of the equipment. . Actuation equipment that may not be operated in the design mitigation-N00Qsogle is prevented from operation by the SLAVE RELAY TEST circuit. For this latter case, contact operation is verified by a continuf ty check of the circuit containing the slave relay. This test is performed every 9gdays. The Frequency is adequate, based on industry operating :
- experience, considering instrument reliability and operating j history data.
SR 3.3.2.7 SR 3.3.2.7 is the performance of a TADOT every 3J 92 days. This test is a check of the Loss of Offsite Power r o.2 17
'Jadervelt;;; RCP, =d 'J'.! P;;p Suction Tromfer en Sucti=
Pr;;mr; Lew Functions. S a h Paxti= i; t uted up to, = d . I in;l; ding, the n;t;r tra;f;r r;l;y ;;il . Oc t;;t 01;; inclui; trip d;;i;;; that previi =tu;M
'- diratly to the SSPSJ ine bK is modified by a Note' that excludes verification of setpoints for relays. Relay . CP-3.3-005 setpoints require elaborate bench calibration and are verified during CHANNEL CALIBRATION. 'IlggEisIs@{1(d2 CP~3~3'ED2 fl9 UKIUM r,sia w = ._. - a . m x- r == v= wmmu /
i . . . . 3Bb9f95140MI7Eij'peWer
- rC'. ...;, L _ -_-- _ ,_ _ _ 4 % L . r. C . T v i7ie-3 Frequency is adequate. It is Dased on industry operating experience, considering instrument reliability and operating history data.
(continued) CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-119 in9/99
ESFAS Instrumentation B 3.3.2 BASES l
.SR 3.3.2.8 SR 3.3.2.8 is the performance of a TAD 0T. This test is a check of the Manual Actuation Functions and AFW pump start
.on trip of all MFW pumps. : ( .s g g u4 M1 cA.3.3 005 1 M ll m!htvolfssottistant!stsansmestasEste3mses Idplreitm1088AlmaBWdp]EtwapaRatigtMWlDs2the cogacts;fgrJ* akgg;#_*=*1ep7**==+*** It h nerfonned every 18 months.Jpis.- ,_MJIerjeeXActisstlag.
CP-3.3 ED2 [wlanjl$sl,3ggggggggq3 bgg,@gt3gclu#ggEthelaaster; rglgy AL11s.'Eghiggegg38!gdangMtMigmastgMartail i
- a:wharfarameinPNWithRX3;2;472.nn F.;;;;l l Actation Function i; t;;ted up ;;. x; .;;;- ng, th; =; tor 0 3.3 G.1 rel;y ;;il;. In ;a in; tex;;. th; tat ixlui; ;;tation of th; ad d;;ic; (i.;.. pu:p ;t;rt;. volv; cycl;;. etc.).
The Frequency.is adequate, based on industry operating experience and is consistent with the typical refueling cycle. The SR is modified by a Note that excludes verification of setpoints during the TADOT for manual initiation Functions. The manual initiation Functions have no associated setpoints. SR 3.3.2.9 SR 3.3.2.9 is the performance of a CHANNEL CALIBRATION. ACHANNELCALIBRATIONisperformedevery1$ months,or approximately at every refueling. CHANNEL CALIBRATION is a complete check of the instrument loop. including the sensor. The j test verifies that the chsnnel responds to measured parameter ! within the necessary range and accuracy. ! I CHANNEL CALIBRATIONS must be performed consistent with the assumptions of the unit specific setpoint methodology.-The i diff;rina kt ;; th; cu. re..t ";; f;;nd" v;1x; end th; pr;vi;;; t;;t 'n 1;ft" =12:; ;;;nt k ;esi; tat L'ith th; drift ;11;;;; u;;d in th; =tpoint ntheil;gy. l The Frequency of 18 months is based on the assumption of an 1g month calibration interval in the determination of 0-3.3 G 1 the magnitude of equipment drift in the setpoint methodology. i i This SR is modified by a Note stating that this test should .,,_ include verification that the time constants are ad.iusted to y,j,j,5 the prescribed values where app 11cablw ,;.%a. ;w -
,.u w -- .==.....m-Q w .m m.u m ... ..
(continued) CPSESMarkup ofNUREG-1431 Bases -ITS3.3 ' B 3.3-120 109/99
l' l 1 ESFAS Instrumentation B 3.3.2 1 BASES l m - -.,- . m .-_..- u - - _.u.. ___. 7 l l
. - . .. -mm .--_ . - ,. . m r w,.n .
vn , , nn. CPb.bbb2 i I SR 3.3.2.10 Q 1.1 4 This SR gsLPeg verific; the isn;Mindividual channel ESF 1 RESPONSE TIMES are less than or equal to the maximum values 0 3.3 55 assumed in the i i i 1 1 1 1 I 1 i l 1 l l l (continued) CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-120a 109M9
, .~. .. .. ... . -. - . ~ . . . - . - .- . -.- .-- - - -.---. - .
ESFAS Instrumentation-B 3.3.2 7-BASES-i accident analysis. Response Time p l 0 1.1 4 misniremannunmansmand acceptance criteria are included in the ! Technical Requirements Manual (Ref. 7). 6lEgelg[s1ctLes!al, ) gger .JdunstsAWMEUnalakles3hesq 0-3.3-55
, , _ . . . ______.....,. .-m . ... . _ .,..~ .... .
l N 7 M those j clRhrlel 1 1 i. .c sM388318E IdlRHBl!Ogsg!anseltjug ; fem-westas~nserW perforeWWEdgMigatlMIMg"$1B@ Individual component response
- times are not modeled in the analyses. The analyses model the 1 overall or total elapsed time, from the point at which the ,
parameter exceeds the Trip Setpoint value at the sensor, to the point at which the equipment in both trains reaches the required i functional state (e.g., pumps at rated discharge pressure, valves 1 in full open or closed position). For channels that include dynamic transfer functions (e.g., lag, lead / lag, rate / lag.. etc.), the response time testing;sjay , bej nrific; tic , 'i ny k performed with the transfer functions set te ;; with t k r;;ulting n aur;d r;; pa;; tin ; M icd t; t h ;pp ;pri;t; ISA" re; pa;; ti n. Alternet:1y tk r;;pa;; ti x t=t an k perferad with th; tin cen; tat:; 3;t t; their r.;;;;inel , velu; previded th; required rapa; tin i; =;1ytially l
=icul;ted n;;in; the tin ant =t; ;r; ;;t at their nominal i values. The response time may be(meanutejd verified by a series of overlapping tests such that the entire response time is measuted- ;
measured-sees #. !
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i i (continued) CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-121 1/29M9 i
_ _ . _ . ~ _ . _ ._. _ . . _ _ . _ . - . . . __ . _ _ . ._ _ ._ _ . _ . ESFAS Instrumentation B 3.3.2 BASES : l
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.. .n~ ~ ras ~v2mawxeu-w: w= . m- aw azwwf s. v ESF RESPONSE TIME JeAggrg verificatic. i perfornec s. an 0 1.1 4 la month STAGGERED TEST BASIS. The31LesgggMMM sheMM2104 Hit 3MatBERelata153uctlintstMetIDtathEeN tested?ftMfft&lNEMNIIERdRDerS4615pthM Testing of the final actuation devices, which make up the bulk of the response time, is included in the test 4nt4Riffettientesgjg of each channel. The .
final actuation device in one train is tested with each channel. Therefore, staggered testing results in response time verification of these devices every M months. The g month Frequency is consistent with the typical refueling cycle and is based on unit operating experience, which shows that random failures of instrumentation components causing serious response time degradation, but not channel failure, are infrequent occurrences. Thic SR is modified by a Note that clarifies that the turbine. driven AFW pump is tested within 24 hours after 0 3.3 G 1 reaching-1000 53g psig in the SGs. CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-121a 1/2989
ESFAS Instrumentation B 3.3.2 BASES (continued)
- 5. 10 CFR 50.49.
i
- 6. WCAP 10271 P A, Supplement 2, Rev.1. June 1990.
- 7. Technical Requirements Manual.
a t.e a n geren g
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i
- CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-123 1/29M9 l
I l
- .- .. - . . . . . . _ . . . .- . ~ . . . - . .-. .
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: CP 3.3-ED3 (new) APPLICABILITY: CP REQUEST: Based on feedback received from the NRC reviewer, the following Bases pages for LCO 3.3.3 have been revised as noted on the attached pages. ATTACHED PAGES:
' Attachment 9, CTS 3/4.3 -ITS 3.3 EnclSB. B 3.3-126,127,129,130,131,133,134,135,136,137,139a,141,142 and 144 l
l l l. l l 1 4
4 I
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'j B 3.3 INSTRUMENTATION l BT3.3.3' Post Accident Monitoring (PAM) Instrumentation IBASES- ,
BACKGROUND The primary purpose of the PAM instrumentation is to display unit ' ; variables.that provide information required by the control room ! operators during accident situations. This information provides j the necessary support for the operator to take'the manual' actions -l for which no automatic control is provided and that are required i for safety systems to accomplish their safety functions for Design. Basis Accidents (DBAs). P
- The OPERABILITY of the accident monitoring instrumentation ensures that there is sufficient information available on _. )
selected unit parameters to monitor and to assess unit status and l behavior following an accident. The availability of accident monitoring instrumentation is ! important so that responses to corrective actions can be observed ! and the need for, and magnitude of, further actions can be determined. These essential instruments are identified by unit specific documents (Ref.1) addressing the recommendations of Regulatory Guide 1.97 (Ref. 2) as required by Supplement 1 to ]' NUREG 0737 (Ref. 3). E The. instrument channels required to be OPERABLE by this LCO , include two classes of parameters identified during unit specific implementation of Regulatory Guide 1.97 as Type A Cgegqry3 l
$}} Type A'Jggggy11, variables are included in this LC0 because
- they provide the primary information required for the control room operator to take specific manually controlled actions for l which no automatic control is provided, and that are required for safety systems to accomplish their safety functions for DBAs.
";;;;; tk li:t of Typ A v;ri;bic: differ; wid:ly ktuna aits, T;bi; 3.0.01 in tk eas,,=ying LC0 cat; ins n; =apl;;
L ef Typ A v;ri;bic:, a;;pt f;r tMn tMt ay ;is; k 0;t;F,r., I L , veri;bla. (continued) 4 r 1 CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 . B 3.3-126 1/2989 m ..
. PAM Instrumentation B 3.3.3
- BASES
- I gM m1 9 ategory 1 ] variables ar; th; k;y veri;bi;;
i deemed risk significant because they are needed to: I- . Determine whether other systems important to safety are performing their intended functions:
. Provide information to the operators that will enable them to l determine the likelihood of a gross breach of the barriers to l radioactivity release; and
- .. Provide information regarding the pgentig release of i'
. radioactive materials to allow for early indication of the need to initiate action necessary to protect the public, and to estimate the magnitude of any impending threat.
These6 variables are identified by the unit specific CP-3.3 ED3 Regulatory Guide 1.97 analyses (Ref.1). These analyses identify the unit specific Type A and non;-JypeM Category 1 i
- .' 1 variables and provide justification for deviating from the NRC proposed list of Category 11 variables.
" sis-'- %:. !;bi- 3.3.31 - nida ; li-t ;f nri;bic; e twical of th;;; id .itified by the ur.it :g;ific ",c,ul: tory 0;id: 1."7 =:ly;;;. T ble 0.0.01 ir ur.it g;ific 7xhr.ical j SF-ifi;;ti;- (TS) :h;11 li;t :11 Typ A Zd__.,.__..,..u. Cot;,,;ry I n, l
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- =;ly
- ::, :: ; .;..ded by th; L"',0' S;f;ty Evaluatie , ";p-t (SC",) .
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CP 3.3-ED3 MD !!!EttGEMMEBERtd icontsim!!llmtlingsflmtcand i!dJild315lElWWEBilllBBattu!stiMMRO!BIshimmt pr#8 . . A ter3 m z a m ; s 6.; _ _ Mg!statoGgt.emegunttog[tange M!d:pBMillDBfBMeKI (continued) CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-127 1/29M9
PAM Instrumentation B 3.3.3 l' H' BASES 1 1 I LCO -The PAM instrumentation LCO provides OPERABILITY requirements for i Regulatory Guide 1.97 Type A ;.w..it;--anammanamesammal, which
-provide information required by the control room operators to perform certain manual actions specified in the unit Emergency j
! Operating Procedures. These manual actions ensure that a system H can accomplish its safety function, and are credited in the safety - analyses. Additionally, this LCO addresses:M Regulatory , Guide 1.97 instruments that have been' designated Category + 1 non Type A.
- r. The OPERABILITY of the PAM instrumentation ensures there is sufficient information available on selected unit parameters to monitor and assess unit status following an accident. This I capability is consistent with the recommendations of Reference 1. ,
en a e a --_.a___ A. ._ nnen.na e _L___-1_ ,__ ___ , www . w,,w s . w e b- w. - wu ru .u m , d , v. " ** d.w.d
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- r. ._ _ a _ _ _ _ _ _ . . _ _ __
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n,.___ Ab.L.w. 2s ,_..m-k n - -_ _ A 2 w_ _,. . ~ ww d y, w . w . . b d 7,., u w d b b s , ., s . ,. . s__ AL__ A_ 3t__>__ AL- __m_A.. _AA.._ _ SAL _ . ._2 A __a A_ L_2 _ s w1 be swsar DW ww wws usu irw WWTw du a ,e bg .5 bu bud v3 br m wa s a b , w rw by wi 5 y m_ . ._ m A_ -_2 __2_A_2_ m 2_ _ __,_ - - _ 2 2 m __ ,_1, _ a _ _ __ bt tw wu i B b bw ut T%s WWtsIIsbns3Is ab 54e u duaw %,wl7%E5brwy5 5WI 3 vWW a s Ty ui5 6MW.d!htWlg113NEMB@CDD s1ggleltangssammatERmantonifrigD$ttW2hmfarmetfog naassagemasuganistgeswahe3stistrEm!@Ethemnit71and , tortunnsamBImussassamntaresNamMRaschilowma anacc . e c " m E .h -ggb ggEbMetgggonIgn - g g g., c m' 4c,' reemass 1 Furthermore, OPERABILITY of two channels allows a CHANNEL CHECK during the post accident phase to confirm the validity of displayed information. w ; t'r;. . de..~1; .r;y be rewired ;t
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I (continued) CPSESMarkup ofNUREG-N31 Bases -ITS 3.3 B 3.3-129 1/29/99
PAM Instrumentation B 3.3.3 $ BASES l l 4
;~
Table 3.3.31 provides a list of variables typicel ;f tt.e;; identified by the unit specific Regulatory Guide 1.97 (Ref.1) analyses. T;ble 3.3.3 1 in unit
, _ _ _ _ m _ r, _ u _. . , 2 ,,_ 2, , . . . _ _ . __; r.i____.. , ..._2.<,__ 2 2 m m _; c.. mu_
wy,ww a # w aw suvvuau aaew uua s yprw gs ussu wu wwyys y a yus awwawe s wws s w s s s wu wy besw ___, a ung._ c ._2.
.. k m .,,,ww., .. . - ,. r.. u. _ ..,,
____ m.w_ now_ _..,.i..__
, n,
. . . . . , . . .n.
.~.w.
t
-,. . m ,~u .mw
_ ,, c,m
,n Typ; A ad(yptWanjCategory 11 variables are required to meet cp.3.3.ED3 Regulatory uume 2.w Category 11 (Ref. 2) design and qualification requirements for seismic and environmental qualification, single failure criterion, utilization of emergency standby power, immediately accessible display, continuous readout, and recording of display.
l Listed below are discussions of the specified instrument Functions listed in Table 3.3.31. Th;;; di G;;im; ;r^ intenid = cxspic; ef #.;t ;heuld b; i 4 previid for ;;;h function den the unit puific li;t i; propered. 1.
; 1, 2. "scr "=c nd Sarce ",== !!cutra riux i
Pr,= ",x; ad Seura ";n;; !;utren flux ir, diction i; F ;;iid t; V;rify TG ;ter ;hutd;Wn. Th; tW; ras;; er; nec;;;ery to aver the full rs;; cf flux th;t =y ;;;ur ___n, .__a~
- ,,. m.w . .w . . . .
!istien flux i u;;d for ;;;ident die;ne;i;, verific;ti= l
_ . . .e _ _ s u _ . , a s . . __; n____.,. _ a _ _ _ : a . ._ __..,..a... wa wwww a c b 3 wu u 4 by , witw w a wyu av e 4 en ws giver s b s vv i www b 3 w s by
; in ,crtion.- l 1] RefuelindTWaterMit6 Pad 64ahl("(RidSTFlairel
@AIRD6E11814."JNd Yataln - less3ReniGM tJWXWtnampaanN00RG!apl21bitl]eglgg@AglEis liroVkledWDtBlMERfRSBaBMB$$15t31ti7#0ftftof$nlHNDd egot199MGaggggggmywwatervonsafetyJlpaetttog anWtontggmalagmK3 2;] SubcdolinfMonitBM acs;subcMINagttyrr$RtempeEcategorE13atjAbleEf.ot RCS*Wling3SRtermination[reinit[1atjonRaator8M (continued)
CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-13G 129/99
.. _ _-. ~ . _ _ . - _ _
4 c 4. PAM Instrumentation B 3.3.3 l ggs i 1: -4
- esammanasasenant.incautmammacEm1annanawamanmemme ,
3,.4. Reactor Coolant System (RCS) Hot and Cold Leo Temperatures"idilstWRekk) RC53Le$ Intl 3pl@tEaugatherAtLType!CCategorG vatsables59t*maingttengaropermKeirculation a cgijltidg43glJjgogg,91; heat 3emoyallatesHRCS Hot and Cold Leg Temperatures are alsoHype18 Category 11 variables provided for verification ;f are seling ad i len; ter; surv;illas, mortitorjpg;HC511ntegr,ttyistatus j ' treM , RCS hot and cold leg temperatures GT Jand2 Ted CP-3.3-007 respectjye]y),areusedtodeter;in;RCSsubs;l:ng mee9+n providelinpytito;the'Subcoolteg1 Monitor; RGS subseling =rgin will all;w ter;in; tion of sefety J J - L J .- #PT% Jr AJ11 J- -------- -- - J JAJ.AJ - X PT g a sgvw h s va s gw&J. #u dbsss sus ysvysudd. vu e u a s s u b a ts b a vu s vs wa if it hn ban stepped. RCS sub;;; ling nigin is al ; u cd ! for unit st; bili;; tion ad cesl&/ rs satrol. In addition. RCS cold leg temperature is used in conjunction with RCS hot leg temperature to verify the unit conditions.necessary to establish natural circulation in the RCS. Rn;ter ;;ti;t ti y;r;tur; input- t; th- RG;ter ; pret;; tion Systs ;r previded by tw; fest respens; resistaa ci;. sts ad =.xi;ted tron;;itters in CP 3.3 009
^^^' '--- 'EacrupTEheriflotMthatWegt3tld_* tach _
l oLL i f M M Q [ ' G E s iC,~1,um'#srT"if85t n M CP 3.3 ED3 RMilne cnaimis EPAEnumspxprov1oe ino1 cation over a range of 32 RQ'F to 700*F gggf2l2J.
- 5. Reactor Coolant System Pressure (Wide Ranae)
REgi@230gggetRelt8%TypeX9Ltegoryl ariable fM18D@D11GW15!lI#3181Dat1Wteig1118tjonE1RCP;trjp andlevettt3tjpgnosigRCS wide range pressure is also a Type Bigjllq Category I variable provided for verifistien of cer; seling ad ognitgjgg RCS 1,1tegrity] len; t r; surv;ill a n . (continued)
. CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3131 129/99 C, .-.
i PAM Instrumentation l B 3.3.3 ; BASES- ; I
- 5. Reactor Coolant System Pressure (Wide Ranae) (continued)
In ;;e ; unit , RCS pressure is a Type A variable because : the operator uses this indication to monitor the cooldown j of the RCS following a steam generator tube rupture (SGTR) ! or small. break LOCA.' Operator actions to maintain a controlled cooldown, such as adjusting steam generator (SG) j pressure or level, would use this indication. Furthermore, RCS pressure is one factor that may be used in decisions to , terminate RCP' operation. j i
- 6. Reactor Vessel Water Level 1 Reactor 1Vesse1JidateritanntE1.slalTgli 3 varfab1_elfgagitoringithe w=11na '
andrinventoryTstatusitre{ referenced 7tn the Emergency AllFratingProceaures TEOPs)Jueactor Vessel water Level is , provided for verification and long term surveillance of l core cooling. It is also used for accident diagnosis and , to determine reactor coolant inventory adequacy. ; The Reactor Vessel Watet-Level ",enitoringilndjcating] System ( _RVLIS)Jprovides a direct measurement of the i collapsed liquid level above the fuel alignment plate. The j collapsed level represents the amount of liquid mass that is in the reactor vessel above the core. Measurement of the collapsed water level is selected because it is a ; direct indication of the water inventory.' ' lCICEE ' ~' ' ... ^ 't-^r; ~ ~14'rt;; CP 3.3 ED3 j l
;J:7,=..;.4. s .:
s.a c .
----m-,
- --- G -
~~.-
- l
- 7. Containment Sumo Water Level (Wide Ranae)
C.---u mu-3 1 Cjig!stingamejgroD!n!!MilMENfEa!gd!se_rmining squ!miita!mgateitsing13egggg1Tygssategory3 ta]'itble7fW%ss,ijn!Fcont_a11ggj!ggtigesitret2 ) ,. Containment Sump Water Level is provided for verification i and long term surveillance of RCS integrity. , (continued) i i L CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-133 ' 1f1989
t L PAM Instrumentation B 3.3.3
- BASES Containment Sump Water Level is used to determine
r containment" sump level accident diagnosis: L I . when to begin the recirculation procedure; and L . whether to terminate sis if still in progress. I F.. L ! 8. Containment Pressure Mde intaggadiate Ranae) Cosgslggest@30peural ~A 1ak . .. ._ _ .a I var 18te?forlo.orriterin.g."contaj.reent?s.tatu2s'treo. . Containment Pressure (Mde Intet'medjate.~ Range) is provided _ l for verification of RCS and containment OPERABILITY. i [
,m- _ _ - - - . . - - 2_ . . _ _ , .- ..-_2,.. , - - . . - - , _2_
l wwv i b u u s ieurwa u b ya w d dut s se p ers w kw vws asg w s wdss W vu ursu s y s
- L--- 2 1 L2-- ..1..-- ruetu-g -> -- L 2--- L - - . .
.a bwomess adviubIvsu TuaTwd g u sw a y e / e us ugs wVI s bu s u usvews i b .Pyu up m- - . ,-
nL,u ..,. n L g u w 2. 1. _. 2 ._._ - -. .s n 2. ._L
.v s .,, -.. . b u s u _- s . b r_ _w _. - us . . .w_ -u.,,
; cr' "(geggtsse~nt]pressuredsiuseeJ,0.
verify CP 3.3.ED3 c]geprfefiM1 M M el so M icrfJa Wes3 MSIVs)Z and c_o_ntpsment15p.r.efm. a_s,.e.~'B...es. Ph M s.ol a.ntioniwh.e.~n n um mMi.gh 33,. s.- i l f*m L=J -mmL Tmai LJ-- U m 1 n .- h- JLJmm j. f f* T U n- JL2-- 2. ---.1J J 2-- ..- 222- 62-- .n 2 t'- Lal----g wav I w.aab:wis aa yi w w a wwss u vs wws s5 5 bu b s vil wa wws i b u a a wavew s a e.
#inenAnTtTTU -J ML--- A -J nL -- B J. 1.LJ-=
v5 bsma s.& u a e usrw I 5 su.ph n ut F%s u 5 vu dw w B Fw I u b I wu u o I e st ._ ..- J L- ..._2g.. nL.-_ a -_J nL.-- n 2- 1 LJ- LL-sui sws a u dwge kw wwu asy a u ru ers n unrw sgruers w s erv a u b a vi uo harw 2--L-L 2 2-- L2- 2. LL- 2- 1,62-- LL- 2 LL-uaau wssuvu b5via ud bs tw adW uu b aviu d b us b u .F ws betw f[ s susyvi bus Ib L--- 1 2
-- L 2--- L --
L.- 62- . 1"L - t 9mn ---.2.--- --- w wsabu auusuawssb ywu rw bc u b a vs sd e aasw uvv s wgu a s w e vurw wi sus si rw s wa i' . 1 .- ---262-- 2 21- L2-- 2 .- LL- --A.-1 ---- A- L-yuavb yver s b s ws e # s aw a wu b i vi s aai burg bvs s b u w 5 s wvens kw ww nnenAntr 2- -- L .64..- PTO J. . -- L.2--- L --- L-.LJ-- v5 ba w 1w n.a. s ws w wws s uwbaww w&W u5g u wws y bu u a essews a b yws sw ks u b u vs s 21 -. . -.LL J - L..- A 6.1 L--- 1- 2 #* T H -- JLJ-- s a vvu yu bu s , c.w., www bv nru a ws sus va sw a .a wa vay yw d B b a vi s J JJ- L2-- 2-- . --- L-.LJ-- 21 m . -LL .J LL L. - m L J . ., s u pw a vu b I VI 5 s ws u ybstw bs u b svua a 5 vvy ygs bs 3 vs # bs i bww uwb5yw
..1..-- P-- --^-,2---L --- L- 62--- .2LL -1., --- . 6 4 .-
v u s w w.p e s vu wwu s bu s u iverwu s h yws sw ks u k s ys sa vs a bu s us u s y with uwb47% f* T H L-..J--. - - 2- --- 2 JJ-.&.J- u A. - (Lg ---..J--- . way szuv sury wwil b 4 w5 5 wwusu u s sw I bu b a vi s , avv bv gw/ 5 w%gu s s wd u
- 1. L-- -1 2 ..1- ---262-- 2 42-.L2-- ba La f\nr*n Ant V
.a s a ry a w wi sur si sw I wu vuavs ywd s b 5 vis u u rw Iwu b s VII ww ww wuhu m a.a..
l "rL2- 2- -.222 1- L L. - J. L 1. . ..-22. LL- .8 - S . 6 2 - p ui a d a en eru e a a w a wu s b bv s wwuv rwun a b u y vws asy bsrw a dv s u b vi u l LL.. 2 -- L 2 - 1.L1 - ---A,,..L2-.a 2LL-- 242=L-' i .y ,2 av.s s a r%s I wu bwns l d bu buey wa bugs e aavsupuw ybs sw b u u b vis w a bu rw7 i L.L.a 2 LL- . A. 2 . . - -- 12- L1- - .2 - ! dbubud vu brtw uwbavw ..1.., wuavs .- uyysawwwawe u n IM ys sv3 ud L--.1 2-- 2 - --- 2..- .2. -..6-- L-A.-.. j s%s svis u wwyb wa u ygs d d a v w vuavw .1.., -- vu yau dy d bwiss uvun swun y e aLL..- 12 - ----~11.. .62..- 961 U 2- L--- L- L- 1-- A -J t dbubud. 6a u s uvs issu a s y uwbevs wav 4d rsa vvvun a bw ww wswwww uirw A-. L2. L J ---262- 2.22- L2-- 2- -a -- J 1 A-
%swww b 5 y u bb%se ywd a b i wi u savu sw u b iviu ad s sw b a swwwwgs ww (continued) ; CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-134 in989
PAM Instrumentation B 3.3.3 BASES ]
. . . . . . _ ~ _ ___ .L. ___,,,__ ,_,,...,__ __ ...,..__ ,_
d.u.we. B u rb s b u va w , .irb pa s . s wv e 5 5 34 5 bu . s ys s s wi vunvwe uss _ __i ___..a__; u_i_ rs A.L.2.
. ._ .A. A. a. .~w ..,...M m. .L~ . n.n. en_a . ns e . .v... s , &v_ A..~L.
1 et_---,_ _ xL_ -i -- 2 n _ - . a. . .w.
. . . a. ._ a.
. L.L. _. L. .~ .r..__t.a..__.. a.. ..~.
. , ~ . w , 2.. .M ;
fu t aleti = v;1v a e.;x = vaiet;d g a tratica i: 1 i:clated by et le n t er.; cie nd ;r.d d= ;tiv;ted =ts.;ti; 1
. . . , . . . _,___> _ . _ . . , . . , . . . L,2_2 ,,____ __ m__.. . . . , . . .
Yu.Tw, wavawu wi sww a yuqvs, w s ausw a s vi ryw , ws ws ivwr% vwavs si m . L .. 1 .. _____J
.2L.L yr s tv s s wvt A.s ra_ ww.ysa._LA.L.
usw vusvs avwuu ww . r N I MegsmingattsgeremtaggiggenLr3emiereEjsla Tsimaggggl3mestM:tetaggettugagNZnaistal j cjn;3ggammaggtgrertgagenstssmg333pe i 83mgestyT***tet!gLMIsostatmelheatisin(1 status cy,3 3 gg3 l treeng;ggr ;.,;,teforwterminina'if's secondaryJL1pegh;nas;.oewi42 This:dndication 1 tsIpalideelt42agtyoperator11n;theljdent1(jcationiof the3aulted gram; generator ~and;to; verify;. natural ctreulatigt , 1 l 10. Containment Area Radiation (Hiah Ranae) Ra'n 7&isMype;E
~
I JOH _ . . .L3lgwa31gh3egaltment ra 3 i x . r aggagengesaggatesetst
~
)
i C neent Area Radi on or for the potential of significant radiation releases and to provide j_ release assessment for use by operators in determining the need to invoke site emergency plans. 1 C;atei. ,.r.t redistien in;l is ;v;d t; it;--ir.; if ; high
; cr;y lir.; brak O!C!1.) has acurred, er.d dether th; ,
2 n;nt i; in-ii er eut:id; ef ;w;teir ~7,t. I 4
- 11. Hydroaen Monitors Hydteg![Q!pnitatGNU)ng;B1Cg.t_egotyllWattabl.gsitot
, hMrdgg[13RggMatsger4tionIRt351els_ola3ygiCECategory j 13ertablggggggstempeggio12rgachroficet:ainment bo]Md_ qty 3 Hydrogen Monitors are provided to detect high I hydrogen concentration conditions that represent a ! f i g (continued) l CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-135 1/29/99 l
PAM Instrumentation
.B 3.3.3 i
-BASES potential' for containment breach from a hydrogen explosion. !
This variable is also important in verifying the adequacy , of mitigating actions. ,
- 12. Pressurizei ^ ^ ^ ^ '-< Level Pten!W!rJatilRO!ItBWPYKT3Mi&SellegemIIIvettablelfot StagametaseggmassetNnanminsjugespir3 fotM;WJgge,EPressurizer Level is used to determine whether to terminate SI, if still in progress, or to reinitiate SI if it has been stopped.
Knowledge of pressurizer water level is also used to verify the unit conditions necessary to establish natural circulation in the RCS and to verify that the unit is maintained in a safe shutdown condition.
- 13. Steam Generator Water Level (W4de Narrow Rance)
Steg!gggel220rlil9tliePhilRingoljutangeEjfalType A;categ!!cylpggtglGarMAtem31pnerator2Iu_be RupptEg!!gggg3Rg31Gl$115IBgWiggtidGIt31s E also'ylgggggggorygipciable2Dr . M_3tE1003E18EBEf141 j 00 'Atr L;ni i: previd;d to ;;.eaiter egr;tien of i;;y M;t reev;l vi; tre 00;. TP.; 0;t;;ery I indic;ti= cf 00
.leni is tk ;xt; aid :;t;-tup r;r.g 1;=1 instrunat; tion.
Tk cxter.id st;rtup r;r.g 1;V;l ;;nr; ; ;pa of 2 0 irek; to iS4 irek:; ekx tk 1;;r tak:;k;t. TP; naured diff;rcati;l pr;nur; i; di;pi;y;d in irek:; cf water et 00*I. T;;;.gretur; ;4 antic. ;f tr.is irdi;etien is Frfered
=n=lly by tk egreter. "cind=t reait; ring ;;Fbility i; previid by twe treins ;f instrL;;;nt;ti;n. 3; ure+ ant;d leni sig ci i; input t; tk unit ;4tcr. ;
;;atr;l ree;;; indi;;ter, and tk E;;;rgrey T;;ieter Centr;l SM SG Water Level (Wide !NE gg Range) is used to:
. identify the faulted SG following a tube rupture:
- verify that the intact SGs are an adequate heat sink for the reactor; (continued)
CPSES Markup ofNUREG-1431 Bases -ITS3.3 B 3.3-136 1/29/99
t i PAM Instrumentation B 3.3.3 BASES
. determine the nature of the accident in progress (e.g., verify an SGTR): and
. . verify unit conditions for termination of SI during secondary unit HELBs outside containment.
At s unit:. egreter OnRgtDR action is based on the control room indication of SG 1evel. The RCS CP 3.3-ED3 response during a' design basis ==all head IMa dM nn the break sizeJggiggBjggggigIL _.._lMllMGllM91GlFJit!gdeL84W3DJileMiteetitransfer (rnD!st.slao11nipDBeiplemags3therformsM;decaytheat ream 1zng!ientmet4cCt! ster 3evel3narro(range)1is:a Type @lystMiggMithelopentorieustimanually; control SG119felitttCesta$lish"an.ladequa!te; heat sisikdf3helst.eam generatoCM;1eyeliJnarrogangel3pdicationlis onis_ cal.e (' r(fncludjngl!Lcettgis!tigs)?We*heatisinkito;*aaart efluKiccoling"ekists'J, .. ; artein r=g a .. -- .n';.
=; z u ;r ;;.. ..x r ;c of h a t tren:f;r 1: nen :nry te rer.~v; i cy hat. Extended st;rtup ra g 1;v-l i: ;
Typ A v;riabi; b;;;us; th; egr;ter =';t snucily reis; d __;_-._.,e.,,.w_..,
- u. w.i . . . a . wwa m. s
._ _c,2 m.u. e s . st. .
c ,,.. ___>____. aaw. w w..wss t.ww.. . s tr=-fer. Ogr;ter ution i; initiated = ; 103 Of sub; eel;d = ri;in. Tud.;;ter ' low i; ircices;d until th; indict;d enter.id stcrtup rug 1;ni re;;ha th; hei'cr
. ~~..~. s.y.....
- 14. Condensate Storaae Tank (CST) Level M M 19P M Categor G J e VilEMG. @ Mf!t1Hary i m _ X olstatic Esgyfce wLtg3 CST Level is provided to ensure water suppl
. CP 3.3 ED3 for auxilia y feedwater (AFW). The CST provides G .; ;.;uredisaretyJ grade water- supply n .. , s for the AFW
. ~ . .e,,-
. . . a. x. . .. - . _ . . . s. . ,....t.,
...m. .....~ ...,
of m . by ; c a =tlet hair. Inventory is monitored by e 0 inch t; 14' irch 3lKIdet19j1lpl1J00Elevel indication for
-each tank. CST Level is displayed on a control room indicator. : trip ch;rt r u er i r, and unit computer. In 4
addition, a control room annunciator alarms on low level. (continued) 1-CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-137 U2989
l PAM Instrumentation B 3.3.3 BASES I _fggigtMJiryXeg$lettrifNWHAFW Flow is provided to l monitor operation of decay heat removal via the SGs.;g l CP 3.3 ED3 l I M MR C h ls;ol / m.4. ___=Eag3agangsammerorwu >
~ "J _. - ~Tr__ _ _ ovim-=__ --3 pidiiiErangenbe 00!GbJaM The AFW Flow to each SG is determined from a differential pressure measurement calibrated for a range of 0 gpm to l 4000559gpm. Redundant monitoring capability is provided ! by two independent trains of floWjinstrumentation for each l SG. Each differential pressure transmitter provides an input to a control room indicator and the unit computer.
Since the primary indication used by the operator during an accident is the control room indicator, the PAM l- specification deals specifically with this portion of the l instrument channel. l L i. (continued) CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B3.3-139a ' 1D9/99
PAM Instrumentation B 3.3.3 BASES instruments and methods, and the low probability of an event requiring these instruments. Note 2 has been added in the ACTIONS to clarify the application of.Conpletion Time rules. The Conditions of this Specification may be entered independently for each Function listed on Table 3.3.3-1. The Completion Time (s) of the inoperable channel (s) of a Function will be tracked separately for each Function starting from the time the Condition was entered for o.3,3 7o
- that Function. IgggitINCRgut_redjChannels3nHat>}e;313l.311 EspapRgggN333GUper'21oopy,2efistedelitu[eerg goedre#3!Bd5239mEtKronditMeaEMenteced separate 1Efoc tech;SE210REMeme%K.ZZ_1-43slapproprjatej a.1-Condition A applies when one or more Functions have one required channel that is inoperable. Required Action A.1 requires restoring the inoperable channel to OPERABLE status within 30 days. The 30 day Completion Time is based on operating experience and takes into account the remaining OPERABLE channel (or in the case of a function that has only one required channel, other non-Regulatory Guide 1.97 instrument channels to monitor the Function), the passive nature of the instrument (no critical automatic action is assumed to occur from these instruments), and the low probability of an event requiring PAM instrumentation durin this interval. ~ , , emm
- -~
.---.a--..-
CP-3.3 E03
- w. - _ u _ m w . _ ,n.m ... u _
IL1 i l Condition B applies when the Required Action and associated Completion Time for Condition A are not met. This Required Action specifies initiation of actions in Specification 5.6.8, which requires a written report to be submitted to the NRC l i_di;talyRREg3lgfgd35!197-1343dys. Thi; r- re,-t l m __..____ m_ ___..u. _, m_ ___ __..__ ._ ,.. ,__ , m .
'_ "l ' * " ' ,I'_' ' '~_' _ I""': _I ' ".' "". I. ! !"._!L. , ._'".'. CP 3.3 ED3 s
", ~y
,' ," ~E I. ,. I. ..
".'7. . ......
r..,~,. . - .. . ... ! Thi: :: tier,i:
.~.,,-.-._,_,_n_-._,.,.,i,.,---" -
- ,^ ^ ; =';;;ng,
"-i._.,,,g 7
.._ ~. _
W1**"ksanch. ----~ ~ - -- N&n,MSNMJ,.aD.Faisi ,,wcm Ud D D EZ4.E*W'W l, C :.Um=Wm W _=vEiatep m i mu vi a snutoown requiremen'; since alternative actions are identified before loss ,' of functional l (continued) CPSESMarksy ofNUREG-1431 Bases -ITS 3.3 B 3.3-141 in9M9
I PM Instrumentation B 3.3.3 BASES capability, and given the likelihood of unit conditions that would require information provided by this instrumentation. ' C1 Condition C applies when one or more. Functions have two inoperable required channels (i.e., two channels inoperable in the same FunctioniMMteL%Jl$tt!!$}Ia@RMgtjf'edlCoN
$1tiTeinglLetareistienneMMope! aMeEeO!nie7egfjted2T,,u[ channel R Eon me]pess!EL:MelP_tessureicpteFlotithe gsoejag g g_ p g g g ;[_= g_g g g g gj m---mem.mn -a -m- ~x ~x - s uw-sm.-m 0-3.340 AR(fedete). Required Action C.1 requires restoring
. one channel in the Function (s) to OPERABLE status within 7 days. The Completion Time of 7 days is based on the relatively low probability of an event requiring PM instrument operation and the availability of alternate c 3.0 000 means to nh M a A -oi mi informatinn q;;;;;i_7 ;-g;;; ,CP-3.3-E03
_ _ . _ _ _ ._ _ _ m .__ _ - _ __ _
"h*Hf"S="2M~E?""M95di'~2.9'"EL n-rum _-an ame sm-sm rurtaymm-u.-s C L -r k E n 1 ~.D Continuous operation with two required channels inoperable in a Function is not acceptatile because the alternate indications may not fully meet all perfcrmance qualification requirements applied to,the PM instrumentation. Therefore, requiring restoration of one inoperable channel of the Function limits the risk that the PM Function will be in a degraded condition should an accident occur. Condition C is modified by a Note that excludes hydrogen monitor channels.
Q1 Condition D applies when two hydrogen monitor channels are inoperable. Required Action D.1 requires restoring one hydrogen monitor channel to OPERABLE status within 72 hours. The 72 hour Completion Time is reasonable based on the backup capability of
.the Post Accident Sampling System to monitor the hydrogen concentration for evaluation of core damage and to provide information for operator decisions. Also, it is unlikely that a LOCA (which would cause cere damage) would occur during this time.
i (continued) CPSES Markup ofNUREG-H31 Bases -ITS 3.3 B 3.3.H2 U2989
PAM Instrumentation B 3.3.3
' BASES are not equivalent, and provide a sshedule for restoring the normal PAM channels.
' SURVEILLANCE A Note has been added to the SR Table to clarify that
. REQUIREMENTS SR 3.3.3.1 and.SR 3.3.3.24 apply to each PAM CP 3.3 017 instrumentation Function in Table 3.3.3-12.;;;;A;-.;;;; __...'. m__,,-...___'. ~ _ - - . _ - CP 3.3 ED3 i q=.e meavv. m m e - a m w ,. .m-
}
SR 3.3.3.1 Performance of the CHANNEL CHECK once every 31 days ensures that a gross-instrumentation failure has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one-channel to a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant , f deviations between the two instrument channels could be an indication of excessive instrument drift in one of the channels or of something even more serious. A CHANNEL CHECK will detect gross channel failure: thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION. Th: hit, r:dictica in trant:tien ;hald b; ;4 red t: ;i;;;il;r unit in;trwat; 1;;eted thrw#,wt the , tm%- Agreement criteria are determined by the unit staff, based on a combination of the channel instrument uncertainties, including isolation, indication, and readability. If a channel is outside the criteria, it may be an indication that the sensor or the signal processing equipment has drifted outside its limit. If the channels are within the criteria, it is an indication that the channels are OPERABLE. As specified in the SR, a CHANNEL CHECK is only required for those channels that are normally energized. AlllDffitt!g 0-7-09 JHstruentUiH12 MIN 1DN##Wi3N3 red 0ntelly: energized! The Frequency of 31 days is based on operating experience that demonstrates that channel failure is rare. The CHANNEL CHECK supplements less formal, but more frequent, checks of channels (continued)
- CPSES Merhap ofNUREG-1431 Bases -ITS 3.3 B 3.3144 1/19199
ADDITIONAL INFORMATION COVER SHEET i
. ADDITIONAL INFORMATION NO: CP 3.3-ED4 (new) APPLICABILITY: CP ' REQUEST: Based on feedback received from the NRC reviewer, the following Bases page l
for LCO 3.3.4 has been revised as noted on the attached pages.
$ ATTACHED PAGES:
Attachment 9, CTS 3/4.3 - ITS 3.3 , Enci5B B 3.3-146a - !
)
i l l l i
. , . - - - - . ~ _ - . . - - . - . ~ -
Remote Shutdown System B 3.3.4 BASES
. sMg!WrAmetDatadtGRE!*@ewf***** TAIL 1cludfg samlageneggepepassegg13erpsemeyssiasservonen 04-08a
%33.L iE+14ee
~
.. 1eanissal 7 . ..
l - .. EILM , ingMatiH9W3893'anteMWaleMlWKchemelsrit .gg""""l neuestgrug!agtsKt!!gatt!!!!Mzgte:Misare!tidedMg TieOMst! Mill Wi4?!?BTE2W70HEIMECHREERKERIMItBIG3BTMBEEATENI WIG ~iEE?iCi!%S FjMALIMJ INSTIM Elli 170FCHAIAlELS 1111eutron;FluxjMonitor,s32 2 2;Mde, Range 1RCS;Iemp;1T, 1/ Loop 31MdetB!!gge;RCSIIemp2T, 1/ Loop (continued) CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-146a 1/29/99
- c. _ _ .-
l l t ADDITIONAL INFORMATION COVER SHEET l l ADDITIONAL INFORMATION NO: CP 3.3-ED5 (new) APPLICABILITY: CP 4 i . REQUEST: . Based on feedback received from the NRC reviewer, the following Bases pages for LCO 3.3.5 have been revised as noted on the attached pages. i ^ ATTACHED PAGES: l { Attachment 9, CTS 3/4.3 '- ITS 3.3 Enci58 B 3.3-153,153a,154,156 and 156a a P e r
?
. I l
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: CP 3.3-ED5 (new) . APPLICABILITY: CP REQUEST: . Based on feedback received from the NRC reviewer, the following Bases pages for LCO 3.3.5 have been revised as noted on the attached pages. ATTACHED PAGES: Attachment 9, CTS 3/4.3 - ITS 3.3 Enc!SB B 3.3153,153a,154,156 and 156a , i I l
- . _ . . _ . _ . _ . . ._ _ . . . - . _ _ _ . _ . . ~ . . . __ . . _ _ . _ . _ _ . _ _ . . _
LOP DG Start Instrumentation B 3.3.5 i B 3.3 INSTRUMENTATION B 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation BASES BACKGROUND The DGs provide a source of emergency power when offsite power is either unavailable or is insufficiently stable to allow safe unit operation. Undervoltage protection will generate an LOP start if a loss of volt = ne degraded voltage condition occurs in the-(ggCQ G t .hyerMher; grc tw LO" : tert :b- ch. era for ::ch 4. m n v n:1 F= - g._ - CP-3 3 EDS 1 _._ _ _ _ ,.. __ _ m , _ _ - ___. ..y,,+__- e ,..__.__.___._..._____.._,m__m_._m.-m..-- _ . _ _ _ . .. . _ _ _ .m,a . ...s.s % eneu = 0 3.3 131 5_m__._. ses--ma----
--.__,__,___m...__....._
=_ m.mm%-s.mm=& _m a __.
. .L.m-m_-m J, .:.x,_ ._-..--__m--__,.
m urA,,.= .%_- .m_.u.o..-2.m_. n .__._re__2 - -e m___-n __ m m __ y-mm . ., - -v ~ ~ - . 2=.-,_v-. =,. .w.,_
~
n.m . . m e - m. ..- nn- -.3 .i - ,P-m. m ._ , an.. ~i..i
....m... , = ,=-.m , . ms.. - = , - - w..-me.enn.,,.
a.s.m - , - -.c,n,= , -imr---,.mr s L.ma autP .adanha.hdascha md ggy'$*.< ,, !.' ; ;. G. ' p :. _ , gut.y.; ; . . 3, us.. . ;: s,g ; =. gm TMtw tred5MeMRetfRWilsrWEevar.1mW1F bp5857 6 ."RMRlMMIER$$MDff41td
~
pgtel '
= .
_ X f.slte ggtt. 6 2dl.%a.W'aMi \ I g CP 3.3.E.DS--I EldB!IY ._$ m n..__ m_
, y .wmw.er@.Mffatte t -
{ 90!gM3ff$tte Cl#$5 (continued) CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3153 1/2989
. _ _ _ _.. _ __.__ _ ~._ . _ _ _ _ . _ . _ . _ _ _ _ . . _._.__._ _ - _ _ . _ _ . . _ _
LOP DG Start Instrumentation B 3.3.5 BASES l l i I o-3.3 131 P 3.3 ED5 ! l l Thr;; unirv;1t;; r;l;y; with in'.cx ti e chere;teri; tic; er; previid cr. ;xh 410^ 01=; it in:trunr. bu; fer itatin; ;
;;;t;ixd i;;;id v;1t;;; saditien er ; 1;;; cf bu; volt;;;.
The r:1;y; or; edixd in ; two cut of thru 1;;i; t; ,u.cret; An LO" ;ign;1 if th; volt;;; i; below 75* for ; ;hert ti;r.;
^^* '--
cr 9' '= " :.qqofittygg eggg16ays"]$3b05?1 flat?DrOWidEinputito CP 3.3-011 me LOP start actuation logiqjis descr1 , tion 8.3 (Ref. 1). IKgenetal? sggafnll ]tglgjpgggjptg[dtajgfeedia_Mittelegipand acgatie[etagasagaheircresencligittainsEDgLnetworret logictamOggtL11omtelanc~astsateltheloffsgesgree ! treaker,gamepaMst_artisfgnalslasidescribed!1Ethe;FSAR; Trio Setooints and Allowable Values The Trip Setpoints andI43$6ciated31meldelaysjused in the relays are based-on Q!gl$1stettaititjh the analytical limit.s presented in FSAR, Chapter 15 (Ref. 2). The selection of these Trip Setpoints is such that adequate protection is provided when all sensor and processing time delays are taken into account. The actual nominal Trip Setpoint entered into the relays is G$ttirggggijaDamla,J ner ;;;y -tig ore conservative than Inat imc.;.;d 5.7 t6 4 (continued) CPSESMarkup ofNUREG-1431 Eases -ITS3.3 - B 3.3-153a 1/29M9 _a
__m .. _ _ - . _m _. . _ _ _ _ _ _ - _ . . _ . _ _ _ . _ . . _ . _ _ _ . _ _ _ _ _ _ E LOP DG Start Instrumentation B 3.3.5 BASES C Allowable Value. If the measured setpoint does not exceed the Allowable Value, the relay is considered OPERABLE. ; Setpoints a' djusted in' accordance with the A110wab1e' Value ensure that the consequences of accidents wfil be acceptable, providej4ngtheunitisoperatedfromwithintheLCOsatthe , onset of the accident end that the equipment functions as designed.
~
' Allowable Values ad!;r Trip Rtgint; are specified for.each .-
Function in N m 211eged"gM i IgleM. Lei =1 Trip S:tp; int:; er; eln ;g;ifi;d in the unit ;F;ific ntp; int ;;lcul; ties. The nominal setpoints are selected to ensure that.the. setpoint measured by the surveillance procedure does not exceed the Allowable Value if the relay is performing as required. .If the measured setpoint does not exceed the Allowable Value, the relay is considered OPERABLE. Operation with a Trip Setpoint less conservative than the nominal
~ Trip'Setpoint, but within the Allowable Value, is acceptable provided that operation and testing is consistent with the l assumptions of the unit specific setpoint calculation. Each :
Allowable VD'r ad/: '-? tu,; int specW; .;r; CP 3.3 009
;;;rv;tiv; trer. the =;13ti=1 n;;;n ;;;:r :d i;; tr.
C;tra;icat er.d sciint only. :: i. s.--i r te - 7G= " accoumLtht]fetymstrument uncertainties appropriate to the trip function. Inese uncertainties are defined in the " Unit Sg;ific , RTS/SSIM Rtpint ";tt.ed;1;;;y Study" (%f. S). s#PMBt l cggelatBS. APPLICABLE The LOP DG start instrumentation is required for the ; SAFETY ANALYSES . Engineered Safety Features (ESF) Systems to function in any ; accident with a loss of offsite powe O s n .V. m i 6 Its design basis is that of the ESF Actuation System (ESFAS). Accident analyses er &
- W W of the DG based on the loss of offsite oowe l CP 3.3 ED5 l
_ine acwai vu start has historically been associated with the ESFAS actuation. The DG loading has been included in the delay time associated with each safety system component
- requiring DG supplied power following a loss of offsite power.
.The analyses assume a non mechanistic DG loading, which does not explicitly -
(continued)
. CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-154 1/29/99 a <
. . _ _ . _ _ _ _ - . _ - . . 2 -
LOP DG Start Instrumentation B 3.3.5 BASES pc. ', cr :. 'r; 2ha. a. e, ' 00, ;^ tc;;w '.-ipw . ';. 't.1 "f' 2. bus-atewmmw wm. trier =.=aemimuty 1 ofg)heJMllifg35'EggNi$RajLoggstj!$331Undervol1Lapq o.3,3 13o
- fMl!!*1oG3P.3hoAmbleeldteEstgasmuggigtsjutee3eabg
- jglog6NWehtread$t1RiWPIWfter#8MsitEMtege cp.3.3.ED5 sagtce . - w the
#NtgithKCN _ 27 ' -
=
signs 13plligll$MscQ!dg#ldeWoltage!functjenslate te s *81 e O F M a pe!1l G !R ACTIONS In the event a channel's Trip Setpoint is found nonconservative with respect to the Allowable Value, or the channel is found inoperable then the function that channel provides must be declared inoperable and the LCO Condition entered for the particular protection function affected. , Because the required channels are specified on a per bus basis, the Condition may be entered separately for each bus as j appropriate. A Note has been added in the ACTIONS to clarify the application of Completion Time rules. The Conditions of this Specification F may be entered independently for each Function listed in the LCO. The Completion Time (s) of the inoperable channel (s) of a Function will be_ tracked separately for each Function starting from the time the Condition was entered for that Function.
- - _ _. _ m m ._.,
i
.,__-_.._m_
i' rM= c-?";h=f&fM"W"t'_~'~T"" ";"Z,,,
.. . . - .. ._,m. m i
,1 . , %__a_ _m,m_, ,_. .,. ,
-~ - ~._. m
-< .. .m -
#._. .m m,_ ._
m 1. # ..._. ~ &
- m ,
m
._.... m o 99gPtft_lRlRi.M_lBLE._!PjtfCZML;XCE.MZF.;M;;37;
_ m ,m., j e.~._ u yy n m a. m =ws y m - - - A,1 i Condition A applies todine?ONNdtt tG) LOP DG start o.3.3 131
- Functioif@with on[ex :M= : :: ef v;lte;; ad/;r: CP.3.3.ED5
;r:d;ivolte;;) channel per bus inoperaDie.
t (continued)
- CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-156 1/29M9
LOP DG Start Instrumentation B 3.3.5 BASES If one channel is inoperable. Required Action A.1 requires that channel to be placed in trip within 6 hours. With a channel in trip, the LOP DG start instrumentation channels are confiaured to provide a one out of tt,7;c m logic to iriti-teDtrinktheincomingoffsitepowe I i I l d (continued) CPSESMarkup ofNUREG-1431 Baes -ITS3.3 B 3.3-156a 1/29/99
I ADDITIONAL INFORMATION COVER SHEET
- ADDITIONAL INFORMATION NO: CP 3.3-ED6 (new) APPLICABILITY: CP o
l .. REQUEST: Based on feedback received from the NRC reviewer, the following ITS and
' Bases pages for LCO 3.3.6 have been revised as noted on the attached pages. ,
t ATTACHED PAGES: ! Attachment 9,' CTS 3/4.3 - ITS 3.3 ! l Enci SA 3.3 1 I- EnciSb . B 3.3-163,164,165,166,167 and 168 ! 1 l l 1 1 l l 1 l ! I I l L p. l l I-l l' i.
i Containment;3g$[}gt@Q Purg eri RP. u:t Isolation Instrumentation enPS@ ;
; 3.3.6 l l
i Table 3.3.61 (page 1 of 1) ContainmentiVent@etglj Purge-and-E*heest Isolation Instrumentation gypgj N FUNCTION REQUIRED CHANNELS N PIQUIREMENTS TRIP SETPOINT yygg
~
- 1. Manual 122Z3;Tijet HeMinitaleSE98913;C'ESFM3nstrumsptasjeti; Initiation ni_: --
- - 1Efpr,;altigittatica; functions . 3.3 77 u_- .._.e Q 3.3-79
, e n,
- .. .... , , , eg,) g
- 2. Automatic 1K27;3;"4 2 trains SR 3.3.6.2 NA Actuation SR 3.3.6.3 Logic and SR 3.3.6.5 ,
Actuation I Relays
- 3. Containment Radiation 1
- a. Gaseous 1Tl2;;324; lj SR 3.3.6.1 ; [3 x b; d gr; rd' a g.p3 y 1 (b);(c) SR 3.3.6.4 &) (a)
SR 3.3.6.7 1 3.3 79 0 3.3 79 i ! be fi-} L", 3.3.5.1 ; [3 x b;dir;;rd'
";dic;';t 0" 3.3.5.? 3.3 MM C" 3.3.0.' Q.3.3 79 i
1
..t._,22._~_
en, g ,9.,.1
... . r--,
L l - .- . . J.1 3.3 MM , 5" 3.3.5.' Q.3.3 79 I J W ,,,, ,,.<__,___.._2, ti-} , ....... r-.,...., Red +et4en L" 3.3.0.? 3.3 M79 f 0" 3.3.5.' Q.3.3 79 1
- 4. Containment Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 3.a. for all initiatio Isolation - functions and requirements. I CP 3.3 ED6 l Phase A
._.--......--.-..__...----,.-......--..-----m.-.. . - - - - * - . - .
4 a 1: CPSESMarkup ofNUREG-1431- ITS3.3 3.3-61 1/29/99
Containment Pur;; erd Exhn;t MMjgg Isolation Instrumentation i B 3.3.6 8 3.3 INSTRUMENTATION B 3.3.6 Containment Pers; ;nd Exh=;t gegLlagg Isolation Instrumentation BASES J BACKGROUND. Containment pr;; eri cxh=;t ygnt9Bjg . isolation instrumentation closes the containment isolation valves in the M4M CopJie Igeng PurgeHARggIMWptGMContaffinegtiW Refjef Systems ;-4 th; Shutds . Purs; Sy;tc;;;. This action isolates the containment atmosphere from the environment to minimize releases'of radioactivity in the event of an accident. I The"iniPur;;Cogtalpeggt23ssureA11efSystemmaybeinuse during reactor operation and the Shutdown Contajnsent Purge System will be in use with the reactor shutdown.3The Hydrogen 1%;Syggjfs141sgiplementaryisystesiforjthe CP 3.3 ED ele @rjC1 M ner lS W!!!jSic E atediforihydrogeg d1Attonitoms amM1peptisonowing7a30CM Fot;.ModesQ CP-3.3 ED6 tl(1lG$@2WPE _ 1i lkaidGM50:si. UnAvi)2Wyr - alvd53tejJc!ggil31cgEy thDpwynorLohM'= i i LMLupaltdient2Mit0M2961efF@lyesi j Containment pr;; ;rd exh=;t Vent 11atigy isolation initiates on ag automatic QCganual safety injection (SI) signal through the Containment Isolation-Phase A Function, or by manual actuation e of Phase A Isolationggggggggjia 7Agg11gnlof3cntaignent Sptey. The Bases for LCO 3.3.2. " Engineered Safety Feature Actuation System (ESFAS) Instrumentation," discuss these modes of . 1 initiation. FourQng MRhaggggradiation monitor 4ng chsal; ere ij( also provided as input to the containment pr;; ;rd exh=;t yggiltigg isolation. The f;;r che x1; g ntty; measures 1 containment radiation at twe 6H6 locations. ThOlMitdlrsamples tgE6DonMionMfEgh_7,tadiatjen 19R131 m lat1E-hux10=
;hennel i; ; catein a t ;rc; - : e niter. end th; other thr;;
n nur; r;di;ti = in ; : z?l; ;f th; cent;innr.t pr;; cxh= ;t. The thr;; pis; exh= ;t r;di;tien it a ter; ;r; cf thr a different tga;. ;; n;;;. p rticulet;. ;r.d i; dix aniter;. All f;;r d; tater; will ra pe d t; = ;t ;;=t; th;t rel;; x r;di; tion i t; cent;innat. lba rs -;=1yx; h;n not b;a ;;nicted te d,. ~n;tr;t; th;t ;11 credibic sat; will be itat;d by er; th= en eniter. Th; refer;. for th; pr p x; cf thi; LOO th;
.f;;r ch e ni; ;r; not c a ;i i r;d reird =t. In;t;;d. th;y ;r; (continued)
B 3.3-163 1/29/99 CPSESMarkup ofNUREG-1431 Bases -ITS3.3
' Containment Purg ad Ex'act kg)qqg Isolation Instrumentation B 3.3.6 BASES I
tr;;t;d =_fa r a; =t ;f a.; Pureti a ;. Since the ggggg pgg shn;t monitors constitute ( a sampling system, various 1 components such as sample line valves. - ,,1; lira hata:;. gl sample pumps, xd filter rutus are required to support monitor OPERABILITY. E;;h of th; ;;rge BgggggggWtslgeRg@e9BD~@r067fand Cegajm;Msystems -hes eagl Gag inner and 1 outer containment isolation valves 4e-4ts oplgjejg =pply ad ,
)
sh=';t ict: Mggiggt3ejgttatjerffDe[pathq. A high i radiation signal' fra any a.; cf th; f;;r chsnel; initiates containment purge Vagt13Rieg isolation -which closes both inner and outer containment isolation valves in the "ini Purg; Sy-tu 1 erd the Shut h . Conh1geant PurgeliHydrogen_ Purge land Cgetaifeent;ftssfig1]Mief Systems. These systems are described in the Bases for LC0 3.6.3, " Containment Isolation Valves." . APPLICABLE The safety analyses for LOCA assume that the containment SAFETY-ANALYSES remains. intact with penetrations unnecessary for core cooling isolated early in the event. .;ithin ;pprexi=tcly 50 :;nend:;. ; Th; ini;ti;n ;f th; pag; v;1;c h;;; not bcn =;lynd
;;;ech=i:;tially in th; i:;; ni;;leti;n:;, ;1the;;h it; r;pid j 2__,_a__ ,_ ___._2 m_ __m.u m _-___a _.t_.._,.
u sw e u w s we s ae u s erw ww . pssw wwv a wu u s ws , w ps yb u s .ss bns suu d w isc1; tion redictica reaiters cct as b;c h p to the SI sign 1 to en ar; ;10-ing of th; pa s; sd s h s -t Gl; G. Th;y or; 0100 th; p-i cry ==- for at utially i=1;tir; cent;innat in th; neat ;f ; fal hadling sciht iring :;huth ;. CJ!G91ttmeg 61deBNt1 Tith 1tn57setztIdsief P3smontainment isolation in turn
, ensures meeting the containment leakage rate assumptions of the safety analyses, and ensures that the calculated accidental offsite radiological doses are below 10 CFR 100 (Ref.1) limits.
p m-2--- u - - sm.m ma.r.m. [ f89tttEND M ' wa m.mH MMfOl5Medj%
- tajg2estjgtemagginiatutoM2ge13and11ggaccidents The containment pur g =d sh=;t _ attogisolation instrumentation satisfies Criterio 433 of-th MC I;14ey St t;nn;.EEF1591M19MRM111! g t
(continued)
' CPSESMarkup ofNUREG-1431 Bases -ITS3.3 .B 3.3164 12989
1 Containment ."argc ad Rhast ][eJLtj]ai;3g Isolation Instrumentation B 3.3.6 BASES LCO 'The LC0 requirements ensure that the instrumentation necessary to initiate Containment ."urg; and Rheast Ditt9Mieg Isolation, listed in Table 3.3.6-1, is OPERABLE.
- 1. Manual Initiation C.gggjgpK50g$1)gigliitolat1Nr"1slee!nsal}yljnitjatgd when3tht18pMf1SvtsolationitannieE9tithezcogejnennt spranspagtciamilja jydinitiancinetatito;thelBasey forlLCXJD2WlaiEM2!nMatMy;Ennetjon"3;a111and 2imespantM1TZarappHeab111tyEtequirecchannelsrand surve111.antemustfreme,n_t_s]
The LOO Tcquires two chancis 0"E"J."LC. TFa ;Fr;ter c= initi;tc 0 nt;irant "urg; !;;10 tion ;t =y tin by u;ing citkr of tw; .;it;tes in the centrol ree;;; = tascrik. Citk r ; witch ;;tuatc; both trains. Thi; ection will = u;; oct=ti= cf all cag,r. cat; in th; == =arr a my of the at;= tic ect= tion ;i;=l:. The LOO for "==1 Initiction =sures tk gegr e.;.eunt Of recurd acy i: = inteired in the E ngel Octatica circuitry t ca;ure tk egr;ter ks =n=1 initi;tica =inbility. Cech ch = =1 cen:ist: Of en; insh butten erd th; - intcc;;nanting wiring to the Oct= tion logic =bist.
- 2. Automatic Actuation Loaic and Actuation Relays The LCO requires two trains of Automatic Actuation Logic and Actuation Relays OPERABLE to ensure that no single random failure can prevent automatic actuation.
Automatic Actuation Logic and Actuation Relays consist of the same features and operate in the same manner as described for ESFAS Function 1.b. SI. and ESFAS CP 3.3 ED6 Function 3. 2) t,vm.ainment Phase A Isolation. Ine applicable and specified conditions for the containment pege fggjlbtlorj isolation portion of these Functions are different and less restrictive than those for t their Phase A isolation and SI roles. If one or more of
- the SI or Phase A isolation Functions becomes inoperable in l
(continued) CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3165 1n9199
E i 1 Containment ."ur;; ;nd Oi;;;t ygg11aMcM Isolation Instrumentation B 3.3.6 l BASES i such a manner that only the Containment Ptege Yentilatlog Isolation Function is affected, the Conditions applicable to their SI and Phase A isolation Functions need not be
- entered. The less restrictive Actions specified for 3 l inoperability of the Containment Ptege McAtflatf.cd- l Isolation Functions specify sufficient compensatory measures for this case.
Containment Radiation l 3.. The LC0 specifies fete one] required radiationimonitorjng channels of redi; tion r.enitor; to ensure that the radiation
'* monitoring instrumentation necessary to initiate i Containment Ptege Ventjlation Isolation remains OPERABLE.
i For sampling systems, channel OPERABILITY involves more than OPERABILITY of the channel electronics. OPERABILITY may also require correct valve lineups, ag sample pump operation. ;nd filter r;ter ;;;retion, as well as g detector OPERABil TIyC if th;;c supperta; ;;;turc; ;rc } - CP 3.3-E06 f;;;;ryfertripteoccurundcrthecondition; e
;;;md by the ;efcty ;n;1y;;;. These!tupportjpg l l
(c) tot 3EaNtIntegspaglfoGBonta1_rategtita!!!atlogitrj tolg@MMt_jpng@%yWSaf Q-3.3 73 L = _wE-i-mun amSD181EsMG18 Ml!$131!!89]kitj r1MBBMhWBHMGBK998tleJRtfELtegggggelatlog O:> K.D y L 4. Containment Isolation-Phase A Refer to LCO 3.3.2 Function 3.a.. for all initiating Functions and requirements.13tleDpefagglinitiatt Co.]LtggggtlWgtiggtggill,glatfg28111gfitjge2py;0sj ng eitMBIMREWRElmLMikOBjeff2lt0EDRSELWitMi inBassaREmangsamt.tw3ntstCatutepptntraingy IllHERapatIBENRs9sctpet1BTaf241BoentnRttt3nIthe sag 3gggggggggggggggeERD!253NtiMlB1991E ThjMRygdfeuetsIAggagsp,%hjggqD1_ementits r tesagtglegantgittationlefettertsugitggoperlamount oL7J88ElRW48JR1!$p1r!Blilo3N3an!!anctuation effJgitty2R6M'stfielepJe atotGltaEJqnuallinjtj_atforj cap]ibility] (continued) B 3.3-166 1/29/99 CPSESMarkup ofNUREG-1431 Bases -ITS 3.3
I l
- j. J l . . -
Containment Purg ud Ed.s;t MgJtJatigg Isolation Instrumentation B 3.3.6 BASES 1(continued) I. j
-APPLICABILITY The Manual Initiation, Automatic Actuation Logic and Actuation
- Relays, Containment Isolation-Phase A, and Containment
. Radiation Functions are required OPERABLE in MODES 1, 2. 3, !
l and 4,' and m i uring CORF , i- . ALTERATIONS or movement of irradiat 1 assemblies within L ' containment. . Under these conditions, the potential exists O for an accident that could release fission product radioactivity into containment. Therefore.-the containment pur ,; ad ahn;t
' yggi}sgjeg isolation instrumentation must be OPERABLE in these ,
MODES.- i l While in MODES 5 and 6 without fuel handling in progress, the containment purg ad ;2.=;t ventilation isolation ;
- instrumentation need not be OPERABLE since the potential for radioactive releases is minimized and operator action is sufficient to ensure post accident offsite doses are maintained ,
f within the limits of Reference 1. j Th0J_AppMRDD1MJRIgntairimag2ggM14jonMaolgjig,og i thplESFXJilllglgggggggtionE Phqq3MMctfgnJfDpecfi jed inct.tXLEarsmaalammamurmeses2feetcRinnfaurMiscussion Of 8 8le~ M M
.m ACTIONS The most common cause of channel inoperability is outright.
failure or drift of the bistable or process module sufficient to iS exceed the tolerance allowed by unit specific calibration l < procedures. Typically, the drift is found to be small and results in a delay of actuation rather than a total loss of function. This determination is generally made during the performance of a COT,_when the process instrumentation is set up for adjustment to bring it within specification. If tre Trip C;tp; int i; la; ca;;r;;tiv; tha the t:1;rsa :p;;ified by the b
;;1ibr;tica prs;ir;. th; chsr.;1 =;t b; i;l; red inep;r:bi;
~ i;ndi;t:1y ad th; apprepri;t; Caditi= at; red.
p _ p A Note has been added to the ACTIONS to clarify the L application of Completion-Time rules. .The Conditions of this Specification may be entered independently for each Function listed in Table 3,3.61. The Completion Time (s) of the
;. inoperable channel (s)/ train (s) of a Function will be tracked F
(continued) CPSESMarkap ofNUREG-1431 Bases -ITS3.3, B 3.3167 - 1u9/99 l
. __ .. _ ~ _ . ._ ._. _ _ _ . _ . . . _ _ . . _
l . Containment Isig; xd Sh=;t Veig11at10ll Isolation Instrumentation B 3.3.6 l 5 L BASES (continued) t l separately for each Function starting from the time the Condition was entered for that Function. U I Condition A applies to the f ilur; cf ex ;;nt: inn..; purg; isoleti= radiation monitor channel tejpiseggMLegceeggit!! l segjfM. Since the fete containment radiation monitors measuret tggggggupgut;Leospt!ar,e3nlEprjpggesler)
^
actuat" '3 different ;;rseter;. f ilur; cf : :ing1;
^
--__% ire.itett$g 00ts1Al%sl$peMfjeg #3*3#
6%gits3MIStsgeR0ttenceCDf =y r;; ult i- len of dx. 27 ] um ramation monitor 1ng tunctior, for ;;rtain n;nt;. 1 Consequently, the feHed channel must be restored to OPERABLE status. The 4 hours allowed to restore the affected channel is justified by the low likelihood of events occurring during this interval, and ruegnition th:t ex or nr; cf th; r;xining ch;xci: will r;; pend t; x;t scats. M i Condition B applies to all Containment Pur;; =d Sh:u;t Vgg;11gg Isolation NLtoetticMetuatQu',L_0giqL4edTActifattori rgyg Tuxtiengand addresses the train orientation of the Solid State Protection System (SSPS) and the master and slave relays s for thjg th; x functions. It si;; ;ddresses the failur; cf
=1tip1; r;diati= enit;rias chsx1:, or th inbility t; rc:ter; ; singic failed ch=;;l t; OPE"J.PLC ;tatus in th; tia;;
olic,.;;d fer "; quired Action A.I. Colidit10n?B3R$OlppUds3pltJ)$ GalatMMdLtt!gg3!!Nignmetfortatid m!!ple13RE8WEERI8tMr.sware'3mta!!n 0 3.3 73 If a train is inoperable, witipi; chenal er; inoperabier or the Required Action and associated Completion Time of Condition A are not met, operation may continue as long as the Required Action for the applicable Conditions of LCO 3.6.3 is met for each valve made inoperable by failure of isolation instrumentation. G!telEC99Ligd203811dlGifi$1149[gajg!!LtJpNiisUte Mllefftalfe! a c1D*d3EBil1IARRulggggItamto.ibmppeedEcW).laigMt!C1he a ggitout391fJ$ititignjtb[,fj)MI,fl$Mt8tibhMqui@er!tsIjnLPittJJof thel 00Clu A Note is added stating that Condition B is only applicable in H00E 1, 2, 3 or 4. (continued) CPSES Markup ofNUREG-1431 Bases '-ITS 3.3 B 3.3-168 1/2989
l 1 1- , i l ADDITIONAL INFORMATION COVER SHEET
- ADDITIONAL INFORMATION NO: ' CP 3.3-ED7 (new) - APPLICABILITY: CP i
REQUEST: Based on feedback received from the NRC reviewer, the following ITS and Bases pages for LCO 3.3.7 have been revised as noted on the attached pages. ATTACHED PAGES:
' Attachment 9, CTS 3/4.3 - ITS 3.3 Enci5A 3.3-67 l-Enci 5B B 3.3-177 l-i l
CREFS Actuation Instrumentation 3.3.7 T 41e 3.3.7 1 (page 1 of 1) CP1FS Actuation Instrumentation APlNK/SLl! WEES M TRIP W' S19W5ll REQUIRED SURVEILLANCE 51 SETPOINT FUNCTION EXBRERq CHANELS REQUIREENTS
- 1. Manual Initiation 122.53C4ES2 2 trains SR 3.3.7.6 NA and%3a)
- 2. Automatic Actuation Logic and IT2.7;T4Z5; 2 trains SR 3.3;7.2 NA Actuation Relays and_6;7Ja) 5" 2.2.' 3.3 78
["',jj'j Q 3.3 78 NA
- 3. Control Room Radiation
- . = tral ",= nus~.x fe} [",g.g.'g ; ::: e./"
f3~3a784 L',
! T..,';
bra. Control Room Air North 1;;223E4L5; 2 SR 3.3.7.1 ; :: C/hr Intakes and.6C(a) SR 3.3.7.2 114 x 104 73.3;78::1 SR 3.3.7.7 pC1/ml bHContteilltoceAirsSoutl1 1E232425; 2 SR"l3';3,7;3 1;4X104 r d Mtates a m tal SRHL37.2 pC.1/s1 03:3?7831 SR.D;%1;1
- 4. Safetyinjection Refer to LCO 3.3.2. *ESFAS Instrumentation." Function 1. for D initiation functions and requirements. g-3.3.ED7 l 2
9 13 OctaastuoNeer4fof1RtediatedARDssemblies] g3,33yygj CPSESMarkup ofNUREG-1431 - ITS 3.3 3.3-67 129/99
- . - . - - -. - . - ,..- .. - - - - - _ . ~ - . . - - . _ . -
CREFS Actuation Instrumentation B 3.3.7 BASES 1
,L_ n_-.J-_J &_AJ__ ,__ ft__JJAJ_ A J_ __JJ,J J L., . H 1_ AL.L gatw aw3w s s ww rm b s wv a a vs wws sw a b e wv a r) ad susww I 4 IUw wJ u syv bb b u zu b requi.;; pi;;ing er C"""S treir, ir, th; teni; A; pri.,t;; tion sede inst;;d cf th; [redi;tien p.etection] -d; cf eper;tica if th;
_.___u_ i____,__- . i_.2_ ___ _____u__ __2_ 2. 2_-____L,_ ww kwsugu b 5 b be us ud i Ut bw kwnsb gu up yi wbbb bgvie upswwh ad a u wwyba uw a b . Thi;.;r;;r;; __2_ _, _____u__ th; C"_C",S tr;in i; pieced in th; ;;t ;wr.,;ry;tiv; _ . u .._ .. mL. nnen.n,i ,w _, mL. _____,. _; suswwb ve wyb4 U b Iwe a absubsvs bw barb vs bsw uw e s.4 s I we besb uddwbsubbw _ _L . . L a _ ., A__L_.-_- K ,L2 ,_
- Ub b uw b : vi a s a u d b a assuews u bu b : vi s .
6MMNRWWERGBIR$Gtt~2slippWMaeEth>1sttected aaE4aansammsensseussanDisacatumsummmeera 4 Mm2abM31GMCW3M21mRa0Fr005 CP-3.3-009 se3EmManMmIRussuR1IIRIEmeldemPanenNumthMtirths'ernt 2 E MUl[.MIM MRLeietR511!!DalWN8Edu.!anitgedjqqpt!gg B.1.1. B.1.2. and B.2 Condition B applies to the failure of two CREFS actuation trains, two radiation monitor channels, or two manual channels. The first Required Action is to place one CREFS train in the emergency M W alMigtZrediationpretectien}nodeofoperation immediately. This accomplishes the actuation instrumentation Function that may have been lost and places the unit in a conservative mode of_ operation. The applicable Conditions and Required Actions of LCO 3.7.10 must also be entered for ogi the CREFS train made inoperable by the-inoperable actuation
' instrumentation. This ensures appropriate limits are placed upon train inoperability as' discussed in the Bases for LCO 3.7.10.]
' Alternatively,
. . . , .; ,' n.
. ., . a. . c , . ,. g . 6 ~ : . . o. 4 m... , ,a ,.. ,
CP 3.3 ED7 1 __2_ .L. , . _ u__ ,_ __ ,____2 r,wbshb m__u.v_,_.,a - . v. u. . .b ._. __
. . ,, u ._b ., .bu_~ _ w.enere.
_ m. . w. m b u w. s . . , ,n.. .w. - w cv n in th; pr;;;nce e' ; ;ingl; 'eilur;.
,L_ n__.2__2 ._2,__ ,__ , _ _ 2, a __ o ,_ __;m_;L.. . _i_ .L.,
5 yrs aw3wsaww rw w Iwv y a vs b wisw s bsvss w a .y_ uurww # u aww vg u svw bs bs su b ___..a-__ _1-_2__. ___ enrre A_.J J AL. A_m2. _-- ___m _AJ _ __J-i u w3w 4 s b .a y Iu b 5gv3 wits wIws ear be u 5 us asa bu N bvn4b ywd yi w bW h baviu errvus instesd of the [rodistion protcetion] . odc of operstion if the
...i___u. i____ ,__ m. . .a _ ___ ___m__u __ __2_ a. 2_____.L,_
uw wwsssw n, 3 h bl uI s ep 5 b l kw wwn3b yud yi w b5% b I wt I UUrwwh ad 3 3 Fvybs uw 5 b .
,Le_ _ _ _ . . _ _ _
AL_ f*nere m_.2 a_ _1___a _ AL_ ___m _-____...u.._ p si a p bu sdus bd b s ub vvw w ba u p a s ud ypubbw seu birb survd b hwi 3 =pb a TubIvs __;_ _,_____ma__ __1 . u .._ A. A. L . nnen an e r Tw _, AL_ -____J A_; , suswwb wa wybe u b u vi u abaub: yb kw b is vihum abaaa ws bsub uddwhaubbw
- a..-se__ n- - s 2, w_ .u.
wb buu b . v. , 2.. . ._.L
- b. _b..- .rbub
, CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 . B 3.3-177 . 1/2989
i l l ADDITIONAL INFORMATION COVER SHEET l ADDITIONAL INFORMATION NO: CP-3.3-002 - APPLICABILITY: CP l l REQUEST: CN 7-06-LG for CTS Section 3/4.3 indicated that the readout location of remote shutdown instrumentation would be moved to the Bases for ITS 3.3.4. The Bases description of the location was inadvertently omitted from the submittal and is being added now. l REQUEST (supplement): The readout location of remote shutdown instrumentation is also moved to the Bases LCO description. ATTACHED PAGES: Attachment 9, CTS 3/4.3 -ITS 3.3 Enci5B B 3.3-147 l i 5 . _ , . - _. -
l Remote Shutdown System B 3.3.4 l 1 BASES 4,iPressariag?fgsgrq 1 SJtessgrjaarlhi 2 E3eMWMereitgassagitt 1/g l 715teaniangregfitsgi 1/SG 8]Ag1]jgrXEselbgtelfjeR J 2/SG l
;3atelt!gggetas!stelet '
9;condensatgstoragelanMteverz2 ; 101ChargingiPompitoICVCS 33 ! ElCharginglaf!d R E5es)s2 l IH.loEInd_1 cation l APPLICABLE The Remote Shutdown System is required to provide equipment SAFETY ANALYSES at appropriate locations outside the control room with a capability to promptly shut down and maintain the unit in a safe condition in H0DE 3. ; The criteria governing the design and specific system requirements of the Remote Shutdown System are located in 10 CFR 50, Appendix A. GDC 19 (Ref. 1). I The Remote Shutdown System i; ;;nsidered ;n i;pertent centributor t0 th; reductic. ;f unit ri;k to ;;;ident: nd ;; ;;;h it h;; b;;n retaincd in the T;chnical Sp;cifications as indicated in the NRC I'clicy St;t;. ant. sgisfjgJ&rjllMonI4Lo! Lolaso"asRM2Ktf12
.LCO' The Remote Shutdown System LCO provides the OPERABILITY requirements of the instrumentation and controls necessary to
' place and maintain the unit.in H0DE 3 fmm a location __other than the control rum @,fggg!lgu$3ggiglf,ohthese
.( i$8tWSjsisjMMIPggER)~ CP 3.3 002 inn. -.na u vr. . ~ m.... J. ,,,, . . 1, i wu n ed-eeeffs listed in Table 3.3.41 in the accompanying LCO.
(continued) CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3147 1/2989
j ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: CP 3,3-009 APPLICABILITY: CP
~ REQUEST: The BASES changes provided in this item are changes which incorporate current CPSES licensing or design basis information, clarify the STS BASES or provide additional information to more precisely describe the BASES and, as such, cannot be considered changes that could create an unreviewed safety question.-
REQUEST (supplement): Revisions to the changes contained in CP 3.3-009 were discussed with the NRC staff reviewer and are provided as attached. A1TACHED PAGES: _ i Attachment 9, CTS 3/4.3 - ITS 3.3 Enci5B B 3.3-4 Revised for grammatical consistency B 3.3-43 Deleted redundant wording B 3.3 41 Restored inequalities previously deleted B 3.3-62 Restored inequalities previously deleted < l B 3.3-124 Restored inequalities previously deleted B 3.3-125 Restored inequalities previously deleted B 3.3-138 Deleted reference 4 B 3.3-139 Deleted inappropriate reference to " trains" B 3.3-145a Deleted reference 4 B 3.3-162 Restored inequalities previously deleted B 3.3-175 Clarified the separation of Control room air intakes
d
.1 RTS Instrumentation B 3.3.1 BASES BACKGROUND The circuit must be able to withstand both an input failure to
- .(continued) the control system, which may then require the protection ,
i function actuation, and a single failure in the other channels [ lproviding the, protection. function actuation. Again, a single failure will neither cause nor prevent the protection function .
-N actuation. These requirements are described in IEEE 279 1971
- (Ref. 3). The actual. number of channels required for each unit .;
~ parameter is'specified in Reference 1.
p [ Two logi.c channels are required to ensure no single random failure of a logic channel will disable the RTS. The logic channels'are 7 designed such that testing required while the reactor is
- at power may be accomplished without au;ing trip CP-3
, j 000$tt .
TarfmWhith4Tuseipt _ 0 89fA1M*'1p1*Boalom!GtLsap3hs caeMitmaammasugarsmMarsteessweetioniidt11enn~4estl rrcvisier.; to clic,. reaving 1;;ic cher.als fre; nrvice Aring i .=tts;; i ;.7.;;;;73 bC;; Of tri hst ;y';ts'; dai;;d 1: 7;1tbility.
' Trio Setnoints and Allowable Values
' The Trip Setpoints are the nominal values at which the bistables e
are set. ' Any bistable is considered to be properly adjusted when
- the "as left" value is within the band for CHANNEL CALIBRATION accuracy (i.;.. .;. r n k = lit,r;ti m ' e g r;ter ;ettin; n;;r n y).]
f W y .e r ,o m .3. . ; yp .g 1. e M. The Trip Setpoints used in the bistables are based on the . r analytical limits stated in Reference 2.' The selection of these h Trip Setpoints is such that adequate protection is provided when all sensor and processing time delays are taken into account. To ., .% allow for calibration tolerances, instrumentation uncertainties, instrument drift, and severe environment errors for those RTS channels that must function in harsh environments as defined by
- 10 CFR 50.49 (Ref. 53), the Trip R'.,,eint; ad Allowable Values specified in Table 3.3.11 in the accompanying LCO are conservatively adjusted with respect to the analytical limits.
A ats11cd description of the athcd-2 1csy used to calculate the 3 Trip RtF, int;, in;luding tkir explicit Greert;intic, i; n Fe?iid in tk "RTS/SSIAS S:tp; int ";tkilogy Study" (kf. S).
.DDNl j, en mwanwen mnummeeremmaneasvanseeseenanammmmmaece,4hawe-4 n MThe cP 3.3 013 4
B 3.3-4 1/29M9 i[ . CPSESMarkup ofNUREG-1531 Bases -ITS 3.3
RTS Instrument: tion B 3.3.1 BASES gjggigg[ 0;nditica " epplic: to the !atcrudiate ",eng Neutrer. Pl= trip WMa "lC".. PO'E.", is bel;w th; " 5 sctp; int end era er tw; cManels ;r; inegr;bic. "cic; tk " 0 xtp; int, th; NI-S seura range griern tM r.er.itoring and getnti= funti m. The irepcretic N!0 interrediate rs;; chr.rel(s) ust be returred t; ^^E"XLC -t;t;; prior te ini;=ing psc r.b;;; tt " 5 setp; int. ";c N!S inte.adiate reage chancis ust be 0"E"".".LE when tM p;;r icycl i; ab;;c the copebility of the source rasc. P 5. and bcicw the capability ;f the p;;r r=gc " 10. L1 Condition I applies to one inoperable ;ource Range Neutron Flux trip channel when in MODE 2. below the P-6 setpoint-end grfer;;;ing : reector startup. With the unit in this Condition, below " 5. the NIS source range performs the monitoring and protection functions. With one of the two channels inoperable, operations involving positive reactivity additions shall be suspended immediately. , Thislactiog will preclude any power escalation. With only one source range channel 0PERABLE, core protection is severely reduced and any actions that add positive reactivity to the core must be suspended immediately. L1 Condition J applies to two inoperable Source Range Neutron Flux trip channels when in MODE 2, below the P 6 setpoint.
=d gif---M : ----ter -torta, or in MODE 3. 4. or 5 /
with 6Es clescd adJthe GR3 googro] System capable TR 3.3 005 of rod withdrawai mwMuipfgIrptsggrifjllfjiserted. With the unit in this Condition, below P 6, the NIS source range-performs the r,;aitering =d protection functions. With both source range channels inoperable, the RTBs must be opened immediately. With the RTBs open, the core is in a more stable conditior ad th; unit =tus Conditica L. K.1--and. K.2iTMndTK'212 Condition K applies to one inoperable source range channel in H0DE 3, 4, or 5 with the "Es ciend =d the C",0 Rod: Control CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-43 1/29/99
RTS Instrumentation B 3.3.1 BASES n.. ;.x ggermasnluulassmefMBstes;$stpospts OM= Epnchign ItEssepoint 1.1 thu!anEnnectineJrg E4 23 teuerlaansealatrpemigigjh MtREE 29! eeustJangsatto!t!BKZiaW R ENE 3,; teuer RangeAutremfMt'AsteTLuighltosit1KRa.tg 'tKaitime ejseconds (; -y 4J Intermediate:RangeJeutronlElux;iHigh 2; 25t; RTE 5; source'JtangeJeutro[E]ax,THim 2)105: cps 6f over:temperatutep16 seeJote:1; Table:3;3;1-1 U overpowettE16 h112*Et
$3 PgssutizatiR11ss!gyJaoj ([880jpsjg 81tl Emizet;FrassutREingh RMMig M PpssutizerIng$ergejelEl1@ ij EEspan IE Reactot1 Coolant 1E1EHoW ( 90JMposinaEflow 1 11 Not:Used }
122 t!gdergoltagelRCEg $hi40]ts W t!eetithWen!EjGPJ (! E2ER ut sanegeisteeplwajaggyearciistoj b gag 5unin1) C HialDIR.Tuntr21 E @$IJ U jedj M2 IIHMaeJIt193LsEnteEleveliHighEttigh R $4Munit.jM E ! G Tiiunit:21 1931 tow 2Eloid311TTreJiutt RJ SIEpsis Mill! TarttinEEtop3AIMN]MLtd ( R 1Espell J2 SII2ftlLffotCESfjl Y Mi BeactorHtip Mstegggetiot:ks , 3 M3 IntermediaWapgCNetMall21FJjl i ,233;1o*; amps l 1sitt Lottawer2ReactorlTtipC81ockEPR M CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-61 129/99
RTS Instrumentation j B 3.3.1 BASES MQC WRangeJg!trag?StalCTfjg 4R'ef/1((II
- " 2.0 000 W3 PW eE; Range; W l lDMy;fi9 [50fof;RR M RoweCRange_lf!!tstrpn21%%PfM 10 Eof.,ME Igf Turbine 11tstLStage?NW,Pjl3 10Lturbine;powet is geactorlItip3reakerj M 20] ReactotiTrjp3reakeriUgdetyoltagCandJhunt; Trip %
Mechanj'ses 21; AutomaticTrip' Logic NA \ CPSES Markup ofNUREG-1431 Bases - ITS 3.3 B 3.3-62 in9/99
l ESFAS Instrumentation B 3.3.2 i l BASES '(continued) M%2mmzeM ,.l , , ,,l
- M 'E E M T E E EiE @ R W 3 9 9 E B Lt(
Eingschlae Trip'3etpoint I samtWaketten 4 Itan m D ettistin M q AutanttioctustgtogtcRActuatwgelm m 4 contalmentfressureXHighJ h;2fpsig 4 PressurjAerfressure 73.oW f150;psig g stems;Line fressun E LW psig
%;%250: seconds i
%s;51 seconds 1 1
2 contaivuont;.sprey 1 a I!agus1;Initiatig m i b Autenst10ctuatigittogionOctuatMhlays m q containment;PressureXHigh1 [sh2psig 3J cetaisnent3 solation a l'liestgtsoittig GEillnestMinttistiM m (873ptgest19:ActestiocpglanCAggustig3 tim m (53stetuslanBM SeelEunctim3 4 !!!aKPJaplatig GrJgennat1993ntstatig n (2XAstemetjemioG901 Dot **us11stanim n (Augmgalemenacessempl123 $18;23410 5 Sqm621*Jseglpg 4 IlEWRED41tiatie m U N#Ymet1petuatMLomonCActgatiotuptes m C centeinuntTregure3Higu g psig d3 S_tMXine' Pre 3sutt Gli.L% hdr 9 507skecogdg 778 : E8!W3PRf8 CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-124 1n9/99
ESFAS Instrumentation B 3.3.2 BASES Samasp Trie:Islastat
;g a 3.2 0^^
t B5eaubSARKfeggelgementagem ! I MRMIM!IO9eBBitiongagEggigegl Leg ll3eles e 4 ss~jggetteteEMghitnWigra4I ; a r p tunit 3 1 T J M X (unit:2)
< safeltrimmetfog 'seelunctiorO; 6 miliary:fgedseteri
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(sses) 4 M Lused c- salaterLLevelE.LoElow Q25: m3 unit 31
, i]3sL4r;)R;(Unit 1.2) d- s._4fetyllnjectjort seelunctiorCL; i Lo*CoflEawet M I tt3Diul j 9 T d 83LC &UIUR F Ee]!tWate t eus s M H Mlage61 3 8lBlESE;Sli!BhoB!S$n'Idt:30JM$M l 4 AmeeBMerAssttioBMicIagIag!astagmeles M 40~l0* Tsp 60 4
Bg3Rtlgg]DistBEStoraggEa!E(B.igB.
- . B m ir.t m R991XLoliB I EliEBEiiMMtidRK8 4 geBRERbpEas4 E 4 EMBBRWatfMER91Lsufj!7EP31 @l960;psig (continued)
CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-125 1/29/99
_ _ m ._ _ . . . _ . ._ _ _ _ _ . _ _ _ _ _ _.. .- . _ _ ._. _ _ PAM Instrumentation B 3.3.3 BASES u _- .._ u _ re, n _. . _ , 2_ ____22___2 _ r . ._ _ ...__2_t,_ ru b erwsuuh us s s be , wwa n.w y w s ya wws u d s guw s ww u agyv rt y un uuwaw L___..__ iL_ ___t__, ____ __t__ __2 ___.. 2_i _ ___ wwwwwww bu sw wws r bs v s s wwsus susw bwa wurw ut ru sua rs, s u b si us w cen;i'a.ed tt.; prinry ir.dic;tica n-d by tF.; egreter. The DBAs that require AFW are the loss of electric power, steam line break (SLB) e - Ti ' nMja and small break LOCA. The CST is the initial source of water for the AFW System. However, as the CST. is depleted, manual operator action is necessary to replenish the CST or align suction to the AFW pumps from the t.etw;11 statioppgicdGMMets
- 15. 16, 17, 18. Core' Exit'Tennerature CoreMX1titgpgggre31sWType%TCateggyf1]yar1able;fot natralmtmengsamistiane!ainatig/J11nitiation; anagstimaggm1psnT.jemsattegmatariable .
foGatigemunagginettarsalaGtMlamL2tMestfW MM_)flphle'jfod CP 3.3-009 magitoMitgllR3pggMMMYifGeBlagM7aCore Exit Temperature is provided for verification and long ters surveillance of core cooling WefsEI2d6dG3 A ;?;13 tiers v.'; '; rued; Of tE.; ;ini;;; G;;b;T cf V;;;; ;;r; exit traccuswsuples (CET) a;;;ssery f;r ;;narir.;;_-__,---m cer; ___ 2__ rt. _...,..i2__ ;_i__>___. it. __2.__.2 www s a u rg , aasw w w uaww b avii ww bwa rus e u pwse burw a wwww.T.%s .-. r'"'"' _2 er=r. - _ _ _ _ _ _ _ . m. .n _ x _ _x 2 a i2_, _ _ _ _ _ _ _ _ . . _ _ . . .; i__a ws wbad a rwwsddws g bw wv bvJw b asatb3u5 gewy w swwwybug uiyu bu besu mu_ ___.2__ ____ t__m.._ rt. ..._,...ia___ sysw wYuawwbsvuud wwwwuvsb ____.._i ,__ ____ s vu www w berw wiseru a a ny news v srwubuy. 2-____ _es__i_ _ e iL_ ' . .n 2 _ , _--.._22-_- n2__ 2 _ _2 . . n 2 _ _ u swa sus a a # ws seu 5 b a T.e , susw awgssary a u uwws w waswg.bd wu buww a uw s u s decey p;.;;r distributien, Oncer; cff;;ts of cerudersset; runb;;k in tFa P;t 1;;;s, end nenunifer; ini;t tw.u.gr;tur;;. Bee;d en thes; oveluctiens, edcquetc cer; cceling is ___..__2 . .u t i.._ .._,2s r___ r _ u r - - - _ _ _2. . . _ _ _t___ ,_ ___ wu sews ww su u ts a bvvv v u s u ns wwi w wis s h s wissyws u bwi w wa suu ss ew s d yvs _. . ~n- - A .u k 1- crre --- ---J-J L---_, rL. Pr r _ J quwwu usib vs s be a bzuw wk5d yve s wngw a s wgs ws ruz tu vb a . sasw wbu yu a a ___ __2- ._; __22.,,.. i. _ _ __ u ..._2.. 12__ _, _-__ _ 22_, [ un w ws a wa s bsns suwsausag ww yvs sus a b w w u s ww w awyu ws wwu w s u%s e u a
;___.. - - _ _ Ja_i_2L.12__ e___ r_2i r--____A...__ J. ..__2 m.
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dctereinc 4.cthcr
- i. __2_u2_i_ c, 2, to a tcrainetc u__ L___
SI, i'_stillr___ _i___ _n in pregicss, r_ u or bw a w a s s a b u u bb es a es ab s yu es arvws u e kwyyw%s . wwi w a.#\ s b r-- ___m..__ 2. . , _ _ ..__2 ,__ . ._ u _i_ta,2__ta__ __.2 3 v5 wg a s b er bww I a 1 deu b awI a us tw s wvuuyw u U bus s ad usdw eBerw%s
*EME.H (fjlya_t1M CP-3.3-015 F10E datntwinni1EElagentkImetienennemamiranFTeieMuMrtM
@EIBf.0. 0 (continued) i CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-138 1/2939
PAM Instrumentation B 3.3.3 BASES FJ M G M 51BMiti CP-3.3-009 D Two OPERABLE channels &co @ tjg c(iprilenkt@po3EI& . -of Core Exit - Temperaturearerequiredineachquadrant1 CP-3.3 015 0 OfRJECEJ411nXatidlW12BlihtAstMper t W W ee D W W rAptR M LG E M u toc 10 MM3*2EffaLoroflasseabites; aM1 3j OfLttieMCig' Eabog3bCML6ne;ofJthe[CETS 1![EaboteMat;"leastIoneiCETjperitrain;sust be centtallflocated:An: core;Ltc providc d_dl L2__ .2 __A2 , 22_L_2L..L2__ _2 LL. Iurw 5b u bavss vs suwaus u 4 a bs a vns b I vu s va bs N coolent tc rcreturc risc scross rcpresentative regions of the cerc. T'cucr distributier. _.-n_.. . . . . ____as___s _ s_ _ _2_z__ r gj owses w ks y prt i d hvi se s ubs bu sus ww bss aus s u u s s ay b
,pccific nu;bcr Or.d lec; tic ,'; provided for di;;ncsis of loc;l cerc prebices. Trareferc, two r;nde;1y ciccted thccreceuples art. not
_..,,,_2__. m. ___. mu_ i.._iu_---__.._,_ ___ dus5 s h s hssb hv sveww k bush kww hu ms issvvvuy s k e yLi chenral require.nnt irs eny quadrant. 7a two thcrseceupics in cach chen 41 must ;nt the _;o 2___, ___.2_ .u. ___ ,_ ,___ _; ____ bs su b visv ae IwwwbEM 4 ab u s u%s%sabavusuu a 53u a a wverws a b the ccatcr of the cerc er.d the other accr the cerc peri. etcr. such that the pair of Cerc Exit Teepcreturcs indicate the radiul te,,sycreturc gradicat scress their core quedrent. Ta scts Of tWO therewceuplcs On,ur; ; ';ingl; failur;
..,,, _ m m__t,_ .t. .t a , 2 . . . .. ;_&___2__ it_
wass a vv b %s a duw a w ba N uw s a s by hv ws bha sus a s m bs m _ _ _ _ _ _ _ _ m sm., __m, . _ _ _ _ _ _ . . _ _ m , . - _ . -o.
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- 19. Aux 111ary Feedwater Flow" Rate"Arti&#meGen'e rator 0-3.3-70 Waterard.eeTWddFRame)
AMilierJJdMWetMEMitslajDpWEGalgo_ry31Ntiable 1 totEtemitfatiotRastNetetstettitelpaglejstteligdeguag hCBl5EMIIN43BIIf_83.9plE8EAtedofy21RbliableHojj atEWR100229tishRtBIDICpla]tKjlRf'gg!gSM GenerAtotTWatet EMt!MDHUfitangelug!b5yp61sXatD5fy3118dabjyxot j
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(continued) I l CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-139 129/99
1 I PAM Instrumentation B 3.3.3 BASES l l l l REFERENCES 1. {'Jr.it specific decar.t (c.s., TZ, NRC Resulotery ) Ouid: 1.^7 = letter'.] F_SAR~SeretiertWa~51 l
- 2. Regulatory Guide 1.97 Edete} My,1gM2'illegest!a(3980.
- 3. NUREG 0737, Supplement 1, "THI Action Items."
T EEM+'872'C1E1$7 EMj M q MPEEEiflHT53EE2 Gartef!s[!A!!ty23313]JaNLREGiO3Elechnjcal l SpecitLesttetsrJeggbeG2198M l 1 l l 1
)
i l i l 1 1 1 1 1 1 l CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-14Sa 1/29/99
I LOP DG Start Instrumentation B 3.3.5 BASES l XiECECIJ.LCZEE3?MMiabl@W411 , , , , , _
" " ' " ~ ~
l MESTg2;LOPK Statt!I,nst!MtqqttRm]Irlp;Setpofnt l
/
FHection Trip Setpoint OffsiteJWceEUnderg1tage 5ffi92KV2 referred !h_43olts R6 X kV.31. ternate Si! 004 Jolts 619;kV;Cl as.sJ lELBus1Undervol tage SJ 0_371Vol.ts 6jgf kV"Cl ass;1E; Degraded ; Voltage i",i 054: Volts ; 480lVLClas.s11EiBus Low; Grid,'Undervoltage 5: M7iVolts 480X, Degraded Voltage j ij4391 Volts V CPSESMarkup ofNUREG-1431 Bases -ITS3.3 3.8-162 1/29/99
CREFS Actuation Instrumentation B 3.3.7 i 1 BASES
- 2. Automatic Actuation Loaic and Actuation Relays (continued)
Automatic Actuation Logic and Actuation Relays consist of the same features and operate in the same manner as described for ESFAS Function 1.b., SI, in LCO 3.3.2. The applicable-H0 DES and specified conditions for the CREFS portion of these functions are different er.d 1;;s restrictiv; than CP-3.3-009 those specified for their SI roles. If one or more of the SI functions becomes inoperable in such a manner that only the CREFS function is affected, the Conditions 1 applicable to their SI function need not be entered. The less l restrictive Actions specified for inoperability of the CREFS { Functions specify sufficient compensatory measures for this case. S$, sE.E,d,, niF.lh_.islMsIII,_IIN,.Iistl..e,_ idio $.G7 0 3.3 78
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- 3. Control Room Radiation l
The LC0 specifies t.;; required Cer.tr;l ";;; At ;;;,hcr; I
' ";di; tion ".eaiters ;r.d two required Control Room Air Intake Radiation Monitors pe[51gake to ensure that the radiation ,
l monitoring instrumentation necessary to initiate the CREFS
-remains OPERABLE.
EagEgigg6FF'f=_ =11sPaWretsiifunctierrMan t g"881 l For sampling systems channel OPERABILITY involves more than ' OPERABILITY of channel electronics. OPERABILITY may also require correct valve lineups, sample pump operation-end filter ,,ter oper; tion as well as detector OPERABILITY, if these supporting features are necessary for trip to occur under the conditions assumed by the safety CP 3.3 ED analyses. n . -- . _ - _ , n:___-_=-_=-m,_ v ____ ,m _ _ _ -
-- .* - mu w ~wamm ,
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- 4. . Safety Iniection 1
Refer to LCO 3.3.2, Function 1, for all initiating ; Functions and requirements, i CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3175 1/1989
. . . . . . ~ . .. -. -. .- - - . - _ - . - . .
l l 1 l l l. ADDITIONAL INFORMATION COVER SHEET
- ADDITIONAL INFORMATION NO: CP-3.3-010 APPLICABILITY: CP REQUEST: The Bases have been revised to clarify which functions listed in Section 3.3 Table 3.3.2-1, Functional Units 5 and 8 actually required testing in accordance with the ESF specification and which ones, if failed, justified declaring the function inoperable.
REQUEST (supplement): Revisions have been made to clarify the descriptions provided by l CP 3.3-010. Also a licensee initiated correction is made to l the P-4 description. The MFW isolation (with coincident low Tava)is not credited in the accident analyses. 1 i ATTACHED PAGES:
]
Attachment 9, CTS 3/4.3 - ITS 3.3 Enci5B B 3.3-93 and B 3.3-103 i
ESFAS Instrumentation . B 3.3.2 e i BASES e coincii.at 'Jith Ofety Ini;ction 'T= Leen " nit:'
/--_LJ-.. J%
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";i:; P. .; tion .;ust b; 0"C"#LC in ",00001, 2, ad 3 2,;n ;
s;; airy sii brx% or ; tuck ep;, velv; ;;uld r;;;;M in rapid ipr;- .;ri;; tion of th; st;; lir.;;; unic;; eli "0".'s er; -._..,-s . u. cle';;d a n. ..u.... 2, ,u. ..- u . 2. -- uu ns Lww wwbsyubEwJ. s ai a e I ws tw b i vs s qe g av b a w3w s a Ew kw uw 0"Cl' OLE in ".00CS 4, S, ad S besus; ther; is ir.suffici;nt ' incrgy in th; e;; airy :ii of th; ur,it t; h;v; = ;;;iint. l 5. Turbine Trio and Feedwater Isolation The primary functions of the Turbine Trip and Feedwater Isolation signals are to prevent damage to the turbine due to water in the ' steam lines and to stop the excessive flow of feedwater into the SGs. These Functions are ' necessary to sitigate the effects of a high water level in the SGs, which could result in carryover of water into the steam i lines'and excessive cooldown of the primary system. The SG high water level .is due to excessive feedwater flows. cP.3.3 010 ThoseMiagtigsitMKNselthe3IurbtgiltipIa, gdfeedwater ; 1solatioresionalstare111stedibelowGhogevgrAthe3.Colonly
-- - w4esme**majp1turbineat1plagleeAmtet.
ii _._11!ssipibetoperable2GDtiteaafgegLfunct ions pj!@'$plWidfledwaggggplattohIt INbut?are 9ttft W7c v L J anal _w au - . _ ._ . q N The Function is actuated when the;3gg level in any SG exceeds the high high setpoint and performs the following functions:
. Trips the main turbine; mu
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. Initiates feedwater isolation!2.tM;G.;;3J;;;E;~;71R.; ;
-end
[ . TrMt.he20DLtapt14nd131tiat6srclotute 'ofitgaaig L ffgdJggt3gpTdische_tgye alvFs]3Rd i . Shuts-CJpgsI3the MPJ r;;;l;tingEcDMtql valves and the bypass feedwater r;;uleting con 3@Ivalves. I i L (continued) i CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-93 U2989 [ e l , e -
. . ~ .. . .--. - . .. . . .-.. _ . .
ESFAS Instrumentation B 3.3.2
' BASES Interlocks-Reactor Triof P 4 l
The P 4 interlock is enabled when a reactor trip i breaker (R1B) and its associated bypass breaker is , open. On;; th; " 4 interleck i; :=bicd, =t;ntic SI
'initi;ti a i; bl xk;d ;fter ; 00 n ;;nd tin del;y. ;
71EREEBMlBINt31WJRERREiWBMWMMstro.i 888 EAR 8HMSDNBeGN3EBMEMNEEEtte$f 180BRMefaleDeltistXIERRORutdetWJagnit1Thi s Function allows operators to take manual control of SI ' systems after the initial phase of injection is complete. Once SI is blocked, automatic actuation of SI cannot occur until the RTBs have been manually closed. Thpgg The-functions eRthetiusejthe P 4 interlock are ' 1 Mad below: howeveQtjhe tC0;cn1TptRIDiresA ; lCP3.3010 MBEMggggggil1tjGtME63Diggr %llutJreinot w l f. 3 ___ - m . _ _ . - 2.tu ;.__ .m
. Tripg the main turbine:
Isolate! HFW with coincident low T m:
. Prevent aggnaltg reactuation of SI after a manual reset of SI:
BuillWaRREnEGEmittmaENBland gransferj the steam dump from the load rejection I, controller to the tmM MRg trip controller: and
. Preventi opening of the MFW isolation valves if they were closed on SI or SG Water Level-High High.
Each of the above Functions is interlocked with P 4 to avert or reduce the continued cooldown of the RCS following a reactor trip. An excessive cooldown of the RCS following a reactor trip could cause an insertion of positive reactivity with a subsequent increase in g a r;ted c J5 power. To avoid such a situation, the noted Functions have been interlocked (continued) CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-103 U29/99
l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: CP 3.3-011 APPLICABILITY: CP l REQUEST: The CTG and the ISTS address the undervoltage and degraded voltage channels j for the Loss of Power (LOP) Diesel Generator (DG) start instrumentation but do l l not address any Automatic Actuation Logic and Actuation Relays. The CPSES design included Automatic Actuation Logic and Actuation Relays as part of the LOP DG start instrumentation. ITS 3.3.5 has been revised to incorporate this function and the CTS has been marked up to be consistent with the ITS. REQUEST (supplement): The Bases has been revised to enhance the discussion conceming the basis for the Loss of Power Diesel Generator start Required Actions, the associated completion times and SR 3.3.5.1. ATTACHED PAGES: Attachment 9, CTS 3/4.3 - ITS 3.3, Instrumentation Encl. 5B B 3.3-157, B 3.3-157a, B 3.3-158, B 3.3-158a, B 3.3-158b and B 3.3-159a l l l l r 4 K 4 W
LOP DG Start Instrumentation B 3.3.5 BASES A 1,te is added t; ellow typasing n.irepereble ;henaci for up t; 4 har; f;r nrveilla;; tatin; Of ;ther ch==1;. This elic;wre; i:; =i Jer; byp;nia; the chenrel dx; ret enx en
;ctu;tica ad Jere et icest tw; g.;; other chancis ;re 3 r.eaitering th;t per; ;tcr.
' The specified Completion Ti= end tim ell;=d for byp=-ing cre chmaci ;r; fits reasonable considering the Function remains fully OPERABLE on every bus and the low probability of an event occurring during these intervals.
A~geteM~#penInd$gMJ_lgll1fEthatitMECogdjtioglisinot applicable 303hqquaticIActuatioGogigandMctuatjon CP 3.3 011 RelayMction. Ih1CfunctioKisladdressed by]:enditionE B.1?? B r2.1'7and' B T2 P Condition B applies wher .er; th= cre;boti) loss of voltage-er 7.er; tha era igc;id volteg; channels or, ; sing 1: baithe PRfer 9d10ffsit4[Jg1tAggggMelblislair$ 4e inoperable. Required Action B.1 requires restoring ;11 but one channel to OPERABLE status. The 1 hour Completion Time should' allow ample time to repair most failures and takes into account the low probability of an event requiring an LOP start occurring . during this interval.
. - - . . . . - . , , . CP-3.3-011
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(continued) CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-157 1/29/99 m
LOP DG Start Instrumentation B 3.3.5 BASES 7 MCMMlIM f CP 3.3 011 l
._._.______.._____.._M_..,_ W WA adititjagtgeisikmemsteinel and MalmiaRMeemeRNR8mBWpntBD1HpgrKwA!Etegate:1ng:an 1 i
LRTistera!!a21 MAR 3!altgrintesan C?1?C"2I1NfandT2?2 conditionicIappuesIWheEbothilossionyoltage.Mhannels;onithe a-3.3 131 AlternateErsitmingtsourgbus3minopetable] ! Re!pdred_Miop31M,tgqq1tesItestoti.gp!eIchannehtol0PERABLij status!ZJhE11hohricosAletion1DueIshou.1dlallag. asp],jtjuego repairiggum11mslagttge.s_11stolges Ethclgprobab111ty ofign regenttNiquiringEt.0Pistartloctssrringidoring;thjis igervan l 1 I (continued) I CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B3.3-157a 129M9.
i l t LOP DG Start Instrumentation B 3.3.5 i l BASES. 4 l 4 .dm.sa..,m . .....-.---,C CP 3.3 011 fe .,_3..-m _G
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... .. - . =. - . . - . . .. - . . - . - .. .- - .. - - ._.. - -
LOP DG Start Instrumentation B 3.3.5 BASES
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t.w .j s - . m. c o - . . n:g ; 7.:9 a..JegguissupsBIERER$NEits . _.,__-a.-.-__.., RdlhabM16MMBBISBERRI1Bg31ut109 th1511ntEMEBIEk2MtmilEH21EIUittlEttMtmaERIl151MDUIM 9Titce3BIMMIE183PittRERBhtE6WitR4WRENN21!f183!!3a l@t(
'(continued)
CPSES Markup ofNUREG-1431 Bases a ITS 3.3 B3.3-158a 1D9/99
LOP DG Start Instrumentation B 3.3.5 1 BASES i y qe. f"gggggggym
; .. '. ,,,1 ,
9.. . ) . .
- .- ~ _.
- ' W M iqq !
etern,a nn < ,.:. :o'...teessagsgig mata
' 1 "
gjggg3i.f f.j. . . 1 62- i __ j l tgtje s M tjpg j alm 33Ressaganggesig!nnel ' m m :a s u m anes een1ttan , msI1glg!Leig ! l f3 J l ConditfogIE28pp]1ejs3tjiegIone:gr[moreltrainsl:of1 Automatic wation3ogiciagdl8ctuatfon1Rel.anfunction3re CP 3.3 011 l inoperablea l l RequiredRtioliiDXtp@itesitestoringitheligopet$leittain(s)lto ole!tABLEigatgENDRE]LouKcompletion:Ilmelallge$1tfaelto tenitirlfjtt1 tags *anegggGiuteraccountEtheBojw ntobellit#IAcag elegtirJgulttKjagg5L3tgrEgccurttWJu!1ngithis116tetyalL1 1 1 1 l l l (continued) CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B3.3-158b la989 I'
i LOP DG Start Instrumentation B 3.3.5 BASES i 1
.s _
. . - .. . _. .n sw.m.an -. . ag _
g__ _ d
. . i,. f.. n a
. !iC3731533B3tamecan.mTgtagCHESI.:ZThe 5
LotiDEstattung!!npjg!geeMen3cgfEand 2gLtestic![RelaysJre teMedlFMMleastbeJLDE!EiflMen11gillDEEforigreatet;than ' otleque15 tow tteggentilfLgperfotigeGj!Kthelprevious192 dar21!!alftsg1Eisitesteetiot;toI;enteting;tlDDEifjolessure that:the2ssocjatedidige1IgenetatosisInoonnecessarily;. started bLtheltestingLYSuchlL4!!necessarylstatts30uldibe;adyetseltolthe reliabilityroftQridj_eseligeperator&Rhe; testing:yer.1(ies;that the]ogjcMg0PERMLEffdhlf.Trequency;ofitheitestjngii sfadequate E The22;hourg assures;thttZthete;islsufficient;tieelduring;the s.huthto~petfonttMtestjng;MThe192idaysFjsiba_ sed og L industry 1 operating;expette. nce gconsidering:; instrument;..reliabil ity adoperating.histgrCdata_; I l l l I l l 1 (continued) j i CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B3.3-159a 1/29/99
5 ADDITIONAL INFORMATION COVER SHEET I ADDITIONAL INFORMATION NO: CP-3.3-012 (new) APPLICABILITY: CA, CP, DC, WC REQUEST: ITS 3.3.1 Bases are revised to clarify the relationship between the Reactor l Coolant Flow - Low reactor trip function (Function 10 in ITS Table 3.3.1-1) and l permissives P-7 and P-8. Traveler TSTF-169 correctly combined NUREG-1431 i l Functions'10.a and 10.b into a single Function 10. A single function is . I appropriate to ensure thermal power is reduced below the permissive P-7 setpoint in a time frame consistent with WCAP-10271 and its supplements. However, the Bases changes attached to TSTF-169 did not adequately revise all discussions of this trip function. In addition, as noted in a telecon with NRC staff on' January 12,1999, it is confirmed that the monthly Actuation Logic Test of ITS Table 3.3.1-1 Function 21 l (ITS SR 3.3.1.5) demonstrates how the low flow trip function on low flow in two ' l or more loops and on low flow in one loop is enabled or blocked by the presence or absence of permissives P-7 and P-8, respectively. ATTACHED PAGES: i Attachment 9, CTS 3/4.3 - ITS 3.3 l l Enci 58 B 3.3-20, B 3.3-20a, B 3.3-30, B 3.3-31 and B 3.3-45 1 l l
i RTS Instrumentation l ' B 3.3.1 l
' BASES level channel failure cannot cause the safety valve to lift I before reactor high pressure trip.
In MODE 1, when there is a potential for overfilling the pressurizer, the Pressurizer Water Level-High trip must be OPERABLE. This trip Function is automatically enabled on increasing power by the P 7 interlock. . On ! decreasing power, this trip Function is automatically l blocked below P 7. Below the P 7 setpoint, transients that could raise the pressurizer water level will be slow and the operator will have sufficient time to evaluate unit C conditions and take corrective actions, s l
- 10. Reactor Coolant Flow-Low l G. RC;ctor C001;r.t fl=- LA ' Sir,;le le0LI CP 3.3 009 The Reactor Coolant Flow-Low fSir,gle Leop) trip Function ensures that protection is provided against ]
violating the DNBR limit due to low flow in one or : more RCS loops, while avoiding reactor tri)s due to l normal variations in 1000 flow. ^~m7A CP 3.3 012
't he P 8 serpoint,Q& i:; ;;&rexi;:tch '0* R.., a loss of flow in any RC5 loop will actuate a reactor trip MM. Each RCS loop has three flow detectors to monitor flow. The flow signals are not used for any control system input. ;
i 1
)
0 3.3.d GEN V ;. 'u . 4 . , n mi t e b L a R O . M..J-Q y...r.. o . , c . 4j . y.g.; y . m . . A ~ . 1 h J g. 3 . .; y . ,w $ : 3 iy,,f., . r. , . g.4 ;, g q;gg l RC 6 f M *110 8ct081 nounggesmesmanthersteagangamLttleignidet j WWEREEEEllmGlahmisomettttartM BGBENEBBrt1Ett4E@nt14!SEQDIMl393REflof - (RutrtfEB5tahl.Mla G tig3EREt M E M E Lttrat1M i tGERBW58BEitBtijumagg8BERBlDBEMtL4M
. v.t " :2.4 MNilMDIEIThsEMKolmisilESlSciRfitRI
$99tmitMRW.tggCAU8MEGi-2 yfRidG1catedlf]s2 CPSESMarkupofNUREG-H31 Bases -ITS3.3 B 3.3-20 U29M9
- -- ~- - - . . - . . - - ~ . . . . - , - ~ . . . . - . . . . . - -- -
o RTS Instrumentation B 3.3.1 BASES - MMisill$dSEMllatifiedTovilitll$8helltptl g 0 3.3.d GEN MERIBEIBMacnepBg!Ls!!stE1MManelhel , etenigB8881mM!m!tJtitE18!!atmMMBISttle ateistammig The LC0 requires three Reactor Coolant Flow-Low channels per loop to be OPERABLE in MODE 1 above i Ms l-In MODE I above the P 8 setpoint, a loss of flow ) in one RCS-1000 could result in nNR conditions in the : cor@Ioftthethigher2poweti] eye 1. MODE 1 ! below the F u setpoin(andjaboveltheJPE77setpo a l loss ~ of flow in two or mora i ws is_ required to . actuate a reactor trip Q ica 10.b3 Decause of the - lower power level and the greater margin to tha riadan limit DNBRM_cKt!!ef!7ssei,wiisgallfreactorltrjps l 4 OMificQrragomatjcallTblocigtJ131ncelthetel1!! 18pffic14DMiletIproductortmegetatEons i conditions? ,
- b. 2 xter Cool =t rica-Low (Two Lce;;'
Th; R;;;ter C;;1c.at flew-Low (Tw; Leep;' trip furetion cr.;ur;; th;t pret;--; tion i; provid;d ;;;in;t viel; ting th: 0%CR li;;;it du; to 1;w flow in two er 7.er; RCS leep; d.il; ;;;iding r;ector trip; de; t; rer;;;;l v;ri; tion; in 1;;p flow. CP 3,3 009 t l CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B3.3-20a 1M989
RTS Instrumentation B 3.3.1 i BASES , t OPERABLE because the NIS Source Range is providing l core protection.
- b. Low Power Reactor Trios Block. P 7 The Low Power Reactor Trips Block, P 7 interlock is ,
actuated by input from either the Power Range Neutron l Flux. P 10, or the Turbine Igl;c Dr_stjStage Pressure, P-13 interlock. The LCO requirement for the P 7 interlock ensures that the following Functions are performed . 1 (1) on increasing power, the P 7 interlock i automatically enables reactor trips on the ! following Functions: j
. Pressurizer Pressure-Low:
. Pressurizer Water f.evel-High; t
. Reactor Coolant Flow- ,wo L;;p; l oW1f,} M i,filtwoIorjaore;RCSI] oops):
CP-3.3 012
- RCP; Src kcr Oper. (Two L;;p;);
. Undervoltage RCPs: and
. Underfrequency RCPs.
These reactor trips are only required when operating above the P 7 setpoint (approximately 10t power). The reactor trips provide protection against violating the DNBR limit. Below the P 7 setpoin'c, the RCS is capable of providing sufficient natural circulation without any RCP running. (2) on decreasing power, the P 7 interlock automatically blocks reactor trips on the following Functions:
- Pressurizer Pressure-Low:
- - . Pressurizer Water Level-High; i
l
. Reactor Coolant F1 Two L;;p; E1Qot(si,nJwoiorimoIpLRC_S11 oops) : CP.3.3-012 i
? CPSES Markup ofNUREG-1431 Bases - 1TS 3.3 B 3.3-30 1D9/99 i'
_. ~ . - - _ __. _ _ _ _ . _ . - . . . . _ . ._ _ _ . . . - . _ _ _ . . . 4 _7 RTS Instrumentation' :I
- B 3.3.1 BASES :
* % " "r: d;r ";;iti;n (Tw Leop;).
i
= Undervoltage RCPs: and l
= Underfrequency RCPs.-
.i Tfip Lt,~ int; .M Allowable Values are not ;
applicable to the P 7 interlock because it is a logic 5 Function and thus has no parameter with which to j associate an LSSS. l The P 7 interlock is a logic Function with train and !
.not channel identity. Therefore, the LC0 requires one-
^ i channel per train of Low Power Reactor Trips Block, l P 7 interlock to be OPERABLE in MODE 1. l The low power trips'are blocked below the P 7 setpoint and unblocked above the P 7 setpoint. In MODE 2, 3.
- 4, 5. or 6. this Function does not have to be OPERABLE because the interlock performs its Function when power
. level drops below 10% power, which is in MODE 1.
- c. Power Ranoe Neutron Flux. P 8 I l
The. Power Range Neutron Flux. P 8 interlock is ! actuated at approximately 48t power as determined by : two out of four NIS power range detectors. The l P 8 interlock autm"~11v enaoles the Reactor ! in er .;. . ~ m Coolant
" Flow--Lohy,;1;
.;;iti;n (Singi; Le~5 reactor trips on low .. flow in one or more RCS loops on increasing power. ;
The LC0 requirement for this trip Function ensures that protection is provided against a loss of flow in any RCS loop that could result in DNB conditions in the core when greater than .ppre;;i;;t:1y 48% power. On decreasing power, the reactor trip on low flow in any loop is automatically blocked. The LC0 requires 6hannels of Power o.3.3 44 Range Neutron Flux, P 8 interlock to be OPERABLE in MODE 1.
'In MODE 1. a loss of flow in one RCS loop could result in DNB conditions, so the Power Range Neutron Flux, P 8 interlock must be OPERABLE. In MODE 2, 3, 4, 5, or 6. this Function does not have to be OPERABLE
. CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-31 1/2939
. . - . - . - . . - . - . - .-- . . . . - . - - ~ . . - -. - - - . - . . . ..
RTS Instrumentation - B 3.3.1 ! BASES expricre; in grier;ing the "equired A;thn; ;rd the kn;wled;; thet nit a ;;rdition; will ch;;;; : lowly. I M.1 and M.2 Condition M applies.to the following reactor trip Functions:
.- Pressurizer Pressure-Low:
. Pressurizer Water Level-High:
. Reactor Coolant Flow-Low (Tw; Leeg):
. R0" "r;;icr .";sition (Tw; L;;ps):
- Undervoltage RCPs: and
. Underfrequency RCPs.
With one channel inoperable, the inoperable channel must be 01**-f fr th: +-4aaad enndition within 6 hour-W;the Ptts_stjzggtegrgGEEErgssurazetJatetilevelEHjgM , UngL!tyettgl0RDPMJgg3!!glerftgeencERGtjplejgionEplacjg ttuticM~8fF4ht3rJpM!!(conditionishenLatge3hGJJlsetpoint rewitenmanessEammocosttlembatteamcantywapettimal i am .mygg esage .; c. +:
. n -
getr ou . . , m. m ... .. m m - wig m m m.o. . sults in a_ partial trio condition requiring only one a 1- aba=1>6 W u- ' M. .f t ^- I initiate a e--'-- trChe; tre ." 7 ;;;p;" - - CP 3.3 012
===r ===iR the -
ese functions do not have to be OPERABLE below setpoint because there are no lou af r tMr halow tha " ' cr'--4a+ 1REto n1 justified in Reference 73. An additional 6 hours is allowed to reduce THERMAL POWER to below P-7 if the inoperable channel cannot be restored to OPERABLE status or placed in trip within the specified Completion Time.]Gr.G;;;Li;;;;;;1..;^4flC,LM m1 Bak*isE CPSES Markup ofNUREG-1431 Bases, -ITS 3.3 B 3.3-45 1/2989
l 1 l ADDITIONAL INFORMATION COVER SHEET ' ADDITIONAL INFORMATION NO: CP 3.3-013 (new) . APPLICABILITY: CP . REQUEST: : The NRC staff requested that information regarding the CPSES setpoint methodology be included in the ITS 3.3 Bases. ATTACHED PAGES: , CTS 3/4.3 - ITS 3.3 Enci5B B 3.3-4, B 3.3-4a, B 3.3-60, B 3.3-65 and B 3.3-123 i i i i l
. . ~ .~ , .. - . - . . _ - . -..-. -- - -.-- --
RTS Instrumentation i B 3.3.1 ! BASES BACKGROUND The circuit must be able to withstand both an input failure to (continued)- the ' control system, which may then require the protection function actuation, and'a single failure in the other channels providing the protection function actuation. Again, a single failure will neither cause nor prevent the protection function i actuation. These requirements are described in IEEE-279 1971 l (Ref. 3). The actual number of channels required for each unit j parameter is specified in Reference 1. l Two logic channels are required to ensure no single random failure of 1 a logic channel will disable the RTS. The logic channels are designed such that testing required while the reactor is
, at power may be accomplished without.;;;;ing trip CP 3.3 009 1RitiatiWIprotectMMif."M3.yongeniessialtrip conditiofactuaByIgk_fqtsMThislarjses2fremitheluselof l colecidence3osicKessetatingireactorittMsignal s: and :.fromTthe !
capab111ty; tit @gassigpartiaT3rotect1Eaction%11elin test; , Pr;vi:ien; t; ;11;W r; ~;ing legi; ;Mancl; fre; ;;rvic; iring j
;;;; int;rer;; ;r; unr;;;;;;ry b;;;us; cf th legi; syst;;;;'; i;ign;d r:11;bility.
Trio Setooints and A11gggb.le Values The Trip Setpoints are the nominal values at which the bistables are set. Any bistable is considered to be properly adjusted when the "as left" value is within the band for CHANNEL CALIBRATION accuracy (i.;., i red ;;11bretion " ;gr;ter settin; ;;;urecy).3 TMHripDjgggN3MgtM11MablDL3731Til. The Trip Setpoints used in the bistables are based on the analytical limits stated in Reference 2. The selection of these Trip Setpoints is such that adequate protection is provided when all sensor and processing time delays are taken into account. To allow for calibration tolerances, instrumentation uncertainties, instrument drift, and severe environment errors for those RTS channels that must function in harsh environments as defined by
.10 CFR 50.49 (Ref. 53), the Trip S:tp; int: end Allowable Values specified in Table 3.3.1-1 in the accompanying LC0 are conservatively adjusted with respect to the analytical limits.
A itail;d 'iscripti;n of tk .etbilogy u;;d to ;;1;ulet; th Trip S:tp;ints including tkir tplicit uncert;inti;;, is previ i d in tk "RTS/SSTAS S:tp; int "at b ilegy Study" (R;f. 5)- nuJ8iimid9ETMmdR5imasensam4Eh96 c4 Win 1GB31EN#5""1 HEM 2WannelmEDE CP 3.3 013 9 MIME 1K t191RRp!EfRMR g lpgip10gE3 33LMpD WdJ n
; CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-4 U29M9
L RTS Instrumentation B 3.3.1 BASES 7 ' ii. - ifG 3 h E Q t!$!0d el e gt c"33o l wmenmussammamana:mattatsrana 1 T4simicR1MMRtatMBERRIL108MNDlot!sement ljgtsse2Mm17W2P18vttnity ljabitttK-2 7_;;~ ~ TT_Fr?;r21% actual nominal Irlp asim. meicu mo tne aistable is more conservative than that specified by the Allowable Value to account for changes in random measurement errors detectable by a COT. One example of such a change in measurement error is drift during the surveillance interval. If the measured setpoint does not exceed the Allowable Value, the bistable is considered OPERABLE. I CP 3.3 ED1 theleventiaIchannetlit.3etpoint11 sifound:ponconsetvative'n W1thirespectiteltheispecjfjediTrjp Setpoint;1butimore caiservatiwIthan;theIA13awableivalueEthe setpojnt:mustibe adjusteditoitheIspecifj_ed3riplSetpointi(wjthinicalibrat. ion allowanceslas!proyjdedlinithe3etpoint3tudy); CPSESMarkup ofNUREG-1431 Bases -1153.3 B 3.34a 109/99
4 RTS Instrumentation B 3.3.1 BASES As appropriate, each M hannel's response M aust 0 3.3 55 be verified every 3 months on a STAGGERED TEST BASIS. g .. ,
. >. 4 ; m.a. ,y 3: .g ( ,
Testing of the final actuation devices is included in the 0 1.1 4
. m sponse times Mannot be 4 deteramed-during unit operation because equipment operation is required to measure response times. Experience has shown that these. components usually pass this surveillance when performed at the 18 month Frequency. Therefore. the Frequency was concluded to be acceptable from a reliability standpoint.
SR 3.3.1.16 is modified by a Note stating that neutron and CP 3.3 ED1 E1Egangs] detectors ;; ;.MM .;;ei.]are excluded from RTS RESPONSE TIME testing. This Note is necessary because of the difficulty in generating an appropriate detector input signal. Excluding the detectors.is acceptable because the principles of detector operation ensure a virtually instantaneous response. Responseitime3fithe:Deutronlfittor Ng61sigga]3tAfgCofitheLehangerishallibelseasur.edfrom detectoG-ieitloGinput1to@elfitstiejectragigcomponentiin t_heIch_arge],; REFERENCES. 1. T=. Otept;r [73 3E1QiaptgGZJ
- 2. i=. OF;pter [5].QgtGh.8ptpf_H5]
- 3. i % , Otept;r [15]. IEJlEJEJ 393 .1
- 4. IEEE 2701071. 20ER3iO149) I 4
M M 3990l - 1
- 6. RTS/ESTAS Rtpint ";tt.edele;;5 Study.Ighgig].
ji;L w-
; J);
- 7. "J."
, 10271 " A. Suppl;.;;.t 2, iv.1. Jure !^^0."g3fgbM
- 0. Te,J .icel twira..ts "cr.;;1. Occtier.15. "h;pra; h*Mette,fL6.519g,Talgt_elligayl23?J)8M -
81
~ E01 191!fiHigERIsHID m 93 DietElmhnsstamiram@ndpletirJKdLrMect19n
- B3.tegg GmRltlEIEnisinit373RB21MMIOGED212N CP 3.3 013 i .
y 1 CPSESMarkup ofNUREG-1431 Bases ITS3.3 B 3.3-60 1/2989 l
ESFAS Instrumentation B 3.3.2 BASES
- BACKGROUND Sianal Processina Eauinment (continued) failure will neither cause nor prevent the protection function '
. actuation, b These requirements are described in IEEE 2791971 (Ref. 4). The
- actual number of channels required for each unit parameter is n specified in Reference 2.
Trio Setooints and Allowable Values The Trip Setpoints are the nominal values at which the bistables are set. Any bistable is considered to be properly adjusted when 1
~
the "as left" value is within the ba'nd for CHANNEL CALIBRATION
- accuracy.11helt!plSetpointsjagptoy1dedjnJable'83i3 Mil]
The Trip Setpoints used in the bistables are based on the analytical limits stated in Reference 23. The selection of these Trip Setpoints is such that adequate protection is provided when all sensor and processing time delays are taken into account. To ' allow for calibration tolerances. instrumentation uncertainties, i instrument drift. and severe environment errors for those ESFAS . channels that must function in harsh environments as defined by i 10 CFR 50.49 (Ref. 5), the Trip Setpoints and Allowable Values 3 specified in Table 3.3.21 in the accompanying LCO are '~ conservatively adjusted with respect to the analytical limits. Detailed descriptions of the methodology [eg used cP.3'3.E01 , to calculate the trip setpoints, including their explicity - %uncertainties, M hiG St 2 are ("ei provided E,' M in the ' iris /ESTAS Dn Se]tW" -
- N&m,imaammaannwwnw resoneemmenmanemameenanse
_Aloport
.__...-_-__-__.m........
i _ _ . . . . . . . . . _ . . . _ _ ...._..-.-
)
.a;,un . w: n.,;. a .
s y ~ ,3 L $ the bistable is more conservative than that specified by the Allowable Value to account for changes in random measurement [ errors detectable by a COT. One example of such a change in l measurement error is drift during the surveillance interval. If 1 (continued)
- CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-65 10/30/98 i.
ESFAS Instrumentation B 3.3.2 1 BASES (continued) l
- 5. 10 CFR 50.49.
i
- 6. WCAP 10271 P A, Supplement 2. Rev. 1 June 1990.
- 7. Technical Requirements Manual.
e an geese n_.. 1
- w. t,r,wi avves. . nww. a 5
nea rn w eese -n- a -~n _.., _ a __ e- me-s m x __-_s n____;.__ 8A N Tu#al .Y.ht.JS* d,2*1?f.,I.w! t 6 *w *- LJ" 8 !!_ t !.".bWL. .L,!?.**"_!_*
~ _ _ _ _ . . _._ _ _ _ = _ . ,__ __ ,__ r.__._ . _ _ . . .
~t.-- a--,- ,-- m-~_ . -m to . n,- ! s--- - 2 . ,, -. .--s .,
e + +-4 WKug; CP-3.3-ED2 9; IWestinghedie:Setpoint_Methodologyjfor2Rtotection - - - - - - - - - - . CP 3.3 013 l Systegs Comanchefeag; Unit.[12 Revision;1,2WCAP32123,: Revision"2,TjAprilD9892 i l I l I l l 1 l l l t r l l CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-123 1/29/99 t 1 . . , .
- . - - - = - . ~ _ _ -_ .
J 1 1 ADDITIONAL INFORMATION COVER SHEET i ADDITIONAL INFORMATION NO: CP 3.3-014 (new) APPLICABILITY: CP I
. REQUEST: Provides 'a reference citation for the 2 hour hour bypass time allowed by Note 1 l In ITS 3.3.1 Condition R. l i
i ATTACHED PAGES-Attachment 9, CTS 3/4.3 - ITS 3.3 Enci 5B B 3.3-48 1 i 1 l
-l 1
4 4 m J
1 RTS Instrumentation B 3.3.1 BASES be placed in H0DE 3 within the next 6 hours. The Completion Time of 6 hours (Required Action Q.1) is reasonable considering that in this Condition, the remaining OPERABLE train is adequate to I perform the safety function and given the low probability of an event during this interval. The Completion Time of 6 hours (Required Action Q.2) is reasonable, based on operating experience, to reach MODE 3 from full power in an orderly manner and without challenging unit systems. The. Required Actions have been modified by a Note that allows bypassing one train up to ! hours for surveillance testing, provided the other train is OPERABLE. R.1 and R.2 Condition R applies to the RTBs in H0 DES 1 and 2. These actions address the train orientation of the RTS for the RTBs. With one 1 train inoperable. I hour is allowed to restore the train to 4 OPERABLE status or the unit must be placed in H0DE 3 within the next 6 hours. The Completion Time of 6 hours is reasonable, based on operating experience, to reach MODE 3 from full power in an orderly manner and without challenging unit systems. The 1 hour and 6 hour Completion Times are equal to the time allowed by LCO 3.0.3 for shutdown actions in the event of a complete loss of RTS Function. Placing the unit in H00E 3 results11n Conditjon~CJntryJjffone]@ltrain~1sI1goperable.6emoves ~ "'3 3' " the requir;2at for this prtica r raation. The Required Actions have been modified by tw#-two-e3iotesj
- s. l:sts 1 gptemtjggallows one channel to be bypassed for o.3.3 117 up to 2 hours for surveillance testingg -
orovWd N nNr channel is OPERABI F wuno' - :ise d CP 3.3 014 (1jgit2GllUR1ffed3fCr:V 5 % y3s s a m ggl8 K t6 mm-s-- meJorittleli CGinRL4pf.RetfolWM sigtenamewmdervo1*suf3 Rah!aEstfpadenfenericaditfori y, provided the other channel is OPERABLE. %;t; 2 ella 3 en; " E to be b7;ssed fer up to 2 hours f nintarec en unincitesc or shunt trip each=i;;s if th; oth;r "E tr;in is 0"E"J."LE. The
- 2 har ti;; li;it i; justifi;d in "cfrena 7 3 S.1 and S.2 CP 3.3 ED1 Condition S applies to the P 6 and P 10 interlocks. With one origiore2eaQired channel (s) inoperablel for era cut-Of tu; Or tw; ;;t of four ;;inciinc; 1;;ic, the associated interlock must be verified to be in its required state for the existing unit condition 3y A-.AtM~;f3.E p;(;1;;j g3;.;gE;1;t;;3;iaid within 1 hour or the unit must be placed in H00E 3 within the next 6 hours. Verifying the interlock status manually CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-48 1/29M9
i l l ADDITIONAL INFORMATION COVER SHEET
- ADDITIONAL INFORMATION NO: CP 3.3-015 (new) APPLICABILITY: CP !
REQUEST: . Revises the Bases description of the Core Exit Thermocouples (CETs) to provide ; their design basis for the determination of inadequate core cooling and for i determination of subcooling. .l 1 1
. ATTACHED PAGES:
Attachment 9, CTS 3/4.3 - ITS 3.3 Enci5B B 3.3-138, B 3.3-138a and B 3.3-139 h l i l L l l, 4
- -- . .- m y
. . .__ -. _. _ . _ . _ ._ ~ . _ . _ _ _ . ___ _ . _ . _ - . _ _ . _ _ _ . _ _
PAM Instrumentation B 3.3.3
+
s3ASES
- -- .._2,- e e, . . . . . , 2. --- 2s-- s . ,._,..._2.L,.
t nb wwussw uva s bea wwg m.w w w s s up wwu ses wwi wga u uyyw n vus auwss } l L--..-- xL- -- x_ s ---_ -t_ -. 2 ---.._,2.1-_ --- wwwwwtFW DEUw wVIIb u w 3 5 wwsus supw bw s up r%s ui v7 Twt tw 5 u bwi ul w
--- al -A LL L L. -2__.. mr.-,
L,_ 2._A.1.wuLla_ ..,A L,.. a , w.s s . ,. a - b . b u vv . u , .w u b. . -- .
.r,. U b. .
I L The DBAs that require'AFW are the loss of electric power, L steam line break (SLB)nassanammarmamanlai, and small break LOCA. The CST is the initial source of water for the AFW System. ( However, as the CST is depleted, manual operator action is necessary to replenish the CST or align suction to the AFW pumps from th %t.-11 station 3etyjcQdeterj. 15, 16, 17, 18. Core Exit Temoerature Cgte38ttCNNgggg'eI1$X1T.ypf1Gategom1 Mad $le; fog l natammmmestNaMDtHmataggerinationMinttistiorg
- s 3andatae -
L 64tataliitteiiaW9MteMW y eMedumREIRangersemenMrenamiwme'ammriemuMah1**fm' CP-3.3-009 t ggggggCore Exit Temperature is pr_ovided for verification and long ; term surveillance of core
,_ _.. ,... ,_ ..._ _ ;_ .,mL_
cooling DIRD3Egland1,Ef~M._--- _2_2 _.._ _._L-_ _, ... 22 nss w ww sww b wus svu e susuww wu bysw sus a s a s useouses s susuuwb u v3 yuauw wvi w _ai .u----.._,_. ,e m _ - _ - - - _ . . ,-_ _---.._2__ ---_ wnib bs swa supwwwwy s w e gwwup s ywww.y.ywu g a we ruwww rws aary wwu w
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- - . . , au.
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.. ._L L 1. AL. L_x 1-_. -_; _-_.._2s-- 2 .1.A A --A.._-_
u wi swwwus a 55 burb a sw b uwyee uu rgs s yww sur u s s vv 355 3tuIwb bvassyws w wwu war. n-- J __ AL--- ...1...Al-.-- J--...A- ---- ---12-- ww wwns wvi bu rwww w v u l uu b s ws ter , w%sw3wwbw wwi w www s a u ry
- -. - J . 2 LL L... . . 12 A e--- r_ta =r----- L.._- L----1. --_
wu serwt W)s W s bu s www vuuau wwu w am I b c wissywu u bwi w wa vstv uu rw s ep ywg _. 2_ .A . 2 AL A. - erv. --- ---.2- ; L - - .- - 1 TL. erv _.2_ ngwwwi uvyb w s bus bww wwge ywu a wwgw i s wgs vs awe is sw a e sssw wk. 3 yu s a
--- -A _ . A 2 .1 1 . L. --->L -...s.. 12-_ .a ---- _ 22.1 us w we a we a bwss s uws e u s a y bv yv e ups e b w w u a wu b vs y va wva w u uss e u u J--.. _ _ . - _ Ja L_2L..A2-_ e--- r% 2 A v -- - A.._. J. ....; Am wwwwg ywwws w i e ba s wu b s wig , wwi w u rs u b s wissyws u bus b se w erw%s bv tx->_
2,xL-- s. a-.--.s_ A. es 22 aans 2_ -------- -_ ww bwi sus a a sw wur.birwu bv bwu aus 5 g Wu ww .# 6 e Ia eF b s 3 s t 53 yv wyl b nF =8 e vl J' e-. Aw- _ ,2 2 A 2. u.bwA . ., sw....b e.r A.s as s sb L-.
.v,..
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_-mm.u -uu--,- .- .a % m m m en . . I (continued) CPSESMarksy ofNUREG-143iBases -ITS3.3 B 3.3-138 1/2939
PAM Instrumentation B 3.3.3 4-a m .h-me---a mm . munnamamau ema m. mas r Am ._
. CP-3.3-015
.w
. .. ~ .
_y ._ , . 3 . j
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.g ,
IrME2metEtatuerMTBIMtGBABRD18EIP3!E)) (HIRE!!ManMRianetingangsgeselgenter3Noircus of3Ramt839GBlatB3m!IlMeraggggggEanisidianclude omDg!semigamestaitEgetsgesellegajzgTinen ttoisslaisussetentwt!!ctapaatta@ plan 11able CE14Z$.tt1CESMaiRBte[cgttt41JE]prM5holtrai_ny ofiCEIO!ggtIs1@ltJ9,11ute31HiggtId1Mleiths abil.ityltoidetersinthe:adessacy;otcote: cooling; r b i l I 1 (continued)
' CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B3.3-138a 129/99
.- - . . - . - . . . - - - - . _ - - -- - . - . . _ ~ - - - - - - .. --
PAM Instrumentation B 3.3.3 BASES T6 CP-3.3-009 f Two OPERABLE channels ORlh81tWsR1W WRD11sst5tWICETGRtCof Core Exit Temperature are required in each quadrant] 2] Ofi%Ssitq112aboye71stII.eattieneIper 1GD9eggadontDestlbe3oesteenri o# WrLthanit g two g tpfslof3ssembn es; eM 3] OEthilCETs3nII; abo 9eHtstinot;oneMthelCETS EaZAbmKEatneaglonelCETJper;traWoust" w centrellyilocatedWeorets r, v . s - in en;;n of radici distribution of the cecisat tv ycratura risc ;;ress repr acatstiv; regiens of th; cerc. P;';r distributica _ . _ . . . . . . . ____,s___s a_ 2. -__2_a_. a.
' eg n=uur w b s J www wwu u d s wws su ssu ww bwu sus s u a e u ry bs N
._-__222. .L__ __J 1 _ _ L 1_ ._ _ _--.22_J g_
dyww u a aw s ruussww s ustw I www b a vi sd yi w v s www s ws diegnesis of local ;;r; prebica. Thereforc.
.....___m_,.. __,__m_2 .L__
bww s us Twwsur u J dw s ww bw%s b3 Uw s Eurwwwwy 5 % e Ms w s tw b
...ssa_2-_t s. ___A AL_ L.._ AL______,._1. ___
QW5 a s w a wi s b . ww .arww b kstw kWw bs she mwwy a wa ywu _ L _ _ -_ _ s ___../--___i 2 _ _ . . _.._2_. a rt_ m. .. wesussusw a a w 3w sa wavywuab usa visJ gwwsus us u b . satw bww q d .._L _...A L &L. j AL_---__..1,w_., _ L _ _ _ _.1 _ s,s U-s, v . .. s ,. ~ s -.h .w b bs ~ bs ~u urw%..wy . 4 _222s2__.s .--_.2_-_- t a .x --- 2. s__.s_a . i bu su b wi N se svvubww a sw u s ww%s I b a vi ru a u w3w s a wruwwu s b mL_ _- t__ _, mL_ ____ __2 .L. _mL__ _ _ _ .a : bush wwusbvr vs b a r'. wws w usew burb v bs rvs a rwwe e ____ ___, m __ _.._L u .m m_ __,_ _ , , . . wvu w yws a s.sw bw u . wwbu a bs su b bu #w yw a s vu www w , ar - __ A. ._ _ _ a_Ja_.A. mL. _.J2.1 m - l s w myw s bus w., s i.w s w. bv bs ~ s ou s u s bw sys_.s _ u_ busA . , _ _ l gradicrut eccess their core qu;drent. Twe sets _,m.._ mL--- _ .._,__ _ _ _ . . . . _ , _ _ , _ , . , , . . _ _ vI bww bs rwa suswwwwy a w a wa saws W u e a s ry s w s u s s ut b
. .J 11 __A J J . .L1. AL. _L J 12 s . . &_ ;_t-__2__ u.
M#es. s rw w wswwwIE hssw ww a s e by bw ww kvaassessw bsaw
. , ~ . , _ _ = _ , , _ , _ . , , . , , _ - _ _ . . . _ _
_ .__ - m w. e .w. s--s-s bm~s - b-s e : __ 2,__. , .. w s ws s b. CEIs91s(ilgggggggEgolthel5Ubcoo11gNonitoel
- 19. Auxiliary Feedwater Flow?RateMNd'4 tem *GeMtator o.3.3 70 W tgim M9515fiffGBPREM E1 Ai!DlfEEMBLEADEELdGisI8HfE61categonnejr able fonisnterminationmueterminatiotcofradequat. e. Li_nadequa.te h8At31gKEILisI411tel417#elfat@od211gatiat0Telfg etgt1Lo_r1tig3M.ta!ssinlestatus2treensteam'seneratogatel L9MRide~RegeIB4M.YpeJEQtegoryJ11 Var,1ableJfor monitorJg"the%i, shiiGstates.Itf_ee211t21s31502E' backup (continued)
CPSES Markup ofNUREG-1431 Bases -ITS 3.3. B 3.3139 1/2989
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: CP-3.3-016 (new) APPLICABILITY: CP REQUEST: Revises the ESFAS instrumentation trip setpoint Allowable Value for the Unit 1 Steam Line Pressure - Low (Function 4 CTS Table 3.3-3 / ITS Table 3.3-2) to be consistent with CPSES License ~ Amendment 56/42. Also revises the Figure 2.1.1-1 ( Reactor Core Safety Limits (Unit 2)) and Table 3.3.1-1 Overtemperature N-16 coefficients consistent with recently approved CPSES License Amendment 63/49. ATTACHED PAGES: Attachment 5 CTS -2.0 ITS - 2.0 Enci 2 - 2-9,2-10 and 2-11 Enci 3A 1a
' Enci 38 1 EnciSA 2-03 Attachment 9 CTS -3/4.3 ITS - 3.3 Enci 2 3/4.3-33 Enci 3A 19b-Enci 38 16a EnciSA 3.3-23 and 3.3-37 Enci 6A 15 Enci 6B 22
i
. TABLE 2.2-1 (Continued)- '
~
TABLE NOTATIONS ~ ,
~
NOTE 1: Overtemperature'N-16 _.
..e...- s r
6 Tc . T c] + K 3(P-P ) - f (aq)
=K-K[{+1 1 2 1 Where.
4-mMeasure40er$ggggtuy1N -16 trjplsejpointl#mr by i= chP,crs T,; = Cold leg temperature. F,
.T,' = 560.5 F for Unit 1,ka Eggi for Unit 2 - Reference T, at RATED.. THERMAL' POWER, ;
Ki = 1.150. , i K, = 0 ^ ' ' ' *
/ F for Unit 1 4 w
'F.for Unit 2 $33,g3f _
% CP-3.3 016 i i
t 5 ^ t i i 4 CPSESMarkup ofCTS2.0 2-9 H29/99 i _ .-____c__--__--____________-_____----_____- - - _ _ - _ _ _ , _ - - - _ _ _ _ _ _ _ - _ _ _ _ , _ . _
' TABLE 2.2-1 (Continued)
TABLE NOTATIONS (Continued) NOTE 1: (Continued) ,
. It_ tis . - The function generated by the lead lag controller for T,:
1+ r,S -dynamic compensation, 13 r, - - Time constants utilized in the lead-lag controller for. T ,ri 210s, and r, s 3s, K3 =- 0.^^^^^^* psig for Unit 1l 02-08-A
= ^^'20 g sig for Unit 2 CP-3.3 003-CP-3.3-016 P = - Pressurizer pressure, psig.
P1 2 2235 psig (Nominal RCS operating pressure). S- Laplace transform operator, s ', - and f (a q) is a function of the indicated difference between. top and bottom halves of detectors of the power-range t neutron ion chambers; with gains to be selected based on measured instrument response during plant STARTUP tests-such that: , r 1 CPSESMarkup ofCTS2.0 2-10 1/29199
vt TABLE 2.2-1 (Continued)- TABLE NOTATIONS-(Continued) NOTE l1: (Continued) For Unit 1 (1) for q, - q, beteen -65% and +44@l0%, f (a q) = 0, where q, and q, are percent RATED THERMAL t POWER in the top and bottom halves of the core respectively, and q, + q, is total THERMAL [. POWER in percent of RATED THERMAL POWER. 003 , (ii) for each percent that the magnitude of q, - q, exceeds -65%, the N-16 Trip Setpoint shall be automatically reduced by 0.0t* of its value at RATED THERMAL POWER, and : (iii) for each percent that the magnitude of q, - qi exceeds +4-65:0*, the N-16 Trip Setpoint shall be I automatically reduced by 3-04RL15% of its value at RATED THERMAL POWER. ,
*gNo setpoint reduction is required for the span of the al indication. i For Unit 2 for q, - q, between -65% and :2. 53), f (a3 q) = 0, where q, and q, are percent RATED (1)
THERMAL POWER in the top and bot @tv iJves of the core respectively, and q, + q, f , THERMAi. POWER in percent of RATED THERMAL POWER, [,[3),g3 for each percent that the magnitude of q, - q, exceeds -65%, the N-16 Trip Setpoint shag (ii) ' automatically reduced by hB60;at* of its value at RATED THERMAL POWER, and 1 (iii) for each percent that the magg* nf q, - q, exceeds :2.6%), the N-16 Trip Setpoint shall automatically reduced by 1.5f L2{of its value at ray mtHMAL POWER. i
*J ofsetpolLtir, eductierri[4sitrequiN!d'sfoqthelspe3311thefalljindication! i
[ The channel's maximum Trip etnnint4 hall not exceed its computed Trip Setpoint by more than 3-64gRt NOTE 2: of span for Unit 1 or 1. of span for Unit 2. is01&nd i CPSESMarkup ofCTS 2.0 2-11 1/29/99 1 5 _ _ _ _ _ _ . _ _ _ _ _ _ . _ . . _ _ _ _ _ _ _ . _ _ ._ ._s.___ _
+
CHANGE , )MBE8 KSIE DESCRIPTION ( [ E ,M 8 samtappia!!stagenset g;3 3:0g , 1 maanmuswam - ElMR f , l l l l l I l I l l l l l l l CPSES Description of Changes to CTS 2.0 la U2989
CONVERSION COMPARISON TABLE - CURRENT TS 2.0 - Page 1 cf.1
-TECH SPEC CHANGE APPLICABILITY NLABER DESCRIPTION- DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 1-01' The specific restrictions on mmber of loops and licensed No .not in current No - not in current - Yes- Yes A reactor power for power operation would be removed from the TS. TS.
SLs. These restrictions are stated in other requirements of the license. 1 The requirements embodied in separate administrative Yes Yes Yes Yes A. controls dealing with SL violations are deletede 2-01 The requirements of this LCO are moved to ITS LCO 3.3.1. Yes Yes Yes Yes A 2 02- The Reactor Trip System Instrumentation Trip Setpoints are No - retained Yes - moved to ITS Yes - moved to Yes - moved to LG moved to a licensee controlled document. currentTS.See,pH 3.3.1 Bases USAR. ITS 3.3.1 Bases. , 2-91*A O . 2-03 CTS ACTION b.1. Equation 2.2-1 and the values for Total No - not in current No - not in current. Yes- Yes A Allowance (TA). Z, and Sensor Error (S) are deleted. TS. TS. consistent with NUREG-1431 Rev.1. as they are no longer required. 2-04 .Witi= f th 'z;rHty :fr: t: PA.- P,. M Pg VesNA ". . ret;ir, a.. c;c.; VesN3 Vesg g
- I N - ./.;t;f. witt. """.C0 l'01 ";; 1. ir.dic;;;; tt.; HMIA :
ca.~ .c.tiv; di. ;;is, fr it;;; " v;h;c;. 2 05 Ri; J .e ca . ;;;; tt.; '"oT er.d 0"oT ; ; tic 17. tt.; OC"" YesN/A NeN/6 Neit/A NeN/6 E_$..$,.f.'3f.f.33..,.35.~3.f!liIN_J"',i,ri.M,_E'*?;;.
.~ . ,
.~ _
2-06 The requirements stipulated in ACTIONS [a and b] are moved Yes Yes Yes Yes-LG to ITS Table 3.3.1-1. with explicit direction contained in the ITS Bases. . 2-07 This change incorporates the values for T* (Nominal T.,,at Yes No No No ' .f A RATED THERNAL POWER). that were inadvertently deleted during a previous License Amendment for DCPP. 2:00 lhis&SE51speclt ieggsagglmtlaetkTableN14tENesenhida liq Yes Iso a t 8 ERGectL CP-3.3-003 W9t&iltG_ _ --
=.- M15M!lg P-3.3 016 '
4ligensteitzgu L CPSES Conversion Comparison Table - CTS 2.0 D2989
-- .. . . . . . . . - - - - . . - - .. . . - ~ . . - . . - . . . . . . . - .
SLs 2.0 670 660 ___
- Unacceptable Operation CP 3.3-016 650 l P = 2385 psig 640
~
\ !
P = 2235 psig E e 630 A -- 620 , P = 1985 psig e : I \ 610 s P = 1845 psig-l 000 Acceptable Operation
- 590
\
580 >' > - >+ ' ' ' - >' ' O 20 40 60 80 100 120 Percent of Rated Thermal Power l' ' !- Figure 2.1.1-1 (page 2 of 2) Reactor Core Safety Limits (Unit 2) CPSESMark-up ofNUREG-1431 -ITS 2.0 2.0-3 1/29/99 l' . _
u t. c TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRtMENTATION TRIP SETPOINTS TRIP ALLOWABLE M9d FUNCTIONAL' UNIT' SETPOINF VALUE my ~, w.x . .
- c. Containment Vent Isolation
- 1) Manual. Initiation See Ites' 3.a.1 and 2.a above. ' Containment Vent Isolation is manually .,y y y initiated when Phase "A" 1 solation function or containment spray L" < e function is manually initiated.
2).. Automatic Actuation- - N-A- N.A Logic and Actuation i Relays j I
- 3) Safety Injection See Item 1.' above for all Safety Injection Trip Setpoints'and Allowable Values. ;
- 4. . Steam Line Isolation
- a. Manual Initiation N-A- N.A t
- b. Automatic Actuation Logic N-A- N. A -
5 < and Actuation Relays i
- c. Containment Pressure--High-2 : 2 S.2 p:;ig 5 6.8 psig l
- d. Steam Line Pressure--Low
- a. Unit 1. E 505 psig' 2 g*
, CP.3.3-016
- b. Unit 2 E 505 psis' E 578.4 psig*~ ' l 2m ,
- e. Steam Line Pressure- i Negative Rate--High .. 2100 psi" 5178.7 ps1**
t
~
CPSESMarkup ofCTS3N.3 3M 3-33 ' U29/99
... - - - . . . - _ . - - . ~ . . - . .
i i l J l L- CHANGE NUPEER EitE DESCRIPTION
.,,,,..m....,_- . . . . . , . . . . . . . . . . . . . . . . . . .
g CP 3.3 016 j ;g.Djr: .-1...
. . y 4mg lee 38Him umMaussisalepl33?r g Is1 Tat s mat t (J K ittle!L O W 50R ti! E 6.
31 N N M g 3 01 A The requirements of this current TS [3.3.3.1) are moved to [three] separate specifications in the improved TS. The RCS Leakage Detection requirements are moved to improved ) TS 3.4.15. [ ] The Control Room requirements are moved to improved TS 3.3.7. [The Containment Ventilation ! requirements are moved to improved TS 3.3.6.] I l i i CPSES Description of Changes to CTS 3N.3 19b 129/99
t CONVERSION COMPARISON TABLE - CURRENT.TS 3/4.3 Page 16a of 22. TECH SPEC CHANGE APPLICABILITY NUleER DESCRIPTION DIABLO COMANCHE WOLF CREEK CALUWAY~- CANYON PEAK
,[
2:53 14guismalamme141mepsipm1RM1009 l19 M h yet 0'3 3-21 LG enmisheseeven!tNERA# Mon 61119e e;asigne;,xempig atml82aleMuentl*NAWLc!n*AuG2 ,
-59 h ettenlofJCUhklieliminees.ggtposs1Merecours,1tocart411owableJelueget MEliot:1n_CTI > E.M 10 In 1 ,
in hM ListadelstenumeteilTeDhle&Adidamabatfibamsklandsalatipplunction. eltMtg 41adiL4W681cK44 mage @Te11s_2ndesettnesseBhope1LCDmitementsaare too y,s !se 0-247 (3.3 ] netspap anddeactLvatedi 1 a ; FAsg mPaareACHDutStataan-faantev r and - to M ew the yes M g 0-2-os (3.3 , L3d6 tameneustsaisegnameBLomplaced;to;noomieg aladDiaNRI h ! 23Z CurtenteDiedAlma@yadimmettang11MteniskakigentainmenMPurge alsolation lioAllot insCTS t M X llott ig Yg yg 3 3,3; [ 8 lonal unit 3 M GT3 . Cettt9k JI!rlaysitssys)giang
#sepc_ !
2c56 Action;statementatoLC11 3L4;3AddaMai0R94L9estionaltw1lgggangage11gsJeter2storagelank 1.eyel tio tio yes Les ], 6 ' (!Ili5DeiBeltdL8LGo19 Ming $lMIS$5stagg , loJactions i ( 59 The;Autaget1McE. log 1CandLMo1n RglgysM og11siadded,the_ESF_A5 No Yes Liq pq l CP-3 3-01L E 5 LossioMtmenWessagskiWXJpjr CESE5fg i R:6Q 8evihadsheadlheettimJa]uegor theAttil m lig yes gg g
- 3 3 01 ],
5 t 8 SNietL46sBbbaElmheII51TebJeA3 2)1 tem - m Gossi j i CPSES Conversion Comparison Table - CTS 3N.3 1j29,99
.~. . - . - _ .-_ .. . . . . - - . . .
RTS Instrumentation 3.3.1 Table 3.3.1 1 (page 8 of 9) Reactor Trip System Instrunentation b$ Mote is overt-rature M-16 CP 3.3 003 The Overtemperature N-16 Function Allowable Value ahatt not exceed the following frip petpoint by more than 3.3-138 NdphGo!CunlEL31FC I#pelCfir3MIE3 Cp.3.3-016 aB-P$iN (1 + tis) Q,,y,,,=Q-% Tc - Tj + K,( P- P') - f,( a q) ( 1 + t,5) leilitM a <a sm MessuredJiisttempet#tu6i!!iMGrlp]4ittlpirL"1 i lAJC-[_' s. l K. ! 111583 g, '.forl Unit :1 e EJorcunit] __ CP 3.3 003 44 pets:for;uniti1 ~ 3.3 138 1 ._.0 L psig.fpr, Unit 1Def9tenceX.)t; RATEDJMERNAI. POWER CP 3.3 016 7, i oldJWtemperature 1.3 4 aggesento,xnATsianumNAL POWER (
.Jittiti;1 4 . .. M O MfM3 P3 4 miliihtid:ptsitifJ CPr9eekef peld t' 3 23RENH (N4MneutcOipigntine:ptWinte; U 9 ttiCON#iEttiinif9tinYpi#torzie(N YJi,2EEnieritiero6ti sti!tiertrRteiiiEtsswiinttenW1f6dT,3 WJuss L 1 0 eci en e . 2 3 see iJGD'S 0;os%EckmMM IKeh"RE%FbestrtTE Irefiu.g ora whenMass2telt&sMKW6%KMR Dr#68353RE%FEdiMi910 idisO4.1st)3t2ter61953tE CP 3.3 003 3.3 138 tiOGE91Rei 2ff4DE65N SiiiEEKiUWA55]tfR
~
** CP 3.3 016 IEllHERI 05)T-14 I I&23LEiG'I 4. AII2fa&*EUih titenJAd . ge UB J
CPSESMarkup ofNUREG-1431 - ITS 3.3 3.3-23 U29/99
l ESFAS Instrumentation l 3.3.2 Table 3.3.21 (page 4 of 10) Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR SP ED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION COWITIONS CHANELS COWITIONS REQUIREENTS VALUE88
- 4. Steam Line Isolation (continued)
- b. Automatic Actuation 1.2i". 3") 2 trains G SR 3.3.2.2 NA M Logic and Actuation SR 3.3.2.4 Relays SR 3.3.2.6
- c. Containment 1.2"8. 3"' 43 D SR 3.3.2.1 L6.8psig 6 g gspg g Pressure - High 2 SR 3.3.2.5 6-61 pe4g SR 3.3.2.9
" 2.3.2.10 SR.3;3 Z 10
- d. Steam Line Pressure 1.2 "8 3 per D SR 3.3.2.1 t-676 q (1) Low' 3*"" steam SR 3.3.2.5 5E5 ps49 "
line SR 3.3.2.9 .O 3.3 55
"" 3.2.2.10
. ps g.3.3 55 SR3;3;2.'19. (unirl) - ~
(578.4 L--------. P' 3.3 138 (Unit'2) CP-3.3 016 1 (2) Negative 388H" 3 per D SR 3.3.2.1 [178;Z"' W pgygj Rate - High steas SR 3.3.2.5 ps1 ps*4ses* line SR 3.3.2.9 leh6 0" 2.3.2.10 ps4/see SIL13%M
- . "i;'. :::= ":.: " T= a.ra*A* e-per e :" 2.2.2.1 fet 4-f+ IE3220M St:= Li..c steen 0" 3.2.2.5
+4fe 0" 3.2.2.0 C" 2.2.2.10 Ceinti..: dt' 4,a**r 1-pee e 5" 3.2.2.1 i [550. ]'" ; ;553;'"
T,,, L;.; Lc: 3** 4eep 0" 2.2.2.5 0" 2.3.2."
= :. .2.12
- CPSESMarkup ofNUREG-H31 - ITS 3.3 3.3-37 1/2989
'l l
CanNoE Nl#EER JUSTIFICATION automatic loss of power DG start instrumentation to be operable in these i modes. L 3.3 130 Consistent with the current TS and the CPSES design, the 0 3.3 130 Cer.ditier.;. ";; ired A;ti;r,; ;r.d Surv; iller.;;; er; gglllEnot applicable to the 6.9 kV Preferred Offsite Source Undervoltage l function if the associated source breaker is open. When the associated source breaker is open. credit is not being taken for the immediate availability of the 6.9kV Preferred Offsite AC power source. I
'3.3 131' TS Condition B is replaced with new Conditions B. C. D. and E. Condition C in the ISTS is changed to Condition F. The CPSES current TS have specific actions'for the various bus undervoltage and degraded voltage function. These actions allow an appropriate amount of time to restore an-inoperable channel or declare the associated power source or bus inoperable and take action to isolate an inoperable power source. These actions are a proper way to respond to the inoperable channels because the actions. result in taking the Required Actions in ITS 3.8 associated- ,
l with'the'affected power source or bus. The new Conditions match the Actions of the current TS. 3.3 132 The trip setpoints for the loss of power diesel generator start instrumentation are moved to the Bases. This approach is consistent with a format allowed by a' reviewer's note for the RTS and ESFAS . instrumentation. l 3.3 133 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). 3.3 134 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3 135 A MODE change restriction has been added to-ITS 3.3.1 Condition C per the matrix discussed in CN 1 02 LS 1 of the 3.0 package. (See the LS 1 NSHC in CTS Section 3/4.0. ITS Section 3.0 package). 3.3 136 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). M NotreciateleXDEElilMEieMiceussion: ConstiMYab1A cA 3.3 012 LEM]sglltg6BM EE ~ CZ5MiE36 CP 3.3 003 cP 3.3 016 ma-.aury l~ [g e v . ' L ' . . t ' , " 7 . ' . , j f n 4 ff M$ L MM . tigt3ppigableMRiili!MI5.eMotNmion:CeparDon1Tabl# oc.Au. 0az l W@lMtsB11 CPSESDiferencesfrom NUREG-1431 -ITS3.3 15 1n989
y CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431,' SECTION 3.3 ' Page 22 cf. 22 TECH SPEC CHANGE APPLICABILITY j NUPEER DESCRIPTION DIABLO CANYON CONANCHE PEAK. WOLF CREEK' CALUWAY D eSeingjo!yfmannemassmeeL4ssmngshCMt@Lnititig,9 yes Mhllhpass_Agtfog M s .Enta giggg g gg Egg aman 13Z CA 3 3-0"
- popliesio t spelgesq$a 3801E .
containes p ig W gentotaquetintges Actest not A1 9 4 rot 31eiX senMe Hiffenw31 des!9n) (diffgegasiAssist) Agaspaskese4st BishmaelsHHhd asiammmenammann i 3_i3 :138 Ihis3CPSEkspec1ggnglbggRttagisesulable,A@i 1L 1_i_Y-3! No Igs No N MIRBU -3.3-00 , liq 1tm24._ _ - - - M_6 m. m cm - _
--s- m m m
~..eam , u CP-3.3-O'.6 - I
. - _ . . .. .- . .,3 w_ _ _-
g g g g j nsanna,anothemaner.amamanamanae tensnamenemmmwar;.a DC-ALL-01 2 l IAE&iltlRGi33BIRlWE GhengesjtotR.I5itandifiSMWE@uistignitate s sedelto a tefject No No Ng. leg - 3A149 CA-3.3-007 calj awer.oldtsend!!smptopJagtniteqL40K98j abh141 Ghengestto1ESMSigeeGLERED43gla];Ma@ggitonsattendette M No No les '
-3.3-00 2 reflect.Ca11-14/13/983 3 ; 32144 Addshtraig' te:I.EGoodit.1ggaricensistentivithiI]}
a Yes Yes les les gumummmmm4 ; 3.h2]anLISIE135] E TR 3.3-005E , WM !terjm sit,3;3migg!segang.gtecitta.nletISTFAllgjg yes Yes Yes leg Y[
- CPSES Conversion Comparison Table -ITS3.3 1)29)99
ADDITIONAL INFORMATION COVER SHEET l ADDITIONAL INFORMATION NO: CP-3.3-017 (new) APPLICABILITY: CP REQUEST: A plant review of the ITS submittal identified that an ITS surveillance of the hydrogen monitor channels was not the same as the corresponding CTS surveillance. The CTS surveillance only requires that the hydrogen sensor modules be calibrated every 92 days, whereas the previous ITS markup required a full CHANNEL CAllBRATION every 92 days. The ITS is revised to be consistent with the CTS. In addition, the CTS is revised to add a surveillance to perform a Channel Calibration on the hydrogen monitor channels at least every , 18 months. This change is more restrictive because this requirement does not i exist in the CTS. ATTACHED PAGES: Attachment 9 CTS -3/4.3 ITS - 3.3 EnciSA 3.3-47 Enci5B B 3.3-144 and B 3.3-145 Encl 6A 3 Enci 6B 5 Attachment 12, CTS 3/4.6 - ITS 3.6 Enct 2 3/4 6-14 End 3A 14 and 15 Enci 3B 11
PAM Instrumentation 3.3.3 SURVEILLANCE REWIREMENTS
.........................................N0TE--
SR 3.3.3.1 and SR 3.3.3.03 apply to each PAM instrumentation Function in
^
8+8 Table 3.3.3 ' "_ ~s^ =- --
- ^
CP 3.3 017
.................- - - .- J..........................................
o l l SURVEILLANCE FREWENCY SR 3.3.3.1 Perform CHANNEL CHECK for each required 31 days ! instrumentation channel that is normally l energized. SR
- T 3:3:2 R3 ::
n.,a._ ====~#. :=u_NO.TE=T
- ~ m.u_T W=';;==_== m.; ->
Applicable ~itp30dtggenl.nonitoJr J:hannel41Wy;
- Tr = :r; 3.3 27 w r.Tr.7
.m % ::w..v.... _.= r _: =.7 =
. -m= ,.m=.= " - " CP 3.3 017 92 days Parlotm3.Abtsormodulg3:alibratiorHH481Eh
"^"
SR 3.3.3.03 w ,~..
;;utrer ;; ;;;;r., ar; ;;;;;d:d fr;;;; +3:3_-70H GMNNEt-GAL 48 RAT 4%
, - . - . _x.,,,._,.~qauw. 9.pu. n.v _. _ a -____su
.*a$ ,
g CP 3.3 017
;... . . . . , . . . , . .. .l 2.'.*:' .' .; .. ".) :' ',
l ._ ;.,, . 0-3.3 20
.. , . . , . . . . . .....,....,e.
3...., ,
. .. . f .} . , . H ,' , ' . ' . , h' , .} . .g a .',.
_- . ~. : . L :y ; pg y.
. .g.,,; v, . . ... .. . .. .
l
- m. - - . _ . .
i 9811Mi!EEENI L Perform CHANNEL CALIBRATION. lj months m%BMt;4 , 1 I 1 4 I l l CPSESMarkup ofNUREG-1431- ITS3.3 3.3 47 1/2989
PAM Instrumentation B 3.3.3 BASES are not equivalent, and provide a schedule for restoring the normal PAM channels. SURVEILLANCE A Note has been added to the SR Table to clarify that REQUIREMENTS SR 3.3.3.1 and SR 3.3.3.23 apply to each PAM
~3 3'01 instrumentation Function in Table 3.3.3-NlMMA8PPngs onlyltoLthejegbioperL__.t CP 3.3 ED3 E l d M Z l M ~ E G E5M E EE w i i G ion-SR 3.3.3.1-Performance of the CHANNEL CHECK once every 31 days ensures that a gross instrumentation failure has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between the two instrument channels could be an indication of excessive instrument drift in one of the channels or of something even more serious. A CHANNEL CHECK will detect gross channel failure: thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION. The high r: diction in;trunatetion ;hould bc ;;;pred t; ;imilar unit in;trunnt; 1;;eted throughout the tmit-Agreement criteria are determined by the unit staff, based on a combination of the channel instrument uncertainties, including isolation, indication, and readability. If a channel is outside the criteria, it may be an indication that the sensor or the signal processing equipment has drifted outside its limit. If the channels are within the criteria, it is an indication that the channels are OPERABLE.
As specified in the SR, a CHANNEL CHECK is only required for those channels that are normally energized. A113Dffjthhd 0-7-09 1Rl!t!$1eglyCf1(giJd GDlg23J31}Igggtspl1Eglggipdf The Frequency of 31 days is based on operating experience that demonstrates that channel failure is rare. The CHANNEL CHECK supplements less formal, but more frequent, checks of channels (continued) CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-144 1/29/99
. .. .- . . . - . . - _ - . . - . . . ~ . . . . - - . .- . - . - ---
PAM Instrumentation B 3.3.3 BASES during normal operational use of the' displays associated with the LCO required channels. SRP3:3M CP-3.3 001 d.
. -4BenAEWMEMEJ81
. m ieltg LauteK9 s M M d1 Verifies;that tKegggggggigat!go!nemt*1stoonsgettyin;the j ;
sicNJgalge]2Hpis1SRIts'aodj!!etWKJiotejindicating thatith1RW3MEspplicableitolthelhydrogeOonitors;.~RThe EtequencylsIMIonimamfactugr,isfrecolmilendationsj ] j 1 [ SR 3.3.3.03 1 1 A CHANNEL CALIBRATION is performed every 1$ months. or approximately ; at every refueling. CHANNEL CALIBRATION is a complete check of the i instrument loop. including the sensor. The test verifies that the channel responds to measured parameter with the necessary range and O accuracy. L .1'; m ;s n,c m e; :;y ..m- ; Net; uth;t ,excl %. ,.;._;._.tren m.__
- -. s __...._.._...,m_m 2, -. -
. ,..m The ;;libr=cr. 7;;hed f;r n;utier. 0;;;;a .. .,y,... ic; in th; !
3;;;; ef LOO 0.0.1. "R;;; tor Tri;; Syst;;;; (RO Instru.;;ntetion." M The calibration method for neutron detectors is specified in the Bases of LC0 3.3.1. " Reactor Trip System (RTS) Instrumentation." _.m-_.,___...___- TR 3.3 004 gn , , L ~ ; . >. g. L ;g w. g.,y.sy unnett-ammsnaranrapanmuw enrenwwee-MIDE4MI.EDlEMMt32X32MDf)tioEthat m . - - an 3 .n w .s ii 4a.ir .ii.e ggstm The Frequency is based on operating experience and consistency with the typical industry refueling cycle. Gglaji - . :?. A e etERERfLWilich;BggghMiglNJM SEc0MRES630,1l!SABRMfgh6BRl8DMfgot 0-3.3 20 inel swH feterhenataBNNBfrW9MrGM"dar*nftsWRdmWRERnHhrWantl T A OlHDDO.fMfal: hem 181;@%lM3ft10lH10FM Rtth3agggggtmpspgelgamma;sMM CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-145 1/29/99
- . . .-. - . . . ~ . - - . - - - . - - - . . - .
CHANGE NUEER JUSTIFICATION 3.3 23 Modifies ITS Surveillance Requirement 3.3.4.2 to include power circuits per Current TS 4.3.3.2.2. This change is made to match the plant design which includes transfer switches for power circuits as well as control circuits. 3.3 24 This change revises improved TS Table 3.3.41 to reflect current o.3'3 24 TS [3.3.3.2.1], c .- .~ cW.; g3ggggggdeletes references to " controls" in the table. (3x els; ON 3.3 ^A), and changes Tequired %;;ter of Isatieas" to tequired Channels" sf ace the t;ble has tc; raixd t; includ; enly instr; catation. MMIM heade!@EWISES185lERNM.dCMiseCE'RES!IREDMNNELSL com18tesEMthrsthamnistanFE!Etab1Eastgith1CEI@M313152 Reis1993olu!gggggle!11MEDElLEDlWl5lELFitCM11[ce!!flicMth the3091e!LatattttLtleistiga110anas; gad!!KtMHableito ide011tE!helsMGit1Gnstr1ggggg3Ifynetg1 As raixd. the table is new ;;asistent with th; formt ;f th; oth;r t;bics in ITS Section 3.3 ITS sad is tc hnicelly the 37.x s th; aricat TS r; quire n ats. 3.3 25 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). 1 3.3-26 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). q _ , i 3.3-27 This change modifies R 3.3.3.2 @ 0",-3.3.3.Jto allow for CP 3.3 017
.different surveillanc frequencies for Ine aydrogen monitors than other PAHS u-00nents. The manufacturer for the CPSES hydrogen specifies a more frequent calibration frequency monitor than required (tens for t1e#Wed61lis)her ot PAHS The moreinstruments.
frequent calibration is required to assure function operability. 3.3 28 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3 29 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3-30 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B).
-3.3 31 The current TS require the response times associated with the 0 3.3 55
[undervoltage and degraded voltage diesel generator start functions sad th;] ;;at:ian at [ventil tion] isciatica fu nticas] to be verified against the specific response time values contained in the [TRH]. The ITS is revised to match the current TS and the response time values are [ retained in the TRH]. As is done with the Reactor Trip System and the ESFAS instrumentation, this method is an appropriate way to control response times. [SR 3.3.5.4 and modificationgshbliEMS 54 0",3.3.0.3] are added to require the response time verification.
- CPSES Lifferencesfrom NUREG-1431. -ITS 3.3 3 in9/99
CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431.-SECTION 3.3 . Page 5 cf 22 TECH SPEC CHANGE APPLICABILITY Call.AWAY NUPEER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOL{" REEK 3.3 26 The Pressurizer PORY and Block Valve Controls are deleted No - not in current No - see CN 3.3 24. Yes Yes (per FSAR and RCP Breaker Position and AFW Suction Pressure are added TS. Section 7.4.3 and to improved TS Table 3.3.4-1, consistent with the current SER Sections 7.4.2 licensing basis for compliance with GDC-19. The P0RVs may and 7.4.3.2) be used for eventual plant cooldown; however, they are not > required to attain HOT STANDBY which is the basis for the listed functions. The added functions may be used to ensure decay heat removal by the SGs in attaining HOT STM OBY. 3.3 27 This change modifies ITS SR 3.3.3.2 6 " 3.7.3 h to allow No m No No. for different surveillance frequenciesJfor tne nydrogen monitotdii - ^ "-nan other PAMS components. The N . manufacturer for the CPSES hydrogen monitors specifies a more frequent calibration frequency than that required for N l CP-3.3-0: 7l' the other PAMS instruments. The more frequent calibration is required to assure function operability. 3.3-28 Tie breaker grjyj,]laged ch .. ; per current TS Table (A No - not in current No - not in current No - not in current Yes 2 0.3 3, "O l^" St;t _ ..t 1^ for Functional Unit 8.b is TS. TS. TS. (current 0-3.3- 2 pddeal. TS per OL Amendment No. 99 dated 4-18-95) 3.3-29 Functional unit 7 is revised per the DCPP current plant Yes No No No design to incorporate the residual heat removal (RlR) pump , trip from low refueling water storage tank (RWST) level. ACTION K is revised andillewjg&32.12 ;t; . ,,,.ir; p?;;ir.;; ;r. i.m. ;t?; che...~1 ir. ; triry.d . . .,.; 53;. ,,4 l DC-ALL 002 l t
-,,.~ . ..
r.. .,,.....,y.... ~ , , . . < . . . . . . _ _ . . .
"q,.st M; :~~.. ; t-itted WRISh10 weggeutungeALQg)yi)Dg 1
199hto incorporate these changes into the CTS. 3.3-30 The portion of II5gggondition C 'r;?;t led n 0 pcr No - not in current No - not in current Yes Yes CN 3.3 74) referring to one or more functions with one or more automatic actuation trains inoperable is revised to TS. TS. l0-3.3- l0 l , cover "90P ESFAS pctuatiitonitteins*ionly.tThommLrd "changels"tisfaddediafter@mmutal"dirLCog@Mang& tat,Ci , CPSES Conversion Comparison Table -ITS3.3 129,99 P _ _ - m_<._.__u...- -. _.__ . . _ _ _ . , _.___.x________ _ _ _ _ _ _ _ _ ___m____._____u__.______.__.-__________-___4_____m - __,_,*-m . _ . _ __._w--
CONTAllMENT SYSTEMS ; I. ! 3/4.6.4 - CaleUSTIBLE GAS CONTROL 107 A p- 0 3.6.0-1 L HYDROGEN MONITORS LIMITED CONDITION FOR OPERATION
'3.6.4.1 Two independent containment hydrogen monitor trains (with at least one ,
channel per train) shall be OPERABLE. APPLICABILITY: MODES 1. and 2, anggg g ACTION:
- a. With one hydrogen monitor train inoperable, restore the inoperable sm, monitor train to OPERABLE status within 30 days er b; in at las:t "0T ST!."."~"Y within tre nat S h;urs. otisutulitra SpeciallReportEin
, accordagpgMK30CHt50MWithiq1the;fo11cwingi14; days; outlining;the pinlainesia.itMnatemethodlofisonttoringtitheicause;oLthe inopergtlR)tyEendithelplaps :andischeduleifpritystoring .;thelhydrogeg ! monttgrjggenng},EtoLOPERMLElstatussi The provisions of Specification 3.0.4 are not applicable. ) ! b. With both hydrogen monitor trains inoperable, restore at least one agg ' monitor train to OPERABLE status within 72 hours or be in at least HOT S - STANDBY within the next 6 hours andlbe31n.RSitT[DOWNJithinithe;next 61Wsi l SURVEILLANCE REOUIREMENTS i 4.6.4.1 Each hydrogen monitor channel shall be demonstrated OPERABLE:
- a. At least once per 31 days by performing a CHANNEL CHECK, and
- b. At least once nar @ davs = :: S' YTJ"L" H ST "Z IS by performing a Csensor"le?"d*atidfD 0"f-~M7""J"9 ::libration ;;querce EM) us;;; ;; p;; ;;; n exerdere; .;;;r, tre =nuf;;turcr': rec; .;;ndations end by verifying th;t tFe current ;slibr tion ;;n; tents-ere - -
;;ntaired in th; ;icreprea;;;r d;ta b;;;.
_w 12 08.M M A.Me866]SRATIM;, CP 3.3-017 I CPSESMark-up ofCTS3N.6 3 M 6- H H29/99 l
L
.; CHANGE -
NUleER EliC DESCRIPTION ! 12 01 A Consistent with NUREG 1431 the hydrogen monitoring specification is moved to ITS section 3.3.3 concerning Post Accident Monitoring instrumentation (PAM). 12-02 M Consistent with the MODE of applicability for PAM instrumentation in NUREG 1431 the MODE of applicability for the hydrogen monitors is extended to MODE 3. 12 03 LS 15 Consistent with NUREG 1431 the action is revised to require a special report be submitted with 14 days in lieu of being in HOT STANDBY within 6 hours if one train of hydrogen monitoring cannot be restored to operable within 30 days. This is acceptable because the report is required to identify alternative methods for monitoring and plans and schedule for restoring the instrumentation before a loss of
, functional capability occurs. (See improved TS LC0 3.3.3 l and Specification 5.6.8) 12 04 M Adds the requirement to be in HOT SHUTDOWN within 12 hours if both trains of hydrogen monitoring are inoperable and one train was not restored within 72 hours. This is a more restrictive requirement than is currently applied and is being done to be consistent with the PAM requirements in NUREG-1431.
'12 05 LS 16 Revises the frequency of the hydrogen monitor surveillance to perform CHANNEL CALIBRATION from 92 days on a staggered i test basis to once per [92 days, deleting the staggered test i basis] consistent with NUREG 1431. The hydrogen monitors are part of the Post Accident Monitoring (PAM)
- instrumentation and their primary function is to detect high hydrogen concentration conditions that may occur during accident situations. This change is acceptable because the primary means of reducing hydrogen concentration during accidents is via the independent hydrogen recombiners[ and hydrogen purge systems]. Failure of the monitors would not affect the capabilities of [these systems]. Further changing the channel calibration surveillance interval from 92 days (on a staggered test basis) to every [92 days] is not expected to effect the reliability or performance of the hydrogen monitors based on industry operating experience.
l: 12 06 LG The W 'e P adM for performing t l [ mod ()(Att1 brat 1EC'""il O'LI""#IIT: fare moved
. !cP33017 out or Ine surveillance requirement. 'his l information is procedural in nature and is not consistent with the level of detail in NUREG 1431. The information is being moved to the Bases for ITS SR 3.3.3.2.
l CPSESDescription ofChanges to CTS 3N.6 14 1/29M9
CHANGE NU)BER -IGHC DESCRIPTION 12-07 M Not applicable to CPSES. See conversion comparison table
- (enclosure 38).
M
- --- . A a,- - CP 3.3 017
~
- 3. ; M ,> . n ~
- 1. M d j H L ~. ~ ( *e ~ ~ ~ 11 .
9 79%BbMWillle entjugggglOttatirg3tW4tj!d;toltuppgdtEpost i accident 3mlaterggrlunctjan; J 13-01 LS 17 A new Condition has been added to this specification. This condition describes the Required Action for two hydrogen recolabiners inoperable. Whereas in the current specification LC0 3.0.3 applied. this change allows up to 7 days to restore on hydrogen recombiner to OPERABLE status, based on the availability of the containment Hydrogen Purge System to provide the required safety function. In order to use this action time, the Required Actions require that the hydrogen control function be verified available within 1 hour and once every 12 hours thereafter. This administrative verification will assure that the hydrogen purge system is capable of performing the safety function if an event occurs. Also, the bases for operation of the recombiners indicates that if a design basis event occurs, i approximately [8 days] would elapse before the containment ' atmosphere approached the lower explosive limit for c , hydrogen. It is therefore reasonable to assume that the inoperability of two hydrogen recombiners will not , significantly jeopardize the capability of the facility to respond to a design basis event. This change is consistent 4 with NUREG 1431. 13 02 LS 18 The current surveillance requirement to perform a hydrogen recombiner functional test every 6 months is revised to every i i~ 18 months consistent with NUREG 1431. This change is l considered acceptable due to the redundancy and proven high j reliability of the system. Hydrogen recombiner operating i experience has shown that functional test failures are rare. } In addition, the fully redundant and independent hydrogen purge system provides an alternate, and equally effective, j method of controlling hydrogen. The proposed change is in . accordance with NUREG-1366. " Improvement to Technical l Specification Requirements" and NUREG 1431. I 13 03 LG Descriptive information regarding the current j hydrogen recombiner surveillances is moved into the 0 3.6.8 2 bases. CIE233*gggtJjlCJpegife"sicesPIAnet ctiterialfoShid000tfGrecombjnerltest.jj}glH)lta_telpf CPSES Description of Changes to CTS 3N.6 15 1n9/99
CONVERSION COMPARISON TACLE - CURRENT TS 3/4 6 . Page 11 cr 12 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK. WOLF CREEK CALLAWAY 12-02 The MODE of applicability for the hydrogen monitors is Yes Yes No - CTS Hydrogen No - CTS Hydrogen M extended to MODE 3. monitoring monitoring requirements are requirements are not in this section not in this section 12-03 The action is revised to require a special report to be Yes Yes No - CTS Hydrogen No - CTS Hydrogen LS 15 submitted with 14 days in lieu of being in HOT STANDBY monitoring monitoring within 6 hours, if one train of hydrogen monitoring cannot requirements are requih1!aents are be restored to operable within 30 days. not ir this section not in this section i 12-04 Adds the requirement to be in HOT SHUTDOWN within 12 hours Yes Yes No - CTS Hydrogen No - CTS Hydrogen M if both trains of hydrogen monitoring are inoperable and monitoring monitoring one train was not restored withiu 72 hours. requirements are requirements are . not in this section not in this section ! 12-05 ";;i;;; th; 7. ,.v,.. i of th; -; cni?L.~ t; gif; ; Ves41A M ";
. C": :.,dre.. Ne- [
ifr-46 C"J:: t C^2.!=T!:": fra 02 Cy; on ; ;t;,,,.. d h;u t; mentter4"g GM (3.3) i
,,.~- g r [02 t y;]. "M . - , . . - . . . . . - Itydre Q 12-05(3. i) not 9 thi; x; tic . gen ,
M M eM"5 ,
.-,,1. - .f. ;r;
.;t i ,thi; x;ti;n N E 12 06 The details provided for performina the#Tsen50rduodul6 Yes Yes No - CTS Hydrogen b ]
LG @librationC"J:IL0^2_I= TIC"]}emoveut~, vi 6ne monitoring swveisiom.c m uni - .6. ene imormation is moved to the requirements are [ Bases. not in this section CTS Hydrogen monitoring requirements are l not in this section , i 12-07 A new SR is added for DCPP requiring a CHANNEL CHECK every Yes No SR already in No - CTS Hydrogen No - CTS Hydrogen ' M 31 days for the hydrogen analyzer monitors. CTS. monitoring monitoring requirements are requirements are
~ not in this section not in this section 12;M Maurve11]anced sibMpas!Idolkte;tpetfpreAChannd MogAlreadyiin, CTS: Yes No.6Already2tg \
( CP-3'3-01 l M G4Mlptfon_ onithe2ftpi!Logettsopttottchlu!nela x styleasteyery CTS; . tied MtsellrainCIS, N I CPSES Conversion Comparison Table - CTS 3N.6 1/29M9 ,
1 ADDITIONAL INFORMATION COVER SHEET l . ADDITIONAL INFORMATION NO: Q 3.4.11-4 APPLICABILITY: CA, CP, DC, WC 1 REQUEST Change 4-09 LS-36, Difference 3.4-47, Change 3-04 and Difference 3.4-31 Comment: WOG-87 has not yet become a TSTF. FLOG Response (original): As discussed during a telecon with NRC Staff on July 30,1998, I the above references to DOC 3-04 and JFD 3.4-31 apply to NRC-approved traveler TSTF-87 and were not intended to be questioned here. Additional changes have recently been added per Revision 2 of WOG-87 and are included in the attached pages below. The addition of the Note to the block valve Action Statement is considered to be administrative in nature as it reflects I current plant practice. WOG-87, Revision 2, has been approved by the TSTF group and is i L expected to be submitted to the NRC expeditiously. Given the nature of the Notes added to ; the PORV b!ock valve Required Actions and Surveillance Requirement, the FLOG continues to ! pursue the changes proposed by this traveler. l FLOG Response (supplement): WOG-87, Rev. 2 was approved by the TSTF and designated ) as TSTF-309. As discussed with the NRC sta4 on January 19,1999, the NRC agreed to approve TSTF-309 for the FLOG with a clarifying Bases change conceming placing the PORV(s)in manual control. ATTACHED PAGES: Attachment 10, CTS 3/4.4 -ITS 3.4 Enci5B B 3.4-53 I i
1 Pressurizer PORVs b B 3.4.11
. BASES .
1 i reasonable, based on challenges to the PORVs during this time l period, and provide the operator adequate time to correct the i situation. If the inoperable valve cannot be restored to OPERABLE l status, it must be isolated within the specified time. Because l there is at least one PORV that remains OPERABLE, an l additional 72 hours is provided to restore the inoperable PORV to OPERABLE status. If the PORV cannot be restored 0 3.4.11-3 t. within this additional time, the plant must be brought to e Mi in J.ich th; LOO d;;; act ;pply, C__ ,CC
% 2lL4 H 1il M ll0ll @ lit!C F y g[ N as required byConditionD.
C.1 and C.2 If one block valve is inoperable. then it is necessary to either I restore the block valve to OPERABLE status within the Completion ; Time of 1 hour or place the associated PORV in manual control. The prime importance for the capability to close the block valve is to isolate a stuck open PORV. Therefore, if the block valve cannot be restored to OPERABLE status within 1 hour, the Required Action is to place the PORV in manual control to preclude its automatic opening for an overpressure event and to avoid the potential for a stuck open PORV at a time that the block valve is inoperable. The Completion Time of 1 hour is reasonable. based on the small potential for challenges to the system during this time period, and provides the operator time to correct the situation. Because at least one PORV remains OPERABLE, the operator is permitted a Completion Time of'72 hours to restore the inoperable block valve to OPERABLE status. The time allowed to restore the block' valve is based upon the Completion Time for restoring an inoperable PORV in Condition B, since the PORVs are agnotibe capable of mitigating an nrpr;;sur; event 10ggggop_emble blgK Jan ple;;d in =nal catr:1. If the block va' ve is restored within the Completion Time of 72 hours, the power will be restored and the PORY restored to OPERABLE status. If it cannot be restored within this additional time, the plant must be brought to ressurmaammenhmMemn
- s%m ( ; "00 in J.ich th; LCO de;; at apply, ::q
.:; L >17 7 as required by Condition D. 3 4 11-4
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tuteenseneimmamannaramamenaltattmstmme i i (continued) i- < CPSESMark-up ofNUREG-1431 Bases -ITS3.4 B 3.4-S3 1/29M9 1
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: CP 3.4-005 (new) APPLICABILITY: CP REQUEST: The BASES changes provided in this item are changes which incorperate current CPSES licensing or design basis information, clarify the STS BASES or provide additional information to more precisely describe the BASES and, as such, cannot be considered changes that could create an unreviewed safety question. l ATTACHED PAGES: Attachmont 10, CTS 3/4.4 - ITS 3.4 EnciSA 3.4-26 Deletes the word " Condition" from SR Note that was inadvertently not deleted in a previous change. Enci5B B 3.4-4 Corrected " Condition C" to be " Condition A" B 3.4-8 Corrected "LCO 3,1,9" to be "LCO 3.1.8" B 3.4-18 Clarified the discussion of the loss of RCP transient analysis B 3.4-32 Revised discussion of natural circulation to be consistent with the ! CPSES design , B 3.4-45 Revised discussion of pressurizer safety valve design basis to be consistent with the CPSES design B 3.4-73 Revised discussion of SLB dose consequences to be consistent ; with the CPSES design ! B 3.4-77 Editorial revision to change "Section 3" to "Section 3.6B" l B 3.4-83 included discussion of an exception to leak testing of RHR valves to be consistent with the specification B 3.4-83 & 84 Revised discussion of the design basis the RHR interlocks to remove unnecessary detail.
Pressurizer PORVs 3.4.11 1 l I l CONDITION REQUIRED ACTION COMPLETION TIME G. Required Action and immettetjf ) associated Completion 6 g i Time of Condition F not N o.3,4,11 3 ; met. AE l G.421 Be in MODE 3. 6 hours I l bNQ l l 1 G.232 Sc ir. "00C 4. J:cica 12 hours b ~.M 3 5 Belin MODEI4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY
- SR 3.4.11.1 - - - - -
NOTES - - - - - - - - - - l 12Not required to be met-peff_ogned with block
- 4314f*
valve closed in accordance with the Required Action oQ.=g"his1L.C0J&i S cr E. j 3.4 47 Q.3.4.11 4 l 2E0!j],y;t!!gigdMbt5perfgggdlEHLMSJ13
'N...................................... @E I
" ~ ~
Perform a complete cycle of each block valve. 92 days
.u -, -nua , - --,-,, ma 3.4-47 Q.3.4.11-4 l
9MillM!PABESii l i 'uma ES~$WR! L O!052eDBMBRORGiltfotlNR16sitaa ; i amm
--ma*ght-w. -~: :syw2t mtg l SR 3.4.11.2 Perform a complete cycle of each PORV. 1.8 months 68$
l CPSESMark-up ofNUREG-1431 -ITS3.4 3.4-26 H2989
i RCS Pressure. Temperature, and Flow DNB L1;;1ts B 3.4.1 BASES reduced, as required by Required Action B.1, to restore DNB margin and eHeinete he potential for violation of the accident analysis bounds . . 1 The 2 hour Completion Time for restoration of the parameters provides sufficient time to adjust plant parameters, to determine the cause for the off normal condition, and to restore the readings within limits, and is based on plant operating experience. 53 TMs:condst1EtelocHfD4WXnoteithatistates that;this + condition;10mlyzappupable:after:axesecng;ssamafter? a refue11os;ostageGSMs3nppucab1.1.ttssicenststent':'with3he . requirogatippunC9:eGIRMiUIL4aTheIlmrpose:otithis corKHtten;Etol4eMile#pstructions1phould;SRf3?4:1& notbe completalgtWecaprAIKAg@g3helin1M6&pouetascensioD followfasWERlbtMarRetsam3f2fataramason; SRI 8iMAHEREIMSBMBIMERelMdiB38883@gegand umemmmxmawmmmmtweetnenminrenen repennungsgegBM88MBUtm31Rdtl88Dniactmtyws
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CPSESMark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-4 1/29/99 t j,
W 3-
' RCS Minimum Temperature for Criticality B 3.4.2 BASES-power that either assumes the failure of, or presents a challenge to, the integrity of a fission product barrier.
~
. All low power safety analyses assume. initial RCS loop temperatures e , 1: ? d ' - L s ;; he HZP temperature of 547E*F(Ref.1). The minimum temperature for criticality limitation provides.a small band, 6*F for critical operation . below HZP. This band allows critical operation below HZP during plant startup.and does not adversely affect any safety analyses since the MTC is not significantly affected by the small temperature difference between HZP and the minimum temperature for criticality. l The RCS minimum temperature for criticality satisfies Criterion 2 of th; %"C "clicy St;t;a..; IgCSJ$DQ(CH2M1R. LCO Compliance with the LC0 ensures that the reactor will not be made or maintained critical (k,y a 1.0) et-e-with;arcoperatingloop temperature less than a small band below the HZP temperature, which is assumed in the safety analysis. Failure to meet the a requirements of this LC0 may produce initial conditions inconsistent with the initial conditions assumed in the safety - I analysis.
. APPLICABILITY- In MODE 1 and MODE 2 with k,y a 1.0, LC0 3.4.2 is applicable since the reactor can only be critical .(k,y a 1.0) in these MODES.
7
-The special test exception of LC0 3.1. " MODE 2 CP 3.4 005 PHYSICS TESTS Exceptions." permits PHYSI S to be performed at s 5% RTP with RCS loop average. temperatures slightly lower than normally allowed so that fundamental nuclear characteristics of the core can be verified. In order for nuclear characteristics to be accurately measured, it may be necessary to operate outside the normal restrictions of this LCO. <
For example, to measure the MTC at beginning of cycle, it is j necessary to allow RCS loop average- temperatures to fall below T,,,w, which may cause RCS loop average temperatures to fall l below the temperature limit of this LCO. i t l (continued) l CPSESMark-up ofNUREG-1431 Bases -ITS3.4 B 3.4-8 ^ U29/99
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l ! RCS Loops-H0DE 5. Loops Filled L B 3.4.7 B 3.4 REACTOR COOLANT SYSTEM (RCS) ) B 3.4.7- RCS Loops-MODE 5, Loops Filled ! BASES l i BACKGROUND In MODE 5 with the RCS loops filled, the primary function of the ! reactor coolant is the removal of decay heat and transfer otthis l heat either to the steam snarator (SG) secondary side coolant ! r tne cv.gu-m. cooling wa vig,natp41RLM4C"fKHR) via the residual heat removal heat exchangers. While the l princ y : : #aa darav heat removal is via the RHR System, the i SGs f.?'r'~ 71;;;jf;re saecf ~' :: haricun means for l l redundancy.^J'~"Ythoughfthe
- Even Sisv,ggQnot exag,,g, wuce H ;
steam in this H0DE, tney are capable of )eing a neat sink due to i their large contained volume of secondary water. As long as the SG secondary side water is at a lower temperature than the l reactor coolant, heat transfer will occur. The rate of heat transfer is directly proportional to the temperature difference. 1 The secondary function of the reactor coolant is to act as ) a carrier for soluble neutron poison, boric acid. CP 3. 005 ) _Icapgl$M$g1Lf3lKggitofschievelatidipaintain; natural c1tculgglcgiggageggggahenJ2 ply 1RgMthelpbijjtEofAthe Santommenglpimlpgramew.11tylto;gessurgeIand; control l PrpssugigggggiggggggggDGtoMsRGhpi<1gRsEynsure i ist r getN>l In MODE 5 with RCS loops filled, the reactor coolant is circulated by means of two RHR loops connected to the RCS, each loop containing an RHR heat exchanger, an RHR pump, and appropriate flow and temperature instrumentation for control, protection, and indication. One RHR pump circulates the water through the RCS at a sufficient rate to prevent boric acid stratification. The number of loops in operation can vary to suit the operational needs. The intent of this LC0 is to provide forced flow from at least one RHR loop for decay heat removal and transport. The flow provided by one RHR loop is adequate for decay heat removal. The other intent of this LCO is to require that a second path be available to provide redundancy for heat removal. The LC0 provides for redundant paths of decay heat removal capability. The first path can be an RHR loop that must be OPERABLE and in operation. The second path can be another !. (continued) CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-32 1/2989
Pressurizer Safety Valves
. B 3.4.10 8 3.4 REACTOR COOLANT SYSTEM (RCS)
- B 33.10; Pressurizer Safety Valves -
BASES: BACKGROUND The pressurizer safety valves provide,'in conjunction with the R:metor Protection System, overpressure protection' for the RCS. The pressurizer safety valves are totally enclosed pop type, spring loaded, self actuated valves with. backpressure
-compensation. The safety valves are designed to prevent the system pressure from exceeding the system Safety Limit (SL),
23 psig, which is 110% of the design pressure.
-Because the safety valves are totally enclosed and self-
-actuating, they are considered independent components. The
' relief; capacity for each valve 300A004201000 lb/hr atJ485'psg ple23Egggggggg, is based on postulated overpressur transient conditions resultina from a enanlete inst af .
5 % % 6 M yIOppr.St M Q h tig] g gj g g CP 3.4 005 cgBgul ~ ' . ilEttpiMWfdAR3 team 84R . . . Makesjare O mun s rate into the pressurizer, which specifies the minimum relief capacity for the safety valves gd6TJgtpag tlgtlyingstg. 'The discharge flow from the pressurizer safety j valves is directed to the pressurizer relief tank. This j
' discharge flow is indicated by an increase in temperature 1 downstream of the' pressurizer safety valves or increase in the l pressurizer relief tank temperature or level.
Overpressure protection is required in MODES 1, 2, 3, 4, and 5: however, in MODE 4, with one or more RCS cold leg temperatures j s 075 3*F and MODE 5 and MODE 6 with the reactor vessel head j' on, overpressure protection is provided by operating procedures and by meeting the requirements of LCO 3.4.12. " Low Temperature Overpressure Protection (LTOP) System." The upper and lower pressure limits are based on the i It . tolerance requirement (Ref.1) for lifting pressures above 1000 psig. The lift setting is for the ambient conditions 3 tit.!g M6fggitg3 associated with MODES 1, 2, and 3. This requires either that the valves be set hot or that'a correlation between hot and cold settings be established. The pressurizer safety valves are part of the primary success path and mitigate the effects of postulated accidents. OPERABILITY of the safety valves ensures that the RCS pressure will be limited to 110% of design pressure. l CPSESMart-ap ofNUREG-1431 Bases ^-ITS 3.4 B 3.4-45 ' 1/2939
RCS Operational LEAKAGE B 3.4.13 BASES (continued) APPLICABLE- .Except for primary to secondary LEAKAGE. the safety analyses SAFETY ANALYSES do not address operational LEAKAGE. However, other operational LEAKAGE is related to the safety analyses for LOCA: the amount of leakage can affect the probability of such an event. The safety analysis for an event resulting in steam discharge to the ; atmosphere assumes a 1 gpu primary to secondary LEAKAGE as the initial condition. Primary to' secondary LEAKAGE is a factor in the dose releases outside containment resulting from a steam line break (SLB)
. accident. To a lesser extent, other accidents or transients involve secondary steam release to the atmosphere, such as a steam generator tube rupture (SGTR). The leakage contaminates the secondary fluid.
The FSAR-(Ref. 3) analysis for SGTR assumes the the;jsecondary ; fluidlis~2elehsed30!thei' atmosphere:via;the? atmospheric; relief valvesh$htRaffected $ teas; generator.HThislyalvelis; assumed:to faillto rt}csRMhtteWeseleontinueslugtilitheiteactorloperators closeithelgencidedMgEyalveK; atai=ted xsadery fluid is caly bri; fly ;1Gxd vi; =f;ty v;1v;; ad th; =jerity i: st;.a d t; th; esden;;r. The 1 gpm primary to secondary LEAKAGE is relatively inconsequential. x The4L" i; r;re li;;itia; f;r ;it; redi; tier, relasts. The safety analysis for the SLB accident assumes 1 gpm primary to secondary LEAKAGE in one generator as an initial condition. The dose consequences resulting from the S R accident arosewwitnin 1 the limits definad in 1a re" 100iWTC1 ;i "M Cyagp.Qy _
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The RCS operational LEAKAGE satisfies Criterion 2 of ..m ....
"clicy St;t;ac,t.190fBEEEMMEKLM i
i 1 :
'LCO RCS operational LEAKAGE shall be limited to: ' '~
- a. Pressure Boundary LEAKAGE 1 l
1 / (continued)
. CPSESMark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-73 in989 l
RCS Operational LEAKAGE
,, B 3.4.13 0 W E5 i 1
SURVEILLANCE SR 3.4.13.1 (continued) REQUIREMENTS h inventory balance, steady state is defined as stable RCS y pressure, temperature .W]gg3gMi3M(ggggg, 0 3*4*13 4 1 power level, pressurizer and makeup tank levels, makeup and
- jl 1etdown, and RCP seal injection and return flows. An early. l warning of pressure boundary LEAKAGE or unidentified LEAKAGE is provided by the automatic systems that monitor the containment atmosphere radioactivity and the containment sump level. It
. should be noted that LEAKAGE past seals and gaskets is not pressure boundary LEAKAGE. These leakage detection systems are s xified in LCO 3.4.15, "RCS Leakage Detection Instrumentation."
The 72 hour Frequency is a reasonable interval to trend LEAKAGE and recognizes the importance of early leakage detection in the geyentionofaccyents..............,....,.....7.,..
, ,.g.
~s t;tc g r;t hr.. When:nonisteady[ state"operatjonprecludes
. surveinace:pettornateenthelsurvenlancelshouldibe Performed.@RtessonaldeltimeJperiod 'ccamensurateNith]the satve11hece3pefommendsosthgange:4teady:stateroperAlan o.3.4.13 4 batbeesuklamasembilmEstashtaberET@hoorsJnmi
#MpsedMRKEEbMbrWNWetmumeel !!!!sIMif:eesee3!teMH5fted .
ae % - SR 3.4.13.2 This SR provides the means necessary to determine SG OPERABILITY s in an operational MODE. The requirement to demonstrate SG tube integrity in accordance with the Steam Generator Tube-
- Surveillance Program emphasizes the importance of SG tube integrity,' even though this Surveillance cannot be performed at normal operating conditions. Ib1pisRfgRMBM3lpg53ptEtjd dW Neti M arB EREf W 3bftthd W
W. , REFERENCES 1. .10CFR50,'AppendixA,GDC(Jand30.
- 2. Regulatory Guide 1.45, May 1973.
]~
- 3. FSAR, Section 15.
_ CP 3.4 005 ~- 5j NJEgliB9EElfelGIRSSEN6VepbeGMijg 62 1HER3OU CPSESMark-up ofNUREG-1431 Bases -ITS3.4 B 3.4-77 129/99
RCS PIV Leakage B 3.4.14 ! L , E L BASES I SURVEILLANCE' SR 3.4.14.1 (continued) '
' REQUIREMENTS
. frequency allowed by the American Society of Mechanical Engineers -
(ASME) Code. Section XI (Ref. 7), and is based on the need to - perform such surveillances under the conditions that apply during - an outage and'the potential for an unplanned transient .if the Surveillance were performed with the reactor at power. ; In addition, testing must be performed once after the checkjvalve has been opened. by flow or exercised to ensure tight reseating, j: PIVs disturbed in the performance of this Surveillance should also ; be tested unless documentation shows that an infinite testing loop cannot practically be. avoided. Testing must be performed within , 24 hours after the checdgvalve has been reseated. Within 24 hours is a reasonable and practical time limit for performing this test after opening or reseating a check. valve. The leakage limit is to be met at the RCS pressure associated with j MODES 1 and 2. This permits leakage testing at high differential pressures with stable conditions not possible in the MODES with lower pressures.. l Entry into MODES 3 and 4 is allowed to establish the necessary differential pressures and stable conditions to allow for performance of this Surveillance. The Note that allows this
' provision is complementary to the Frequency of prior to entry.into MODE 2 whenever the unit has been in MODE 5 for 7 days or more, if leakage testing has ~not rformed in the
, 4sgsurve be performed on the RHR System when the RtR System is aligned to required to the RCS in the shutdown cooling mode of operation. PIVs contained in the RFR shutdown cooling flow path must be leakage rate tested after RHR is secured and stable unit conditions and the necessary differential pressures are established.
y .; . . = . 7..,,,7 . 3 +j,pgttGRWalWes7300g e . . .y . 4- 11 . .q , ..
. ; .f . n ., f . gg
...w v. / /.: ." y wa e. m & < .w x v w ' .o w iw : M Kg D D +' . . kdd'I*u, t .: i h L : .If 9 .:.M SR 3.4.14.2 ;.d f." 3.4.14.3 VEffy1EEEEEl3hE3RR33W 11$edocks3ts;0fERABLJ emeJ!GREGE3l tag!mran11P= didzeMbeRsystes (continued)
. CPSESMark-ap ofNUREG-1431 Bases -ITS 3.4 B 3.4-83 1/2989
- 4. -_ _ _ _ _ _ _ _ _ . _ _ _ - __ . . _ . _ _ _
RCS PIV Leakage , B 3.4.14 i BASES i SURVEILLANCE SmaiE m (continued) )' REQUIREMENTS
~ i op3gd M4llpapctles]ggiggesqRe[ggelspi@ejg ~ 3 *"'
42&N1mfaans*statsesmThwsgess! Int;ensurssithe MWM,1W30plielexcleplql$13llL4he[RJ1t}ief I l vahe$35@EN#Rl*K4heDFJetpfgegencOsihasedianithe2need temeCfRM18NFAnleRimme3slericorWR1ons11batlapplyIduttnga RIMtfopB4981!gJtG8;mnhfrequencyListelsolacceptable; based;on cop $1degglicql(i$heldesigggg11 ability 1{and :confirirji ig,*opetating egettenJ!!!tD!!!aluondpment; j Th;;; 2; ;r; ;;. edified by .";tc; ;11mir,; the J"', out;;1;;ur; fa ctier, t; be di;;bl;d ThjslSRIis potiapplicable'When using the i Rm System suction relief valves for cold overpressure protection l
.in accordance with SR 3.4.12.7. ,
l1 REFERENCES 1. 10 CFR 50.2.
- 2. 10 CFR 50.55a(c).
- 3. 10 CFR 50, Appendix A, Section V. GDC 55.
- 4. WASH-1400 (NUREG 75/014), Appendix V, October 1975.
- 5. NUREG 0677, May 1980.
- 6. T_g;hnhridal
- 7. ASME, Boiler and Pressure Vessel Code, Section XI.
- 8. 10 CFR 50.55a(g).
CPSESMark-up ofNUREG-1431 Bases -ITS3.4 B 3,4-84 U29/99
l~ ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: CP-3.5-005 APPLICABILITY: CP REQUEST: This change revises CTS 3.5.2 and corresponding ITS 3.5.2 to reflect the recently approved CPSES License Amendment 62/48 which extended the allowed outage time, from 72 hours to 7 days, for one ECCS train made inoperable by an inre erable centrifugal charging pump. The 7 day allowed outage time is based on a risk-informed assessment to ( manage the risk associated with the equipment in accordance with the Configuration Risk Management Program which is a new program that is being added to ITS 5.5.18. In addition, l CTS 3.1.2.4, which is being relocated to the TRM per DOC 9-01-R, is revised to include the 7 l day AOT. ATTACHED PAGES: l Attachment 7 CTS -3/4.1 ITS - 3.1 Enci 2 3/4.1-10 Attachment 11 CTS -3/4.5 ITS - 3.5 ! Enci2 3/4.5-3 Enci 3A 5 Enci3B 4 Enci5A 3.5-5 Enci5B B 3.5-16 and B 3.5-17
- Encl 6A 2 Enci 6B 1 ,
Attachment 18 CTS - 6.0 ITS - 5.0 1 Enci2 6-7 Enci 3A 4a Enci 3B Sa Enci5A 5.0-29 Encl 6A 2 l l (
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- (RCS) cold legs is less than or equal to 350*F, a maximum of two charging pumps s ong
! shall be OPEMBEE capable;ofl1njectDyyte'the3CSI except when Specification l 3.4.8.3 is not applicable. When required, one chargingAL.A pump shall be demonstrated inoperable'__at least once____ sum S J. Per og. ,s u,. .._ L,.. w .ww.
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-. . ~ . . - . ~. .- .. . - . . - .~ .-.- -- - .-
l i EMERGENCY CORE COOLING SYSTEMS 3.4.5.2 ECCS' SUBSYSTEMS T _ > 350*F
-LIMITED CONDITION FOR OPERATION ,
1 3.5.2 Two irdacricat Emergency Core Cooling System (ECCS) subsy;ts; traigs shall. 48 # #9 1
. be OPERABLE with cah sub;y;tc; a,,,,r.i;;d of; ,
- c. 0.c 0 POLE antrifug:1 ch;rging p-7
- b. 0.c 0CPOLE 3;fety injntica p7
- c. 0 c OPCXLE PC hat c=hs;cr.
- d. 0 .c 0EP X LE P C p 5 . erd i i
- c. An OPEPEL . fica pth =pbic of taking suction fic; the refueling water storegc t=k on : Rfety Injection signi =d =tc=ti=11y egning the centain cat ;;;p suction volvc; during the raircul: tion phuc cf spcretion.
se APPLICABILITY: H00ES 1. 2. end 3* #. ACTION: l j Withlone'ECCS; subsystem;r train'iinopetable;becauselohthe _ mwi inopetability;ota centoitugalicharging:pue77pstoreithe inoperable:puuplto10PERMLEIntatus MtRIEJighiarCocibeXat least H0TISTAISBY;Withigithe]ubjtiEhobr.slerid.jrrgM ( 2 21CP A 3.5 005 l within1thefollog!g"6lhoutsj ebg WithoneormoreECCSsubsystemtrainsinoperab1[forfreasons" - 2.as.so N an ---cler - u; =- Ler = , gggggory W l loy egu1D legt3 0!#IsinglelgN R MLE m p 3 tain restore the w,un. inoperable subsystem train (sl to OPERABLE status within 72 hours or be in'at least HOT STANDBY within the next 6 hours and in HOT SHlTTDOWN within the following 6 hours. N
.*The provisions of Specifications 3.0.4 and 4.0.4 are not applicable for entry into N00E 3 for the centrifugal charging pumps and the safety injection pumps declared ; inoperable pursuant to Specification 3.5.3 provided the centrifugal charging pumps and the safety injection pumps are restored to OPERABLE status within 4 hours or d
prior to the temperature of ene-or-more all of the RCS cold legs exceeding 375'F. whichever comes first. 1 # R NOD E 3 Zboth:SIdnjectionific[ paths 7 mart 6telatedibEclosingitM11solatlo!! g2.asm VA1][gy)JESRIO5:.2a30tf21houtsit6! perform 2ResutelTMlatiorWe1VEtestig!per158 fiWEC22
' CPSES Mark-up ofCTS 3N.5 3M S-3 1n989
CHANGE NikBER NSIE DESCRIPTION restoration of equipment after maintenance specify the appropriate post maintenance testing. 2 19- LG Not applicable to CPSES. See Conversion Comparison Table '
-(enclosure 38).
2i20 ff IkgIapp1D$@g30;2SEEJ_ Seed!plersion;Comparisort 0 3.5.5 2 TaMel(eNGeggplaBYJ l 212; e unesteJItbeNQ3303re0sKtece!*1#L . . N
! LjesseAggleigegeeL4s;3ttich;M;thelellowed outage 11senttgall21houtsItoZdays%fotone:ECCS trainialW3nopergNell!y*an',igoperple[centtifugal chargiosmer e i
3-01 LG . Consistent with NUREG-1431 Rev 1, the LC0 is revised to replace the word " subsystem" with the word " train" and the descriptive information in the LCO is moved to i the BASES. The:proposedichangelj s ' consistent;witti 0 3.5.3 1 < NMRC;931035 Miter's1GujdelforitheJestructured I Techgica]LSpecifications'landithelphRosophyloLNUREG; 1.431pEwhLch;ttle1LCO: desetibeslas2siep]y3s?possib]eithe 1#6 WrJ1onarcapab1]ity3EtheisystemZandfelegates ; th!PdgTQ5LeflighetitonstitutesMORERABLEisystasjto,;the l BawaitusfotCtheadeta11sMJd!sticonstitutesfarj OPEMLElsul!sMtenJtraintsuctCasitequited?gupsZheat exchangertagiDogIpathi7Eaginote;approptiate]f discussedMthe]!ases3tlan;gtKLC0KTheseEdetails ateEg! tit!ggtsppryMeJJsurelECCSigPERASILI1Foriththe ECCS3an'petigtpltfl1Jggdedisafety;fuDetjong _ Thettfor6Mhe3tgpesadithangeJegesitoTthelSasetidetajl s thatlaLv)!agggessary3o2prorjdeIgetatfog15 safety wh114NJELhe0Legh 11313pecificRings;tt!e:bstic. iMiL =E$YoGMLt@WningleJERAsnI1TJ whereas there is no technical change associated with the replacement of
- the term " subsystem," " train" better describes that all l parts of the required system ( e.g., piping, instruments, controls etc..) must be operable to support the required safety functions.
3-02 LS 4 Consistent with NUREG 1431 Rev 1 the low temperature overpressure protection limitation on ECCS pumps and related surveillances are moved to improved TS 3.4.12. The prescriptive wording related to pump operability is
- changed to wording specifically addressing the pumps' capability to inject into the RCS. This change is less restrictive on the configuration of the centrifugal i
- charging and safety injection pumps but is acceptable because it is consistent with the cold overpressure analysis requirements and still precludes flow to the RCS.
CPSES Description of Changes to CTS 3N.S S 1fl939
~
~ Page 4 cf 6 CONVERSION COMPARISON TABLE - CURRENT TS 3/4.5
' TECH SPEC CHANGE APPLICABILITY i DIABLO CANYON CONANCHE PEAK WOLF CREEK CALLAWAY NUlBER. DESCRIPTION No - DCPP does not No - CPSES does not Yes Yes 2-19' Moves the requirement that the 18 month verification of automatic ECCS valve actuation and ECCS pop actuation be have this have this ,
LG - performed during shutdown to the Bases. restriction restriction No1.;.Alreadylinj No MAireadylin3 Yes yog { 3.5.54 2d20 Amew,.LC0;1sladded;tq;CIS1,Y4_;5Ao deposedimitationsion g g g g V M Yes lio [lg
%2.1 - ,--- . .s-a g
.{ .
m an ,n aea wn - .anammmm w w an . Yes Yes 3-01 The LCO is revised from " subsystem" to " train" and the in .m LG descriptive information moved to the BASES. Yes Yes Yes ; Low temperature overpressure protection limitation on ECCS Yes 3-02' LS-4 pumps and related surveillances are moved to Section 3.4.12 in the improved TS. The prescriptive wording related to pump operability _is changed to wording specifically addressing i tha pumps' capability to inject into the RCS. ' Yes Yes Yes 3 03 T M LCO 3.5.3 ".;ti;. ; 1 xci pi n ;-fm-.~ti m ,;;d t; the Yes Q-3.5.39 LS-5 BASESr-The completion time for COLD SWTDOW due to CCP > inoperability is increased from 20 to 24 hours. Yes Yes Yes Yes i 3-04 ";; LC^ ;; tic- t.. ; ;hs; i; . /.;;d ; :' tM d;x-;ptin Q-3.5.3 ' 1 LG 173 _ti;r. ,..;..d :: the i'!,ES. GM4d63t_GlismJE9fjevMeq A prehetnoteEeukwenbaNAJIKKassaggLi!eJ88kREERd4 maintamT,,,saseI* AlotensLaiteressJwetassovel i methodsgTheseidstg31sterpiluoundLtg the1_TS;8aagsd 1 Yes Yes Yes i 3 05 The requirement to sthit a Special Report within 90 days of Yes TR-2 an ECCS actuation arsi injection event is deleted.' Yes Yes Yes Yes ! 3-06 A note is added to tha LCO that clarifies that an RIR A subsystem *s ECCS function is OPERABLE if it is capable of i being manuelly realigrw_J to the ECCS mode of operation. l I CPSES Conversion Comparison Tame - CTS 3N.5 1/29/99 : i' _m.. . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ __ _ . _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ __ .__ _ _ __ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . .
ECCS-Operating 3.5.2 ACTIONS
. CONDITION REQUIRED ACTION COMPLETION TIME
[ A2 03l(((tgigljnepej $)e. AM ll!astore;[pumpit[0P9tAgt.Ej 71 days hElfgB) M ith( status] 3.5-7 M ljty M g ' CP 3.5 005 CR!$tigiga]Icharging j AB One or more traine - y .1 Restore train (s) to 72 hours inonarabWJtea_ sons" OPERABLE status. (other;than;one - i inoperablecentrjifugal charging pump. J AND At least 100% of the ECCS flow equivalent to a single OPERABLE ECCS train available, l BCh equired Action and i 1 Be in H0DE 3. 6 hours associated Completion Time not met. AND 1, 2 Be in H00E 4. 12 hours CPSES Mark-up ofNUREG-1431 -ITS 3.5 3.S-S 129/99
ECCS - Operating B 3.5.2
-BASES APPLICABILITY A; indisted in Ot: 2. eper;tien in "00: 3 with ECCS tr;in; (continued)- i;ler;d ir.egrebi;; par;=nt t; LCO 3.4.t2 "L;; T. gr;tura l 0 ; rpr; n;r; Pr;t uti ; CLT0") Sy;t s ." i; ra;; n;ry for pl = t; with a LT0" ;r;in; te gr;tur; ;t er n=r th; ."00: 3 bandry t g r;tur; cf 350*T. LC0 3.4.12 requir;; th;t ;;rt;ir, p;;p; b; reaired ir.egrebic et ad below the LT0" rein; ti g r;tura. 'l ten . i thi; to g.eture i; et or-mar the "00: 3 b; airy to gr;ture.
ti ; i; ;xid t; TGter; th; in;p;r bi; p;;p; t; 0"E"XLE ; tot;;.
.In MODES 5 and 6. plant conditions are such that the probability of !
an event requiring ECCS injection is extremely low. Core cooling requirements in MODE 5 are addressed by LC0 3.4.7. "RCS Loops-MODE 5. Loops Filled." and LC0 3.4.8. "RCS Loops-MODE 5
- Loops Not Filled." MODE 6 core cooling requirements are addressed i by LCO 3.9.5. " Residual Heat Removal (RHR) and Coolant Circulation-High Water Level." and LC0 3.9.6. " Residual Heat i Removal (RHR) and Coolant Circulation-Low Water Level."
r
~ ACTIONS 83 With onOenttifugalIcharging: pump!JCCP)ldnoperab]elthe: inoperable I
- CCPinustibetreturned3910PERABLEist.atus'itith_inZdaysf1TheJJiday alloweOutagnitteeltsitesed;onzaltigI1nformed
- assessment:tg manageithaltistasaciatedfytthatt!emipment;jOccordanceMith ttMWonEgoistio[It1gmagemmt:Ptegram;andl1G M_]$MWl@MjiODM2 CP 3.5 005 L1 win n- a-r +-a ae innnarab JIeasons70thbr;than'one 3 C1HoperabW1centfffussUtharg13! pump]<ino at least 100% of the ECCS flow equivalent to a single urtMAt3Lt ECCS train available, the ir. operable components must be returned to OPERABLE status within 72 hours. The 72 hour Completion Time is based on an NRC reliability evaluation (Ref. 5) and is a reasonable time for repair of many ECCS components.
An ECCS train is inoperable if it is not capable of delivering design flow to the RCS. Individual components are inoperable if l (continued) CPSESMark-up ofNUREG-1431 Bases -ITS3.5 - B 3.5-16 1/29/99
A ECCS-Operating B 3.5.2 BASES ACTIONS 17 continued) D intent of this Condition is to maintain a combination of equipment such that 100% of the ECCS flow equivalent to a single OPERABLE ECCS train remains available. This allows increased flexibility in plant operations under circumstances when components in opposite trains are inoperable. An event accompanied by a loss of offsite power and the failure of an EDG can disable one ECCS train until powr is restored. A reliability analysis (Ref. 5) has shown that the impact of having { one full ECCS train inoperable is sufficiently small to justify ' continued operation for 72 hours. Reference 6 describes situations in which one component, such as an , RHR crossover valve, can disable both ECCS trains. With one or more component (s) inoperable such that 100% of the flow equivalent to a single OPERABLE ECCS train is not available, the facility is in a condition outside the accident analysis. Therefore. LCO 3.0.3 must be immediately entered. : 1 and E 2 If the inoperable trains cannot be returned to OPERABLE status i within the associated Completion Time, the plant must be brought to a H0DE in which the LCO does not apply. To achieve this status, the plant must be brought to MODE 3 within 6 hours and MODE 4 e within 12 hours. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems. I SURVEILLANCE SR 3.5.2.1
~
REQUIREMENTS Verification of proper valve position ensures that the flow path from the ECCS pumps to the RCS is maintained. Hisalignment of j these valves could render both ECCS trains inoperable. Securing 1 these valves in position by removal of power-or by kcy bcking;a control [ board;switel) in the correct position ensures that they [ cannot change position as a result of an active failure or be (continued) CPSESMark-up ofNUREG-1431 Bases -ITS 3.5 B 3.5-17 1/29/99
CHANGE NUPBER JUSTIFICATION 3.5 6 SR 3.5.3.1 Note (An RHR train may be considered OPERABLE during alignment and_ operation for decay heat removal. if capable of being realigned to the ECCS mode of operation) is moved to the LCO per traveler TSTF-90. The Note is more appropriately placed into the LCO because it defines the intended capability of the ECCS equipment. v - 3.5 7 %t md.MteRtt! alt.L%Ej5]IJ5Ltoingfiscjt,M]yhG- CP 3.5 005 Licens@geltLM?iGR/J8MIMh4110testat##ge i timenfrut;zz1hogggmenMAr2MEntratn3 male inoperelel#Eanlinoperabp3entrifwatchasing:pungrr,q j 3.5 8- Hoves the Notes from the " APPLICABILITY" for ITS,3.5.2 to the ;
"LC0". Also revises the wording in Note 2 from " declared i I
inoperable" to "made incapable of injecting". The wording change makes the note consistent with the wording used in LC0 3.4.12. These changes are consistent with TSTF-153. 3.5 9 .Not Applicable to CPSES. See Conversion Comparison Table f (enclosure 68). l l I i l CPSESDifJerencesfrom NUREG-1431 -ITS3.S 2 U29/99
CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431, SECTION 3J5 Page 1 Ef 1: TECH SPEC CHANGE APPLICABILITY NLDBER DESCRIPTION DIABLO CANYON COMANCHE PEAK' WOLF CREEK CALUWAY 3.5 Replaced
- pressurizer pressure" with 'RCS pressure." Yes Yes Yes Yes 3.5-2 The Completion Time of LCO 3.5.1. CONDITION B is changed No - Not part of No - Not part of Yes - License Yes - Current TS from i hour to 24 hours to reflect the current TS. current TS current TS Amendment pending. per OL Amenchent No. 91.
3.5 3 Adds the word " mechanical" with regard to throttle valve Yes Yes Yes Yes position stop consistent with the current TS. 3.5-4 T'.i; c' ...,. .~. ;;;; the "C." ;cel =n ;;; tion f!;w Cgiction Ves N4 Ves-N4 P.; LOO 0.5.5 i; F.; LOO 0.5.5 i;- Ti;c 'r;; 4 t; 72 he;.r;.. with ; acu Cd verificetion that not g licatic. n;t w lic; tic.
;t ic;;t 1000 cf th; ;;; d c h ,;n; fica . in;' NA M
;;;ii;bic. htM 3.5-5 Deleted reference to centrifugal charging pump discharge Yes Yes No Not part of No Not part of header pressure to reflect current TS. current TS current TS 3.5-6 SR 3.5.3.1 Note is moved to the LCO per traveler TSTF-90. Yes Yes Yes Yes 3.57 /6;.;cd Updates;the CPSES 1TS 1 tqirefl.ggLrecently_
t approved NMNo NMYes NMNo NMgg r Lice;iseJaendmentJ4L48JshichDter$6heiallguet(outage t.jaetifron3datsit01dtysi@lr hEEJSitreistande i=--ele by:-antitioperable:centrifunalr 0- ._ ,_,, f CP-3.5-0 3.5-8 Noves the Notes from the
- APPLICABILITY" to the "LCO*. Also- No - Not part of Yes Yes Yes I revises the wording in Note 2 from " declared inoperable" to current TS.
"made incapable of injecting".
( 3.5-9 The seal injection / return valves (BGV0198 BGV0202) are No - Not part of No - Not part of Yes Yes ( included in ITS SR 3.5.2.7 since they are included in CTS current TS. current TS. 4.5.2.g.2). CPSES Conversion Comparison Table -ITS3.5 1/29/99
_. __ _.____ . _ _ . . ._ _ . . _ _ _ _ _ - . _ . . _ . ~ _ L l ADMINISTRATIVE CONTROLS l
- 10) Limitations on the annual dose or dose commitment to any member of the pub 11c3pggg@gIs.itg3Reggy] due to 2j'sA, releases of radioactivity and to radiation from uranium fuel -
cycle sources conforming to 40CFR190. i i 1H 'MEREIBI!EggetfitRWIMIManeiluratt 2g;A
,._ ___.__......-.--.n---.-
-" J
- f. # J l TgjJhe;Centguts4302RINBgggpt?b9gran3G5PDrovide$L 2-24 A procedageimagttegg1psmerjassessmantitermanesertheitsst CP 3.5-005
- associategyttsteggagnslageren111ty.5TneIprogramwp11es to:itachngallspec*geesten stemeturestsystems, tor, components foriwittch;aT1*itt@rDtA}cupdDtageline ~hasibeep3p antedL program se!alliittejaseithelfollowingAenentsi riiF2TZEI)17iPmisicositatitheIciantroizand;1mplementation ot:a;Levelinnat:
powerajamrpenegatslfKinformed methodologMTheiassessment shellibelcape]Entj!glanting:.the: applicable: plant configMRtt@l EGiHE.E3IJ)2DEMis1Ml836riMglW8$$essmentlptiodt(enterjngithe;LC( Action 19Eptopla!Lnediact1_vLties; E12"'IEE3EffPtWi switorlportprping:anysses.smentlafterlenterj ng ;the . LC0 ec31on18! camp 1mnmul!getEt!LtoltheiLC0iActjog; E4ENVI4)3EP@sigggMbCR$ttssjgg;ttle3tgeMcGadditional3ctierts3ftpr tiniegarrAguaggtng13!mipmeggg#Eofisetylce2#o!!ditiong enew +:.+ sw summEEg[ggysgg) 131ficar!N ontd.3- 3<: 1: : a e g ue! B RW N 8J ettantly3msgBERERB17]
- g. Containment Leakaoe Rate"Ti aM r rx A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50. Appendix J Option B. as modified by approved exemptions.
This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance Based Containment Leak-Test Program, dated September. 1995" The peak calculated containment internal pressure for the design basis loss of coolant accident, P., is 48.3 psig. The maximum allowable containment leakage rate, L., at P., shall L be 0.10% of containment air weight per day. L Leakage rate acceptance criteria are:
-CPSES' Markup of CTS 6.0 6-7 1/29/99
CHANGE NUPBER EiHC DESCRIPTION 02 19 LS 2 Not applicable to CPSES. See conversion comparison table (enclosure 38). 02 20 A Not applicable to CPSES. See conversion comparison table (enclosure 3B). ) OREN 8 MIappM3ff5BigEjpggggtMgg compattseg wc 5.0-oo4 1 te#183M!m885LM J i 02ip A MMI@_MsiMM(.WWJfMsed;to o 5.2 1 include 3]giccationistatements?Aesoting;thetithe prodsienormmo;2Mi;ogratopplicable:to . theseMdties2JheseIttateamstsloffapplicab1]ity clariffthe!! allowance 1Totisutyeijlancelrequency extensins;anctalleuanceitolpectorm;missedisutvia11ances a Generic: Letter;epio1l;3itsplementation:ofiProgrammetic Controls 3ot AtadiologicaliEffluentilechnical l Specificat M sIa g the RelocatioOf;Detailsiof;RETS:tc the offsiteloose1Calculat M panualiorithe1 rocess; P Control Program",fal]cWed21censeesito:M1ocateithe,. Radiological Effluent 1Technica1JSpecificationszend! establish:the Radioact[M1Etfinents1ControlLProgranUnithe Adm1J11sttatpe1 controls;SectioOfithelechnical SpecificationsEIhis changele[fectjielEjaplements;the
. CTSItequitementEthetiete:relgated:petsener.icitettet 892ETsIh18Ichgselit2considetydIanladministratychange since:theIqangeslerOfLW:ptesentatjgleethodlon}yG This3thange2ts eggsistentiwithiqutEsimiinsteadifMby ISI s ssj 0_2dp LG Notiap@icableitolCPSES7dSee30gvetsj@!comparisoE oc 5.0-oo4 tablexenc19sure3su 02E24 8 lh15IchangeJ@slaiggJprogtanMoDfigutation'Rish c 3.5-00 ManagementiPggr.WJJ62thelTSIM@dZeCtecent)9 amRy3EiES31c_egquendggtJL48]
03 01 A Revises " Routine Reports" section to be consistent with l '~ NUREG 1431. The method for submitting all reports is ~ revised to be in accordance with 10 CFR 50,4. Since this change merely makes the TS consistent with the ; regulations, it is considered administrative. 03 02 A Not applicable to CPSES. See conversion comparison table (enclosure 3B).
. CPSES Description of Changes to CTS 6.0 da H29/99
y w
~
CONVERSION COMPARIS0N TABLE-- CURRENT TS 6.0' ' Page Sa of 8 TECH SPEC CHANGE : APPLICABILITY-NUNBER DESCRIPTION. DIABLO CANYON l CONANCE PEAK WOLF CREEK CALLAWAY.- e222 . Tim. Radioactive,EffluentaApattelatteggranitspeed,te ' yes " Yes- yes yng - A jaciade.clariffcstten.accamaguswAssettasitest;the , 0-5.2 1
-- protisionsACR$AtastMAary applicable,.to these semitvittasi 02 23 DCPP. Administrative,Prggnung_Cli,6,8,4.dgBeckup_NeJm Yes No No po LG fot.neteratuisisJutseengamuralibLanddA4d; - DC-5.0-104 sostajament rel m tsom i
nelastee;f!sr_mm21seneset centrp11es:w;gemtagsgesl3ltgeA4lsgLeeentas f w_- - N 02-24 TidEspengeladelamesAtestunn50effnuntia&Rist ( N-No Yes- No- lll A- NElIBossentM62tgeogtjy;.jppqued] CP-3.5 I 05 p 4,1CERSe 6 m I j 03 The method for sn aitting all reports is revised to be in Yes .Yes Yes Yes A accordance with 10 CFR 50.4 CPSES Conversion Comparison TnNe - CTS 6.0 1)2939
~ .- .. ., .. . .-. ..- - ~ . - - - . . . - . -
~- ,
Programs and Manuals 5.5 l 1 5.5 Programs and Manuals (continued) l l M M ; arl3nclassen; v tme RN JMMal m !a ltj! m i gangesemwassmistrattwe entto1EmuussimRM!!MRGDEmanagegamytthout;pt!arfuRc approva32moviedJnicc.hestEm"not_mixefwEchangelt03he;TS , _ ot;:an;untettegelsafatmentgaEdefigadibC10!CFR;50;59lETRM EhangesID! pile 3pprgiaDfitheIllant]Managet*J A ls panfiauration afsenanaasment? Program *(CRMPH l 5.5 6
]he~_Cppf,jgtSt M ' 6 .~M4EINjdeSlg CP 3.5 005 l procettattget isk ,
assfaMEM tesite ! technica_ Ia!rMitchia cisk;MietalediGig!plaswMtusteEMsta!stelliggraamisha)) ; 1Mlude]$helfolidW1MitimetRG ; 11 Prgyisjgggg[3tglG9 Bin 82ng21ePl991Lta_ Man'Afgleve1073tji poetaamirancesetteesEinfeseentiaMgggstsseissment ; ellDit!BWARReSIEMiBl3B2tM3BABWWEplet gy Pgggit H , . . w. 3 '. n .. . . e q .y .- , s . v , 4 y t-a 7.@2ll0
.e - r., p 1. c . . ~ . n .:. y .
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.. ,.... - _ . _ _ _ - - - m ._-, m ,.
p M .v & R... P & & c.. 'D 2 :t
..mu,.. - - - - -.-- m - _ w . - -e =
. . . . . . _ _ . . _ . . . _ . . . _ . _ , - . . . - , . _ . ~ . . . . . . . .
$0E9 M 51' . PNHMMedETar'EDlH1tlMSfEEBitlSWann4Mun1NPimlMEfarHfitsht canti 919!nt41 QSlitatRB6 3 BangmirJLe;pyrfmind3tElamttreermars2fmo_c1gmpnerationsI113ttat pgg' samation11p_oitstatamunmu CPSESMarkup ofNUREG-1431 -ITS 5.0 5.0-29 1/2989
CHANGE g&BER JUSTIFICATION 5.5-1 These changes revise Section 5.5.4, " Radioactive Effluent Controls i Program," to reflect new 10 CFR Part 20 requirements and NRC letter l dated 7/28/95 (Christopher I. Grimes to Owners Groups). A g ep ;;d trov;1;r is king F;pr;d t; r;' ;;t ch;agc; regired for L"J:!c 0 5.2 1 4431 t; k ;;n:1:t;nt with 100l't Port 20. M*jgggigr;gf:gic LatjedWR1a a ; ism 2MhelMIRillf(Genetic Lettet7mExxmesseltESLs.JggigliamitroggthewM GBIR2151m Mgt;.tentic l 1stteggagemmagsEmalm;ng[ggeseg3mpAg!stLewshlseng adelstepEmmumM!BEHl58LWEREMmlululagfMeles@!artalttw sauew!!sm1113nggasatammigenttp3IM!BassHggeMllaispemtional DextbogEtaggstatettsiawJs3m!derymemenamioicm:2em Theseiti!agges]Mt3ppndefttQliminsterpos_$1)]Econfusicnlor 1mproper L lap]esentatiag!rghe2Eiseolo;cm12clequirements] 5.5 2 This change revises Section 5.5.3 " Post Accident Sampling," to ensure capability to obtain and analyze radioactive " iodines" in lieu of
" gases." This change is consistent with the current TS and plant practices.
5.5 3 This change revises Section 5.5.8. " Inservice Testing Program." to delete
" including applicable supports." This change is consistent with the current TS.
5.5 4 The Containment Leakage Rate Testing Program is added to the improved Technical Specifications (ITS) consistent with the current TS. The Containment Leakage Rate Testing Program is consistent with traveler TSTF 52. 5.5 5 This change revises Section 5.5.13. " Diesel Fuel Oil Testing Program," to be consistent with the current TS. The details of the method applied to this test are discussed in the associated SR 3.8.3.3 Bases. [] 5.5 6 Additional programs are added to the ITS (other than Containment Leakage Rate Testing Program discussed in CN 5.5 4). EThi chanaa adds new Sectinne 6 E.17. " Technical Renoir-* "r"R" notBT5i18D% CP 3.5 005 Mb EicE _,. ., .2&Wr0grgjpo me CPSES TS. A l progras descr n:1on nas Deen auuvu w escribe the licensee control offMs Bg]e icensing basis documents and any changes to them]
- t. This gegr;;;; n ;O,;;; ;; centrol cy ra;;c,0.5M ^
5.5 7 Not applicable to CPSES. See conversion comparison table (enclosure 68). 5.5 8 A sentence is added to Section 5.5.9 ("The provisions of SR 3.0.2 are applicable to the Steam Generator Tube Surveillance Program test frequencies") and Section 5.5.13 ("The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Diesel Fuel Oil Testing Program test frequencies") to provide consistency with current application of these requirements. This is consistent with the use of current TS and alleviates potential confusion in the program descriptions. This change is consistent with traveler TSTF 118. CPSESDWerencesfrom NUREG-H.f1 -ITS5.0 2 H29/99
i ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO:- Q 3.6.3-23 APPLICABILITY: CP, DC REQUEST: DOC 7-10 LS-9 JFD 3.6-13
. CTS 4.6.1.7.2 CTS 4.6.1.7.3 -
CTS 4.6.1.7.4
. CTS 4.6.3.4 STS SR 3.6.3.7 and Associated Bases ITS SR 3.6.3.7 and Associated Bases A Note 'has been added to CTS 4.6.1.7.2,4.6.1.7.3,4.6.1.7.4,4.6.3.4 and STS SR 3.6.3.7 to .l
- clarify that leakage rate testing is not required for containment purge valves with resilient seals when the penetration flow path is isolated by a leak tested blank flange. . The staff position is that the valve would still need to be leak tested since the 10 CFR 50 Appendix J requires both' isolation devices in the containment penetration to be tested except for GDC 57 penetrations.
' in addition, because the CTS does not currently contain this exception, the staff considers this
^ change to be a beyond scope of review item for this conversion, as well as a generic change to the STS.
Comment: Delete this generic change. ,
.. l
~ FLOG response (original): While we recognize that this is a generic change to the STS, the i change was sent to the Westinghouse Owners Group for consideration during their June,1998 meeting. We believe the technical merits of the change should justify rapid approval by the ;
WOG, TSTF and the NRC. This change is of sufficent value in precluding confusion, LERs, and
= inspection findings that should we be required to remove it from our submittal, an LAR would be submitted upon NRC approval of the TSTF version of the change. We believe that it would be cost effective for all concemed to retain this change within the submittal pending NRC ,
" I review of this proposed TSTF.
FLOG Response (supplement 1): Based on the present status to the generic change process , for the STS, it appears that traveler WOG-126 will not be approved by the NRC in time to support the initial license amendments for the FLOG plants. In order to facilitate the. issuance of these initial license amendments, an altemate approach has been developed which relies on i the CTS, plant specific information and/or the NUREG but does not' rely upon the traveler. This attemate approach is hereby provided as an interim submittal to allow issuance of the initial -;
- license amendments. The changes which rely upon the traveler can be processed in
' subsequent license amendments following approval of the traveler by_the NRC.
' FLOG Response (supplement 2): The change to state that leakage rate testing is not required for containment purge valves with resilient seals when the penetration flow path is
- isolated by a leak tested blank flange is restored as a beyond scope change.
, All of the modifications made by supplement 1 to Q 3.6.3-23 on these pages are hereby withdrawn.-
l L o -.
. _ _ _ - . __m .. . - . . . .._ . . . . . . - . . . . .
l 1 ATTACHED PAGES: Attachment 12, CTS 3/4.6 - ITS 3.6 j End.2 3/4.6-9 End 3A 8 End 3B 6-End.4_. 1, 30 and 31 End.5A 3.6-17 End.5B B 3.6-28 o End.6A 4 End.6B ' 3 I i 4
.i l
)
i l l 8 l
-1
- - , <w
CONTAIMENT SYSTEMS LIMITED CONDITION FOR OPERATION (continued) l IWW
=3.s.-a.
998WWe8Assemastaraloesteminetystvenerjetadmange? AmR848MO*N3NBiERR51 gegan'Ahtwtst16Jes;andicotRisminag EtDMitLMJinggg ! l SURVEILLANCE REQUIREMENTS 4.6.1.7.1 Each 48 inch and 12 inch containment and hydrogen purge supply and 7-03-ALs exhaust isolation valve shall be verified
- to be locked closed at least once per 0-3.6.3 4 31 daysgexcept:fortone: purge,7yalvednypenetrationiflow1 path whilelin1 Action 316;L7c asialesultlof,measuredjeakageirate31:1,(excess;,_ofdimits.
4.6.1.7. t least once per 184 days andyjthin"9,2[daysloflopeningithe glye~y, a STA00E"C0 TEST ", ASIS, the inboard and outboard isolation valves with M6-s ! 7 14 H resilient material seals in each locked closed 48 inch and 12-inch containment 7 15 A and hydrogen purge supply and exhaust penetration shall be demonstrated 0 3.6.3 19 OPERABLE by verifying that-the measured leakage rate. t k:: th:n 0.05 L,-when ! prc::urtd tc P,- 6 l
$74Mdd l 7-06 Ls 4.6.1.7.3 least once perm $yfiandyithig 92 days;ofiopening?.the 7 16 A 3126 each 18 inch containment pressure relief discharge isolation valve with 0 3.6.3 19 resilient material seals shall be demonstrated OPERABLE by verifying that the 0 3.6.3 20 measured leakage rate t k:: th: 0.05 L, when prc::urtd tc P,. -
SME
- (VAlVItB'Mlt%3psMjentgealsleheEt!!alpenetra_t1op1110iCgJslisolatedj E!Nikageirateltegt.ingMsIgetItequiredifo@ontainmentlpurgeTisolatip0 7.to.ts o.3.6.3 23 :
IWi.Elitegnes3edMag;Dagge
-J* Holat4$ltdevices~1n'h,1ghffadiatjoniateas7,may;be;Ver,1fiediby g-administratigneans CPSES Mark-up of CTS 3M.6 ^ 3H 6-9 H29/99
i CHANGE D NGEER DESCRIPTION MSBC 7-10 -9 A note is added to clarify that leakage rate testing is not required for containment purge valves with a.3.6.3 23 ! resilient seals when the penetration flow path is k isolated by a leak tested blank flange. The purpose of t leak testing requirement is to ensure containment leakage . l integrity during an accident, and thereby limit accident j consequences. Isolation of the flow path with a leak tested' blind flange accomplishes this safety function and ! additional leak testing of the valves in the flow path is redundant and unnecessary. ! 7 11 LS 25 Not applicable to CPSE5. See conversion comparison table (enclosure 38). 1 0 3.6.3 36 l EA2 N Consistent:withIIRREGi1431?JAction]blisirevised to apply;tologly2a~sj!gle~ containment [ pressure l relief dischargelisolation!,yalvelinoperableTPreviously this14 ! houtLRequired.; Action ?alsolapplied]to3wo, valves t inoperable l.% Two;Valvesljnoperablefjs'nowladdressed ,in;alnewfaction tequirementithich a hasialhoutcompletjonjime? 0 3.6.3 35 E1] M Thisic_W3ddslejr ffcation rgsp:1rements;forithe teenten!!stigtgelhydrogen;MtgeIttutthe containmentwess!!telceljefigsolationivalveshtss%6lin EIIs!!DEIDITKcHLTheZtpWt!Lediactions1for 1noperabJs; co!!tainp!stayerA11attmisolattwaalvetsnCvKsreitevis_ed tolvetilfyltEpen!ttritionIfloCMth3solated 'Ance=per 311 days 1forItselatidnzdey1cesLoutsjdeIcontainment Mpriot tolenter;1ggM41ffam1 MODE'J11f3totJperformedMthin;the prmiouspdayjs fgetsolation3 eviceslinside;contajnsenta l TJ!ssetegnien!sntG%LwexisamCIsmTradditi;tEof !' tatenntnerReemreskejassus"conststentiw_tth WestegneusaggEteli!Maj)Il EH H 63awinegmuMBERMh.24ddi!EBEMtfLro !
; thew 811esitg 0 3.6.3 19 NJBEHERLuBRtN5MidId!!tMdece o.3.6.3 20 ;
ag11ggBB!NLI41ROGGRM!LMittatrticcurriingito i 12All! ERR 285GetLWWIIBM1Elleil t!!getrementatsmone7xestr1ctivenetause11t31mpose.slait.es31ng t#MiteMIREthstasagt3jaIcWttGBEMnereforezthe propoDd3hange addsw7sotemragetsiretiuitementithatlis 1 bL.shzapptertagg!dicesisteggetthinUREGL1431;LRey. 3] E15 6 CJsiste!$Mth1tRKel1511Ettielequitementits PRfors2hourve111AngfrAgeheylonialSLEERED Q 3.6.3 19 IESDLASl538IdeleMdRItKdeletjonlofitM 0 3.6.3 20 Sl&SEBEDMl8ASISltpMiteser!tilsitonside_ red!ag Adsjnistrattve;changisincelthelftequencyTpetivalve
-doeXnotzchange CPSES Description of Changes to CTS 3N.6 8 1n9/99
s Page 6 cf 15 l CONVERSION COMPARISON TABLE - CURRENT TS 3/4.6 TECH SPEC CHANGE APPLICABILITY-DIABLO CANYON. COMANCHE PEAK WOLF CREEK- CALLAWAY NUMBER DESCRIPTION. No -Criteria Yes Yes Yes 07 The leakage rate test acceptance criteria for containment i isolation valves with resilient seals is moved to the - already moved from LG Bases. CTS. t No - C"; cir;;dy No - CPSES does not Yes Yes 07-08 " 02 nr.: . .,,,.:. _,...t to gr f;. ; 31 ty ;; . ilkn;; t; - Q-3.6.3-
.crify ;L r; cf th; si-; ;, ;;h;.gjutsunqH.lgncq cent;in; thi; have any closure L3 NLS,-28 EreepsencyMRbtichenge$ifnts_once;per17;daygito;cnce . . si . --..t . restrictions on pver131; days &Asultl%0ggattgaantis1associale:Lwji Neintaining CTS this valves.
$reckingithelmicagajgggggttetj !
pumegalvesihevegesagogaggl tut psca!Wdemmestemd416, t ellsjnete(!j 07 09 Details regarding the valve size and isolation requirements No - CTS does not No - This detail is Yes- Yes LG have been moved to the ITS bases contain this not in the current r.<ma r ,* n 07-10 de added to clarify that leakage rate testing is not %; C"; 2 ; not x.toin thi; Yes Ves;No 0-3.6.3- !3 I LS-9 required for containment purge valves with resilient seals t when the penetration flow path is isolated by a leak tested . ;e . ,...t Yes blank flange. 0-3.6.3-21 ; L No - That No - That Yes Yes ; 07-11 Removes the requirement to blank flange the containment shutdown purge supply and exhaust isolation valves. end requirement was not requirement was not -3.6.3.!1 ' ! LS-25 ! ic.i;;; th; ;,.r.;;1L.-- . .w;. .-..; fr vrification of part of CTS. part of CTS. ch ,.d ;h;.tia. ,,.. , .r v;h;; ;;d fL. ; in;it
.,..w..-...
i
$ction,blis reviseddotspplyitolonlyistsing]Econtainmost 30] Yes Noj Mp33 r Ok12 m 3.6 3- 16 y pressuregeliefidischersanaleslandalAinoperableis j Previouslyght,Jihoortag!sttneduk:tjenistisolepplied;.t.o2 mo t valves 21nopecablemMaalves2inoperettleiis;;nowtaddressed in a unew .
action;3psitegsstAtchJheslajljmut. e completion , t time 4 l t CPSES Conversion Comparison Table - CTS 3M.6 U29199 l
. . - .- -- - . . . _ - . - . , - - - - - - . - ~ ~..--.--_.=-----_-----------._..----------__a----..---- - _ _
- . . -- - _ - - - .- .- ~ . - - - . - . _ .
l N0 SIGNIFICANT HAZARDS CONSIDERATIONS (NSHC) i CONTENTS l I. Organi zati on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 I L II. Description of NSHC Evaluations. . . . . . . . . . . . . . . . . . . . . . 3 r t . ! III. Generic No Significant Hazards Considerations i~
"A" - Administrative Changes......................... 5 "R" - Relocated Technical Specifications. . . . . . . . . . . . . 7 "LG" - Less Restrictive (Moving Information Out of the Technical Speci fications) . . . . . . . . . . . . . . . . . 10 "H" - More Restrictive Requirements. . . . . . . . . . . . . . . . . 12 IV. Specific No Significant Hazards Considerations "LS" LS 1................................................ 15 LS 2. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not Appl i cabl e LS3................................................17 LS 4................................................ 19 LS-5................................................ 21 LS 6................................................ 23 LS-7................................................ 25 LS 8................................................ 27 a.3.6.3 23
- LS9.............................................. .3 m .
LS-10........................... .........-m- a- . 0 3.6.3 28 LS-11............................................... 32 LS 12............................................... 34 LS 13............................................... 36-LS-14............................................... 38 LS 15 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ~. 41 LS 16............................................... 43 LS-17............................................... 45 LS 18............................................... 48 LS-19............................................... 50 LS 20..........................................Not Used LS 21..........................................Not Used LS 22. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not Appl i cabl e LS 23. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not Appl i cabl e LS 24 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not U sed LS 25. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not Appl i cabl e
- ~ ~ " " " "r"" = ~- "*r5 0 3.6.3 4 t_ S:2.6.
. - . M "h24st tLL2JJJ.MSM,2LL?tL5JL*H"!JJ,.tL*l.tL"tJLLL.*JLtLL~2 V. Recurring No Significant Hazards Considerations "TR" TR 1................................................ 5256 TR 2................................................ 5458 TR 3.................. ............................. 5658 CPSESNoSignificantHa:ards Considerations -3N.6 1 1/29/99
IV. SPECIFIC NO SIGNIFICANT HAZARDS CONSIDERATIONS NSHC LS-9 10 CFR 50.92 EVALUATION a.3.6.3 23 FOR TECHNICAL CHANGES THAT IMPOSE LESS RESTRICTIVE t REQUIREMENTS WITHIN THE TECHNICAL SPECIFICATIONS l
'The required action for a containment ventilation isolation valve (CVI) not within its leakage limit is revised to allow the penetration to be isolated using a closed and deactivated automatic valve, a closed manual valve or a blind flange and does not require the isolation valve to be restored to operable status. This is an option not explicitly available in the current TS. The Completion Time of 24 hours remains the same as in the current TS. If valves with resilient seals are used to isolate the flow path, the leakrate of these valves must be verified at least every 92 days. If a leak tested blind flange is used to isolate the penetration flow path, the valves with resilient seals whose flow is isolated by the blind flange are not required to be leakrate tested. Isolation of the flow path with a leak tested ,
blind flange provides the required leak barrier and additional leak testing of the valves in the flow path is redundant and unnecessary. This proposed TS change has been evaluated and it has been determined that it involves no significant hazards consideration. This determination has been performed in accordance with the criteria set forth in 10 CFR 50.92(c) as quoted below:
"The Connission may make a final determination, pursuant to the procedures in 50.91, that a proposed amendment to an operating license for a facility licensed under 50.21 (b) or 50.22 or for a testing facility involves no significant hazards consideration. if operation of the facility in accordance with the proposed amendnent would not:
- 1. Involve a significant increase in the probability or consequences of an accident previously evaluated; or
- 2. Create the possibility of a new or different kind of accident fro <n any accident previously evaluated; or
- 3. Involve a significant reduction in a margin of safety."
The following evaluation is provided for the three categories of the significant hazards consideration standards:
- 1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?
i- The proposed change does not result in any hardware changes. The role of ' these valves during an accident is to isolate containment, and thereby limit accident consequences. The proposed actions will not allow continuous operation such that containment leakage after an accident will exceed assumed ' values. With the associated penetrations isolated per the proposed Action i i l CPSES No Significant Hazards Considerations - 3N.6 30 1/29/99
IV. SPECIFIC NO SIGNIFICANT HAZARDS CONSIDERATIONS l NSHC LS 9 (continued) 0 3.6.3 23 requirements, no accident as a result of the leaking valve is credible. l Further, with the line isolated it cannot contribute to the consequences of a l previously evaluated accident. Therefore, this change will not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?
The proposed change does not necessitate a physical alteration of the plant (no new or different type of equipment will be installed) or changes in parameters governing normal plant operation. Thus, this change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does this change involve a significant reduction in a margin of safety?
The proposed change is acceptable since the isolated penetration provides protection equivalent to restoring the valve to operable status. Providing the option to isolate the penetration will minimize the potential for plant transients that could occur during a shutdown required by TS if the isolation valve could not be restored to operable status. In addition, the isolation of the line (in accordance with the proposed Required Action) ensures that leakage through the associated penetration is within limits. As such, any reduction in a margin of safety will be insignificant and offset by the benefit gained through avoiding an unnecessary plant transient. N0 SIGNIFICANT HA7.ARDS CONSIDERATION DETERMINATION Based on the above evaluation. it is concluded that the activities associated with NSHC "LS 9" resulting from the conversion to the improved TS format satisfy the no significant hazards consideration standards of 10 CFR 50.92(c): and accordingly, a no significant hazards consideration finding is justified. l
' CPSESNo Significant Hazards Considerations - 3M.6 31 1/29/99
1 1 1 V l Containment Isolation Valves (At;r.csphcric, ' L c . . t.._
... i _. _ ._ r_ e__,_
.~..e,
, _ _ ,__2_____
.mm o m, ~e . . s . . .,~...,s,
__; n. . 3,3q 3.6.3 SURVEILLANCE REQUIREMENTS (continued) l SURVEILLANCE FREQUENCY _. I SMM 1dEbersnesultstlMciCMGFG _. M i%I8 6 M I T D8IM.i M 80 Wittlib S Heal; i 3.6 13 I teste ( $1(nl G angegn&,;;jd g g m a g g;gs;&ig d ) 0 3.6.3 23
- =m=_:==
n,, - - umaa-a- ========~=:::.wn aw f Perform leakage rate testing .for . 184 days containmentpurge!1 hydrogen: purge]snd 8 PS C containmentJpressureire11efvalveswith AND l resilient l I seals. Within ' 92 days ; after l. opening the valve l SR 3.6.3.8 Verify each automatic containment isolation ! valve that is not locked, sealed or otherwise i secured in position, actuates to the isolation 18 months fBM position on an actual or simulated actuation signal. SR%613I9 Not'qsed S" 3.0.3.0 Cy0ic C0Ch WCisht er ;prins 100d;d Ch;;k IS ,enth 3.6 M25
...,.. __i &__i.t,_ 2..'--- ----- --
vyu. u'w '. v. i Q 3.6.3 30 vu.ws i rv w wwwwuu.s wwi isry through ;,C ;;a.p10tc cyclc ;f full trev;l.
=d vcrify ^;;h ch;;k V lv r; ;in: cissed _ _ _ _ _ . . _ _ ,_ wkkp.
c M
.t__ 24.,.,.._.__._.m2.,
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dir;; tier. Of fl;W is a [1.2] paid =d ep;r:3 !. .; hen the differential pressure in the
's,___ __ ., c, - . a. r, ,, . 22 __s.
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- v. ii- i. c 64. a y iv v~
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- en on ..v....a
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0 3*6*3 30 valve is blockcd t; restrict the v;1vc fre;;; cpcnins
- Cs0]*.
!B PSsm (continued) i.
CPSESMarkup ofNUREG-1431 -ITS3.6 3.6-17 1/29/99
l.. l's Containment Isolation Valves (At;;;pheric, e . & _ m_ _ _ _ u _ ,__ ,.__m____ __; m.m j; wwww wusevdys su s sw. aww wwi swwa s sw s , usru wwusi ! B 3.6.3 f l
~ BASES i
l ' Additionally, this SR aust be performed within 92 days after
- opening the valve. The 92 day Frequency was chosen I recognizing that cycling the valve could introduce additional i seal degradation (beyond that occurring to a valve that has L not been opened). Thus, decreasing the interval (from
! 184 days) is;a prudent measure after a valve has been opened. l Meongoisses pargeavdrogan'purgegand:centainment pressuten)Miraises arettegad;inlaccordanceMth:the contatapans.teskagesetegestig Progtangitenkagefate acceptaae!rmitatiraps,1es tas;to110ws;
- 17. The;inboatdiandsoutboard;f solation: valves"trithj res111ent;matettalgseal siin'ench 1ocked; closed,4ej inch;containmenttpurgeland:12 iinchipydrogenopurges supp1 rand; exhaust: penetration' mea _suredileakageirate ;
! isE0;051whenpssutized;to;PJ l 2) Each]1811nch' containment? pressureireliefadischargel
- isolation
- valve with1res111entimateria13 seals!
L measured;1eakagezate; ismo.06;tewhen: pres.surized j to E The;NoteJisXclatificationithat31eakagefrateltestinglis ht required;foticantainmentipurgelval ves1with Tesilient? seal s i i whertthettipeppttationlQowlpathjis.21solated ;by"aj eak tested J p1 M apgeB , i SR 3.6.3.8 Automatic containment isolation valves close on a containment ! isolation signal to prevent leakage'of radioactive material from containment following a DBA. This SR ensures that each l P,j!aisef.g automatic containment isolation valve will actuate to its isolation position on a PhajielfgRaelatM)ignal) e8MCPhqul6fBy,ge@mbatW2)otgainmentMMlatMMalveN111 CP 3.6 002 a@ateJROR1MIis0Jat1pnEpoKl1tloniotLg3pptKH! set!tfhaseR 3 IM]atjgGMgllg]l thd3SMpdessurRR81]pf;glischairgefyalve i aMattggD((sggiatigggggg;togLogg Containment l
- y,egtilggg Isolation signal. This surveillance is not requirec for valves that are locked, sealed, or otherwise secured in the required position under administrative controls. '";; 10 cwnth Tr; .;ncy is b;;-d en th; n;;d t; l' perfer; this Surv-ill;nce ur.dcr th; cenditions that :pply l'
during ; plent ;;t;;; and the p;tentiel for en unpi;nned tr;n;ic st if the Surveillenc; war; perfere;d with the reacter > et p;.;;r. Operating experience has shown that these - components usually pass this Surveillance when performed at the 18 month Frequency. Therefore. the Frequency was concluded to be acceptable from a reliability standpoint. (continued) i l I U2989
. CPSESMark-up ofNUREG-1431 Bases -ITS 3.6 ^ B 3.6-28
i l. I-CHANGE MABER JUSTIFIQIIQH f' secured in th;ir r;;; ired p;;ition ;.nir c.tini;tretivG 0 3.6.3 11 L ;;ntrol, thi: cher.;; asuid previi th;t isoletion tin t;; ting is net r;;; ired for ;;t;nti; centeinsat i;;l; tion v;1va th;t er; lxked. :c;l;d. Or otherai:: ; cured in their required p;;ition uni r ;iini:tr;tiv; centrol.lllot"used 1 3.6-13 A clarifying note is added to SR 3.6.3.7 that would' allow 0 3.6.3 23 that leakage rate testing for containment purge valves with , resilient seals is not required when the penetration flow l path is isolated by a leak tested blank flange. The blank flange ! provides the required isolation and additional testing of the valves is unnecessary. - 3.6 14 . Not applicable to CPSES. See conversion comparison table (enclosure 68). ; 3.6 15 Not applicable to CPSES. See conversion comparison table (enclosure 6B). 3.6 16 Not applicable to CPSES. See conversion comparison table (enclosure 68).
~3.6 17 Not applicable. See conversion comparison table (enclosure 6B). '
3.6 18 Not applicable to CPSES. See conversion comparison table (enclosure 68). 3.6 19 Not applicable to CPSES. See conversion comparison table (enclosure 68). 3.6 20 Not used. 3.6 21 Not applicable to CPSES. See conversion comparison table (enclosure 68). 3.6 22 Not applicable to CPSES. See conversion comparison table (enclosure 68). 3.6 23 Not applicable to CPSES. See conversion comparison table (enclosure 6B). DE WaPP11CelllMhilgce tver.s.jogIcompatigon; table o.a.6.6 9 l M1oMd![L60] EMS Based;o!gqSHgsugleillages;SR;3;6J31121and;3[611513 0 3.6.3 30 hagbegEadded! 4 U29/99 CPSES Differencesfrom NUREG-1431 - ITS 3.6 I
Page 3 cf 4 CONVERSION COMPARISON TAELE FOR DIFFERENCES FROM NUREG-1431, SECTION 3.6 APPLICABILITY TECH SPEC CHANGE COMANCHE PEAK WOLF CREEK CALLAWAY DESCRIPTION DIABLO CANYON NUMBER ay f VesNg Yes Yes VesNg 3.6-13 A clarifying note is added to SR 3.6.3.7 that would allow 0-3.6.3-23 that leakage rate testing for contairment purge valves with. resilient seals is not required when the penetration flow s 0-3.6.3 21 path is isolated by a leak tested blank flange. N No No No This change would incorporate DCPP specific operability Yes 3.6-14 criteria for contairment fan cooler units required to meet design functional requirements. No No Yes 3.6-15 SR 3.6.6.7 would be modified to reflect Callaway plant No specific requirements for cooling water automatic functions as well as containment cooler functions. No No Yes 3.6-16 Consistent with the current TS. this specification has been No modified to reflect the Callaway Recirculation Fluid pH Control System. No No No Yes 3.6-17 The ACTIONS and SR's of ITS 3.6.3 are modified to reflect the DCPP current TS allowance to ooen at one time any 2 of-the 3 DBA qualified 48 inch purge supply and/or exhaust valves and 12 inch vacuum / pressure relief valve. No - CTS does not Yes Yes Consistent with CTS 4.6.1.7.2 a new SR is being added to No - CTS does not 3.6-18 contain 24 month have the 24 month perform leakage rate testing for the 36 inch containment requirement. frequency. purge valves and associated blank flanges *.once per 24 months and following each reinstallation of the blank flange. CPSES Conversion Comparison Table -ITS3.6 1n9/99
i ADDITIONAL INFORMATION COVER SHEET l ADDITIONAL INFORMATION NO: CP 3.6-ED (new) APPLICABILITY: CP l l REQUEST: Based on feedback received from the NRC reviewer, the following pages for j have been revised as noted on the attached pages. l ATTACHED PAGES: Attachment 12, CTS 3/4.6 - ITS 3.6 End 3A 10a and 13 Enci3B 4,5, Sa,7,9 and 10
- 1 i l
L L i
l CHANGE Nl#BER RSE DESCRIPTION I i l 10 02 LG Not applicable to CPSES. See conversion comparison table (enclosure 3B). 10 03 LG Not applicable to CPSES. See conversion comparison table (enclosure 38). i MlM 8 NjttJgpl1@leltc[RSESF5Seelcometsjo!!Lcompark tablieijeHC)eSure g g - 0-3.6.6 14 i CP 3.6 ED 11 01 LS 13 Consistent with NUREG 1431 LCO 3.6.3, a note is . l l added to the Actions that apply to all containment isolation l valves to allow containment isolation valves that are required to be closed. [except for the containment and hydrogen purge supply and exhaust valves.] to be opened under administrative controls. This is acceptable based on l the administrative controls consisting of a dedicated i operator at the valve in continuous communication with the l control room. This control provides protection equivalent l to the automatic isolation system. [The containment purge and hydrogen purge valves are excluded because they are not qualified for automatic closure from their open position under. 03A ccnditions and due to the direct flow path from inside containment to the outside atmosphere. Opening on an l interim basis under administrative controls is allowed for certain valves by references made from sections 1.7 and , 4.6.1.1 of the current TS.] ! 1 l l CPSES Description of Changes to CTS 3N.6 10a U29/99 l , L
)
-- . . _ . - - _ ~ . - -
i- CHANGE
- - NUPEER GC DESCRIPTION 11 10 A Deletes [a note] prov1 Jing a one time test interval extension that is no longer applicable.
11 11 A Not 'epplic;bic t; OPSCS. Scc conver-ion cv yeri;0n table (enciosarc OS). 0 3.6.6 10 l. CP 3.6 ED [ i The phrase " flow path" is added for clarification 11-12 A and consistency with NUREG-1431. This l> specification is based on GDCs 55, 56, and 57 which address the proper isolation for each "line" that penetrates containment. It is recognized that multiple lines can share the same penetration. Licensees have always been required to assure that proper protection is provided for each line or flow path that passes through containment even if multiple flow paths share the same penetration. In this
, specification, the term " penetration" has always meant each ,
flow path that penetrates containment. Adding the words l
" flow path" to the specification clarifies this meaning. l 11 13 LS 22 . Not applicable to CPSES. See conversion comparison table (enclosure 38). 1
-11 14 A Consistcat with "JPCC 1431. the phres: 'that is not a .6.3 m locked. 3 led er otherwisc ccured in position, is ;ddcd for clarificatica in rcgcrd to which velv s rc uire isciation tire testing. ;1vc'; that arc dw., s.
s 2..,
- y. ...........2...
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j
-..a su.a. . . s. a . . n...sa.. =rL . 2. 1.sa.. La . L..La .
usew w b bu sb a a du a b kJ s i m bsvs.. ssab a dv s u b g vi s b u t.sb bb d b sAry en';;r;- th;t ;;lv; ;;n r;; ped t- th; p siti ; th;t ;;t'; ! their s:fety furetion in the tira :;su;;d in the safety 1 n lysis. If th; velvcs are secured in the position that
;;;ts their ';;fety function, n testing is ricc serp $t ,
GALM 11 15 A Not applicable to CPSES. See conversion comparison table (enclosure 38). 11-16 A Even though it is not specified in ITS 3.6.3 Required Actions, the Action to restore the inoperable valve stated in CTS 3.6.3.a is understood as always the primary objective ! and a continuous option to be performed during any l Completion Time, i l 11-17 Not used. 11 18 AEG Not applicable to CPSES. See conversion comparison g .3.6 oo7 ,. table (enclosure 38). CPSESDescription ofChanges to CTS 3N.6 13 1/29/99
CONVERSION COMPARISON TABLE - CURRENT TS 3/4.6 Page 4 cf 15 TECH SPEC CHANGE APPLICABILITY' NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK. CALLAWAY 6-02 The inspection requirements associated with structural Ves-NonSee Yes No - (3.6.1.6 not No - pq A- integrity of the exposed accessible interior and exterior ~ Amendment (120/118 in CTS) (3.6.1.6 g Q-3.6.1 -5 g containment surfaces, are contained in Appendix J. Option B {,3.6.1.6_not:19 mt in and in RG 1.163. GTS) CTS) 6-03 Reporting requirements for Containment Structural Integrity Y Ve @ dSee Yes No - (3.6.1.6 not No - TR-2 are deleted. Mendment0120/118 in CTS) (3.6.1.6 E 0 3.6.1 5l (3.6]1knotiin not in CTS) CTS) 6-04 A0T for Containment Structural Integrity not established Ves-NogSee Yes No - (3.6.1.6 not No - y m mmamaq M decreased from 24 hours to I hour. faendments;120/118 in CTS) (3.6.1.6 g 0-3.6.1 -5 E [3,6J.6,notjgi not in GIS) CTS) 07-01 The LCO and surveillance requirements for containment Yes Yes Yes Yes A ventilation / purge valves are now included in ITS 3.6.3 for Contairment Isolation Valves. 07-02 The required actions for a contairment ventilation / purge Yes Yes Yes Yes LS-9 valve with a leakage rate which exceeds the acceptance = criteria is revised to be stated on a per penetration flow path bases. 07-03 A clarification is added to allow one isolation valve in a *es--Norsee CN Yes Yes Yes ;
-3.6.3- L ALS;26 penetration flow path to be opened for repairs when 11-01ELS-13 performing the Required Actions for leakage rate not within 0 3.6.3-5 limits. ,
r ~x 0- The time limit restrictions on opening the [sini-purge Yes - Rel" d to No-CPSESdoesnotf $c; "cicccted tc
, Ves--
R],6 supply and exhaust valves] and the requirements to ECGS. haverestrictions( US'.",Chg tc- 15.iNo N 4 l Q-3 6 1- 15 periodically acn
- a tha time that the valves have been these valves. nRefetJo&OSA ed-to " CP-3*6-10 open would be 6 cctcd mo M licensee controlled 28 USAR documents. Ehepter (
' M-iNo rJefecLto2:08:L%
M 07-05 An action is added for two valves inoperable in one Yes Yes Yes Yes A penetration flow path. ,
CPSES Conversion Comparison Table - CTS 3M.6 H2989
. Page 5 cf 12 ' o
~ CONVERSION COMPARISON TABLE - CURRENT TS 3/4.6 '
t TECH SPEC' CHANGE APPLICABILITY. 4. DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY IUBER DESCRIPTION No -Criteria Yes Yes Yes 07 07 The leakage rate test acceptance criteria for containment already moved from . LG isolation valves with resilient seals is moved to the Bases. CTS. No J PSES does nut Yes Yes 07.nn /,c= 6 ,;g;, _ ,. ;; ,,;7;;; ; : c;y ;,,7;;; , , . . . _ - un M ;'.r: My C have any closure -3.6.3- ;3 !
%# .cr'fy i ; cf tr.; i" ,, ci,; v bc.C_2r ErequpgenuouMituriMD'om,cgceipergiday3Lteicagt cc,c.t iz tri; 7;- ic_.t.
q restrictions on CP-3.6-E
~l eyp yJ11 days;g;$ndjLim,Igspgrenggtsia, sspClate!LwtMI lMntaining, CTS this valves. .
{ trarkinmithmeammataedwettensathms ..HisFWnutatsgeskieleM N8t9M41g;hesihM'speittg3ngLstysdendgeMe_ara gelMAe SMW19888.ld 07-09 Details regarding the valve size and isolation requirements No - CTS does not No This detail is Yes Yes have been moved to the ITS bases contain this not in the current ~f LG requirement. TS. A note is added to clarify that leakage rate testing is not ".; 5 /,,c; =t Yes Vesing Vee-gg 07-10 -3.6.3- ! s.,,c.t;ir tr.i; LS 9 required for containment purge valves with resilient seals when the penetration flow path is isolated by a leak tested r; c. r - .t. Yes '
.6.3-21 blank flange.
No - That , No That Yes Yes ( 07-11 Removes the requirement to blank flange the containment " requirement was not requirement was not Q-3.6.3- !! LS-25 shutdown purge supply and exhaust isolation valves. and ' rcui;= tr.; ; rv;;" m .; c.i.,. c.; fr, vaifi =ti = cf part of CTS. part of CTS. m;,.; Ltt - i; e =h= =d n,.:.;; i=id; Noi Yes- Nod Np;8 97 2 12 8@loni. bits;misedutajiisenkrJewtgl.mus1mlescontainquet 3.6.3- Ni
!! entssuteigt11gfdischNumiselettammheitgopgeblodi <
EnLviouslyithis141hemiegtresAstagMGeolappljeditollmo 31wstigensCaDMEBestiassumper#3e11smetaegnuges inlaicew_acticcitematismluihimaAhout cespletion i
# sed i i
l. I I CPSES Conversion Comparison TnMe - CTS 3M.6 1/29/99 ; i t
'. CONVERSION COMPARISON TABLE - CURRENT TS 3/416 Page 52cf 15
. TECH SPEC CHANGE -: APPLICABILITY' NUlBER DESCRIPTION DIABLO CANYON: COMANCHE PEAK WOLF CREEK CAllAiAY 0714 2
N h -' - - - '- . yet yes yes- leg N. emmestvemmexemmaamiflNktowerify Q-3.6.3- 15 A!1hestfot ' 1setetteldeegewoutssteisessanagathselet toientedne
- nopF&freajelE!L3ftunitastfgespasmalkthm eprav!aus 9%i!$EEE!iLDriASRIMl991'MaseAMARddedleefalBIEle f
l 07:14 Am newirequirseentgisialsoladdegitetperffgrejad]eakage test No Yes No;aseeJ;11;LS 11 0 M gjfAlgSLdaysjtf 4qleg1gg3313aggiggsd 2 0-3.6.3-19 i Q-3.6.3-20 7 NetfEsquigegg 07;15 IhetteRW1MtqKDetfqD4d3141AutNRLence ftgquqperiog;a Ng yes h-l[ 6 EMERElliHEt965JF11&dh08Edi netlinRg Q-3.6.3-19
.( A Q-3.6.3-20 CP-3.6-ED
- 2 ,
07A4 ILigigsdagdisutye11JangedgmlpalsggtaggigkQS4 4ays 2 - 10 0 Ves Yes yg A desocibedisnAn6 LH1IsbegMjKgggK1g&#yst@ Addition Q-3.6.3-19 i ofd'un4JtithinRJinystagetteggningtth!taoMJ - Q-3.6.3-20 0.7.-17 CISiSRL 416;1@2dsLredse(j$gijnglgdet;3ggad(itional Mol-flotdn; CTS nom 1Notiin_ CTS yes leg ! N taquirementLf9ratheimly.and exhaustayDIvesitpib elleshaamstadistalee8&enetipettevetr gQr MLders>1thithe2 blisti2usunusunuuldamuf13h1aJ21ders agaraopen1001theAvahtsta8B!b88R80aMBEsemitsmonti - ; 07 .18 IstocticIsi31 tun 7;ActicREmmesdasadelhtheluseief res No No gg i
. Ls127 taeathouralesurenitani.itsmainalspelantnialfjpw; path anonerable x tensons M m entage.
LQ-3.6.3-Js ~ i 08-01 The LCO references to suction flowpath and manual transfer Yes Yes Yes Yes LG of suction to containment sump have been deleted. These details are included within the operability requirements of > the Containment Spray System as described in the Bases, j i CPSES Conversion Comparison Table - CTS 3N.6 H29/99 ; i
. -4 . . . . . . _ ._-. _ . . . _ _
'w T'
?
Page 7 cf 12 :
. . CONVERSION COMPARISON TACLE - CURRENT TS 3/4.6 .
- TECH SPEC CHANGE APPLICABILITY -
q EDGER' DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAMAY-8 ITS Condition EF] specifies two containment spray trains Yes "; 0"500 i ; ;-ly Yesi Yes- L 0-3'6'6 1~ A; [: my l.. ".i= sf. ^.L. .. ; - . t;;;;41noperable to twedienteenment enter 3.0.3. Even though this condit4sn is not specified e -y tr;in; in the CTS, 3.0.3 would be entered. ... e4 by t';;; tr;ta; i; a t;;d; tk 0" ; ;' 3. 0. 0 ! i; ;.t, ".ic;11y jr N ' .. led . Yes j i 8- "
- 7. di ...,e?'f;il.;t; .ttk LOO",,...i;D ' . Yes No - CPSES current' Yes Yes
^
_.. " 2 t; tt ,,!.11s ti;; 7; =; ^. ,. . . ;f - TS does not have a" Q-3.6.4 -4 4 containment cooler
^
.';' ._... -,/;;;11;;; ;, .t;;; '. 4. .',h . "i; s' .
i; -.1, . d L;;; C..^.. ;;ti;; f- tkt tk 10 ,' , ;lk -d specification.' '
^^
in t k I'S ;;t ts ;^. tk LC" i; i,...".,.. . tk 0" g3;g,cm.ams - m.s4. e
$stdgiEMlEI -
'. n.; 7: e.- - '
.~ : p -y .
m ._
.y -
i W h Yes M - lt Q 3.6.6- L3 !' g 6 M M E ftrAat
- i. JessL151minutsg i
, i i
- 09-01 The DCPP units for the spray additive tank volume limits Yes- No No No A are changed from gallons to percent.
j 09-02 The operability of the spray additives eductors is Yes Yes Yes Yes. LG contained within the definition of operability for the spray additive system as described in the Bases. 09 03 This change revises the action statement by replacing the Yes Yes. Yes Yes A reference to restoring the Spray Additive System to operable status within 48 hours or be in cold shutdown j within the following 30 hours, with the reg 41 resent to be- : in cold shutdown within 78 hours. CPSES Conversion Comparison TnMe . CTS 3N.6 H29,99 ' t
- CONVERSION COMPARISON TAELE'- CURRENT TS 3/L6 - TPage 9 cf.12 s
TECH SPEC CHANGE APPLICABILITY NlNER DESCRIPTION DIABUI CANYON COMANCHE PEAK WOLF CREEK- CALUMAY . N 09-05 The specific actuation signal [(a Containment Spray Yes. Yes Yes Yes. .[ 1R-1.~ Actuation test signal)] for the surveillance was replaced 0-3.6.6- I- ! with a generic words that allow credit for an actual or ! simulated actuation. ; t 09-06. This change moves specific details in the surveillance' No - CTS does not ~ Yes - Surveillance - Yes - Surveillance.. No - 0-3.6.7 8 LG requirement with regard to verifying flow path and the MGT contain this' details are moved details are moved Callaway-water flow [ rates of. between 50 and 100 gpa through the detail. to the Bases. to the Bases.. does not ; eductor test loops} out of the TS, and adds a general have t requirement to verify flow capability through each eductor. this system. ~l 9 07 The' surveillance for DCPP is modified to require. . Yes' No No No , M. demonstration of flow through each solution flow path. ; ' r 10-01 Noves details regarding the number of fans in each cooling - No - CTS based on No - CPSES does not Yes Yes' i LG system train to the Bases. different design. have this ! specification. ! t .- 10-02 Details regarding the automatic functions to be tested and No - CTS does not No - CPSES does not Yes Yes . LG the cooling water flow rate would be moved to the Bases. have this detail. have this ; i specification. { t 10-03 The DCPP specific note cautioning that CFCU flow rate may Yes. No ' . No No , LG not be achieved during Section XI testing and IHL operation is moved to the Bases. - g . _ ..n _ ._ _ . . . - _ _ . . . _ g g. g g j
'~
~
N
.[
~
t
......... .- - _ ~ - ~ . .- - '- '?
-- ~
6 364 N ! m.m eummmmmmmmasemana.s.&- mme ! l
.i
. CPSES Conversion Comparisen TeMe - C153M.6 : 1/MM9
_ _ - _ _ - - _ _ - _ _ _ _ - _ _ _ _ - _ _ - . _ _ _ , _ - . ~ . _ _ _ - . _ . _ . - . _ .--. _ - _.__- .
LCONVERSION COMPARISON TADLE - CURRENT TS 3/4c6 - Page 10 of '12 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON lCONANCHE PEAK WOLF CREEK CALLAWAY f ' 11-11 A =t; i; :.id t; tk -.t;i.-..; i;;lotter. .,,~;.ifictim Ves-HA E ;1. adi p;rt Ves-M Ves-M Of _ .....; 5 . M 03.6.3-1D t Mt th: LCO i; mt .ppli sti "50V;. "S!Y;. T!Y;. [; ,,..;t;d i,p;;; ni n ] nd ;;;c.; c. .. _ 7;licf CP-3.6 EE
% aln;. lls:M 11-12 The phrase 'ficw path
- is added for clarification and Yes Yes Yes Yes A consistency with NUREG-1431.
11 13 This change revises the DCPP containment Ventilation Yes No No~ No. LS 22 Isolation valve surveillance frequency from 30 months to every 184 days and from 24 hours to 92 days ph1lgsglggig yadge. 11-14 TM phr;x *tMt i; n;t lxted. x;l;d. ;,7 eth,..1x VesllA ~ Ves M~' Ves M Ves M 0 3.6.3-]1 A x;,.. ;d i pe;itic .' i; ;14 f; cir.rifixtim in . ... d ' t; dich nix; .;c.ir; e ini; tim ti;; t;; ting. "J 11-15 A Callaway specific note to 3.6.3 regarding testing is No No No Yes , A deleted based on ITS LCO 3.0.5. 11-16 Even though it is not specified in ITS 3.6.3 Required Yes Yes Yes Yes A Actions, the Action to restore the inoperable valve stated in CTS 3.6.3.a is understood as always the primary , objective and a continuous option to be performed during any Completion Time. 11-17 Not used. NA NA NA ~ NA The words *during the COLD SHUTDOWN
- or REFUELING N00E" are No - Not in CTS. No - Not in CTS. Yes Yes 11-18 EGA ;;.;d t; th: Mx; den 14aLisWJnitheJIEE P-3.6.3-29 0 3- j W M 3 4.seses. .
11:19 This ,0CPP;plartspegttigadangLmgeposes;ttnLaore Yes No No M 0-3.6.3-J8 i
- M testtictlye.changetofdlaraimhe21eekitestLirmityquency everr30imenthsitetisedisg[pysty11aelduti .,
i i t CPSES Conversion Comparison Table - CTS 3M.6 y2989 _~ _ _ - - - - . - - . - . - . . - - . _ . _.a_. ._. - - --_-_ . . _ . - - - - _ . _ _ - _ - - . _ _ _ _ - - - . - _ . _ - _
-t ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 3.7.3-2 APPLICABILITY: CP REQUEST:- CTS 3.7.1.6 LCO and Actions ITS 3.7.3 LCO, Applicability, Actions and SRs DOC 07-08-LS26 DOC 07-09-LS10 -
" 1 'JFD 3.7-11,3.7-26
. DOC 07-10-M
, DOC 07-17-A These changes are beyond the s' cope of a conversion.
' Comment:? Provide additional justification.
I FLOG RESPONSE (original): A discussion was held with the NRR staff on 10/9/98 - concoming the proposed ITS for specification 3.7.3 for Comanche Peak Steam Electric Station (CPSES) (the TU Electric position is described below).- The staff opposed the CPSES ITS on
- the basis that the changes might be generic, might be beyond scope, and that the licensee either had to retain the Current Technical Specifications (CTS) specification in its entirety or adopt the improved Standard Technical Specifications (STS) in its entiretyc Based on the NRC's position on this issue, CPSES ITS 3.7.3 has been revised to adopt the CTS ,
frequirements-The CPSES ITS has an LCO which requires the Feedwater Isolation Valves and Associated :
. Bypass Valves to be operable in the appropriate unit conditions of operation (Specification 3/4.7.1.8)c The Main Feedwater Regulation Valves (Feedwater Control Valves or FCVs at c '
CPSES) are not required _ to be operable by CTS because the FSAR does not assume the ,
. Laingle active failure of an FIV or an MSIV and this assumption is not a regulatory requirement.
The FCVs 'are not designated as active (i.e. are not full safety grade) but are designed as highly , L reliable backups to the FIVs. The NRC found this to be generically acceptable for PWRs in
^
L NUREG-0138*. This licensing basis is reflected in FSAR Figure 15.0-10 for MSLB which'does i not apply the single failure requirement to the feedwater or main steam isolation valves ' and FSAR Section 6.2.1 Reference 21. (*USNRC Office of Nuclear Reactor Regulation, NUREG-0138," Staff Discussion of Fifteen Technical lasues Listed in Attachment to November 3,1976 1 ' Memorandum from Director, NRR to NRC Staff", November 1976.] The STS in specification 3.7.3 requires the Main Feedwater Isolation Valves and Main
- ; Feedwater Regulation Valves to be operable. Since the Main Feedwater Regulation Valves .
y ; (FCVs at CPSES) are not in the CTS LCO, CPSES chose to retain the CTS for the ITS LCO. iThe remainder of STS 3.7.3 was retained and modified to be consistent with the revised LCO.
" ~ ' Since the FCVs are not in the ITS, the conditions, actions and surveillances only took credit for 1 >
ithe FCVs if they had been property verified to be capable ~of performing the required function.
' As noted above, the capability of these valves to serve as a backup to the FIVs is consistent with the current licensing basis for the FCVs as approved by the NRC. The CPSES CTS was marked up to reflect the ITS and the changes were justified. The CPSES basis for proposing
. this was to improve safety of the plant. The CTS allows only 4 hours to correct an FIV problem even though the FCV is fully capable of performing the function. Allowing 72 hours to correct an FIV problem given credit for the FCV is consistent with the STS and couki prevent an
' unnecessary plant shutdown transient or prevent a feedwater transient due to a less than a ,
7
+ , -
, - - , ,,v .-.5. .e,
y _ - _._..._..._ - ___ _____ __..___ _ _ _ ._ _ _._ _ _ L L l' adequate time allowed for a repair. The proposed ITS would retain the CTS 4 hours action time should the FCV not be available to perform the function. These changes are not beyond scope. This is a proper retention of CTS and modification of the STS to do so. This should not be classified as a generic change. Although other plants may be similar and - may have similar CTS requirements, the choice to retain the CTS is made by each Licensee
. Individually. Retention of the CTS is not a generic change.
The basis for the STS conditions, actions and surveillances, as modified to be consistent with l the CTS LCO, has not been invalidated by the CPSES proposed ITS. The FCVs are only p credited if they have been properly verified to be capable of performing the required function. All proposed adicns, conditions, and surveillances of the CPSES proposed ITS are just as valid as the actior , xmditions and surveillance in the STS. If these are not acceptable for CPSES, they should 'not be considered acceptable for the STS either. At some point a member of the
' NRR staff said that we cannot take credit for a component in the actions if that component is
' not in the LCO.' Of course that is not true. There are many cases in which the required actions
; credit the functioning of a component which is not covered by the LCO (e.g., if an isolation valve is inoperable, the required actions allow isolation of the affected penetration flow path by at least one closed and de-activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured - these valves are not necessarily in the scope of the LCO). Requiring CPSES to add the FCVs to the LCO is counter to the CTS and to safety. If
- the FCVs are added to the ITS LCO,-it is possible that a deficiency in the isolation capability of the FCVs could result in a unit shutdown when such a shutdown is not required by the CTS and would not be necessary per the CPSES licensing basis. Such a shutdown would put the unit through a transient that would be less safe than continuing to operate.
1 FLOG RESPONSE (supplement): ' A CTS markup page was inadvertently omitted from the
. original RAI response. The marked up page is attached to this supplement. In addition, a ITS Bases page which contained a discussion of the FCVs is revised to delete that discussion since it is no longer pertinent and the Bases for required Action A.1 is revised to match the CTS.
ATTACHED PAGES:
- 1. Attachment 13, CTS 3/4.7 - ITS 3.7 Enci 2 L 3/4.7-11 Enci5B B 3.7-16 and B 3.7-17 e
1 1 SURVEILLANCE REQUIREMENTS ; l i 4.7.1.6 Each feedwater isolation valve, feedwater isolation bypass valve, and j feedwater preheater bypass valve shall be demonstrated OPERABLE by verifying full ; closure within 5 - ;isii tested; pursuant to speu1.t'^n d .5 l 1
-__.= _
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' ~3 2 emen!seea@*
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(IEIQ EVer.1freachifM11soM10Evalve71feedwaterfdsolation; bypass; valve l 5.esa q ) angi 15eginateEpreheaterabypassNalvle ectuatesito;the isolation position:on'an.. actual ! O_Cs_is_cJ.a.t.e. d.Ts..i_
. . gn. al_i. eve.r.y
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( l l l J l CPSESMark-up of CTS 3N.7 3N.7-11 U2989
s "II"; r.r.d "'""; [ Eggand Associated Bypass Valves 3 L B 3.7.3-BASES.. L APPLICABLE : The desigr. basis of the MFfVs M andSFRVs is established SAFETY ANALYSES' .by the analyses for the large SLB. It is also influenced by the accident analysis for the large M-MAA. Closure' of the MFfVs M and associated bypass valves, ;r "I""; .r.d u nci;ted bygn =l;n may also be relied on to terminate an SLB for core
~
. response analysis and excess feedwater event upon the. receipt of a steam generator water level-high high signal ; ;' f;;d.;;ter inl;ti; ;i;; .;l ;r. P.it. :t;; nr;t;r I;=1.
Failure of an MFEV ER MFRV.- or the associated bypass valv'es
- i. to close following an SLB or BS-MAS can result in additional ,
p mass and energy being delivered to the steam generators. ) contributing to'cooldown. This failure also results in additional mass and energy releases fo11mina an RIR or FLS-fM:B Idbbbkd5bbdNbNh;;_m_ .-mmmat-w.- mts .i. .m __.3/=.;rsm m.
.r
- j. me -,% 3.7.3 2 OM The MFIVs lig( and MFRVs andgssottgegGepass3Lelves satisfy Criterion 3 of tt.; ""C ";licy St;t; r.'.. M16(c),(2).Q1)].
LCO c This LCO ensures that the MFfVs M. ".'"t'; and their- .
' associated bypass valves will isolate MFW flow to the steam. ^
generators, following an Fjs-fM:B or main steam line break. II.;;; V;l?;.. Will el;; i;;l;t; tE.; i.er.;;f;ty r;l;ted ,
,,......-.......,.......,...........,,..-.]Ile 0 3.7.3 6 o
4830C.- h l M $dIEindlRI zM iddBINetet 1x. . .- 1 . < : J..a ai. .o . e: 5 c e., u
' s _ .; .I '
' " ' I 'c .
t This LCO requires that Efour) T "; M and associated bypass valves ;..d [fsr] "'""; [=d n;ni;t;d b7pn v;ln:] be OPERABLE. The MFIVs Egg ;r.d "'""; and the associated bypass Ill; *
. valves are considered OPERABLE when isolation times are within limits and they close on an isolation actuation signal.
j-Failure to meet the LCO requirements can result in additional
< mass and energy being released to containment following an SLB or El&-HA:B inside containment. Begagg6+f-a feedwater isolation
' signal on high steam generator level is relied on to terminate an -
excess.feedwater flow event, failure to meet the LCO may result in the introduction of water into the'sain steam lines.
' CPSES Markp ofNUREG-1431 Bases -1153.7 -. . B 3.7-16 1/2939
I "fI": ;rd "I"'!
. [ R $]and Associated Bypass Valves}
L. B 3.7.3 BASES. I i APPLICABILITY The NFWs 133 and49Ws and the associated bypass valves must be I OPERABLE whenever there is significant mass and energy in the
~
l l Reactor Coolant System and steam generators. This ensures that, ) in the' event of an HELB, a single failure cannot result in the
- blowdown of more than one steam generator. In H0 DES 1, 2.
fand 33, the NFW s FIVs ;.;d " T": and the associated bypass ! valves are required to be OPERABLE to limit the amount of I available fluid that could be added to containment in the case of l a secondary system pipe break inside containment. When the valves are cloe,ed and de activated or isolated by a closed manual I valve, they are already perfo"1 ming their safety function. In H0 DES 4, 5, and 6, steam r,enerator energy is low. Therefore, the NFWs Flys. l"*/s. and the associated bypass valves are normally closed since HFW is not required. ACTIONS The ACTIONS table is modified by a Note indicating that separate Condition entry is allowed for each valve. A.1 and A.2 With one HFW Igy in one or more flow paths inoperable, action must be taken to o.3.7.3 2 l : eggge3restoretheaffectedvalvestoOPERABLEstatus,or_to ! close or isolate inoperable affected valves within igEl hours.
,,m - - - -, --m - - - . . . . . _ . . .
! these valves are closed i or isolated, they are performing their required safety function. 1 l The M 4 hour Completion Time takes into account 'the red;;r.d;r,;y C;ffr,-ded by tt.; rc ;1r.ir.; 0"C."XLE v;h;; dr4 um iow proDamilty of an event occurring during this time perloa that would require l 1 solation of the NFW flow paths. The R- 3 hour Completion Time is reasonable, based on operating experience. / l t-o.3.7.3 2 ! l l ! i g ... .. - r- , 27,. ucpc ..r - : ts 4. CPSESMarksgr ofNUREG-1431 Bases -ITS3.7 B 3.7-17 1/29/99
l l ADDITIONAL INFORMATION COVER SHEET i l ADDITIONAL INFORMATION NO: CP 3.7-ED APPLICABILITY: CP REQUEST (original): Various changes that do not impact the technical content of the i submittal or other FLOG members.
-Changes are noted with CP 3.7-ED in the margin and noted below:
I I REQUEST (supplement): The following addition change is provided which does not impact the ) technical content of the submittal or other FLOG members. l l
. ATTACHED PAGES:
l Attachment 13, CTS 3/476 - ITS 3.7 Enci 2 3/4.7-9 The wrong DOC number was in the margin Enci5B B 3.7-57 Corrected function title B 3.7-61 Deleted redundant and potentially confusing sentence Enci 6B 1 This page (JFD 3.7-05) was inadvertently not included with the CPSES response to Q 3.7.4-1. These changes were reflected in the corresponding JFD in enci 6A which was provided with the response to Q 3.7.4-1. l i i l. l l l
. . - .-- _ - . - . - - - - =
1 1 PLMT SYSTEMS i 1 13.A Q 3.7.1-1 l MAIN FFFnWATER ISOLATION VALVES 1 LIMITING CONDITION FOR OPERATION j 3.7.1.6 Od ;in f;;i;tcr 11-- 2;11 h;v; EcurNRCgrid3nsegisted:Dypass g}gggggM OPERABLE a f;;ieter is;1; tion velv;. feei;tcr is;i; tion bpess 719.tg 0 3.7.3 6
\
velve, . .d feei;tcr pid;;tcr b5:33 ;;1ve. j CP 3.7 ED l APPLICABILITY: MODES 1, 2, and 3 egegMeEt;belfeedseterjgelationivalvelor ( _/
.usas3
;j$ pus;1alteIz z ^.L A Z ^a.C w_V;1v;3s -
closeCand:deiactivated;orfisolated;4yfr_ closed;manualaalve. ACTION: NDTEM, Separate:entrylis
- allowed;forleach ;yal ve 7.as.rs =
MODE 1: 7-se-Es 0 3.7.3 2
- a. With one ocjeort feedwater isolation valve inoperable, but sp;n, ^
operations may continue provided ti;;';; ;.tci,;;, .,ft;;.c.d.;-:-; -:',;t;d
.__,___m., .__m 7 eHa 1
~,_ .=- 1a ~1- t%-.m;the inoperabl e m___-._,-.__.. _ _ . . _ , , _ . - , _
-,r--- a-.z-- -m a-. w_
"1 feedwater isolation valve is restored to OPERABLE status 51solated_.oriclosed**
within M ( hours, otherwise be in HOT STANDBY within the next 6 hours. 17-1M83 With one or more feedwater isolation bypass valves inoperable, operations 7-0845
- b. < _ _ _ _ . . , Q 3.7.3 2 may continue provided m_
m ._ ____.
,,,. 3.
.__,~_2
.m ' . t.7 .
_____,_a
. , -- s ,o ,,. .,, r..
a , ...._ einsi.liEIR' ;.C^-EM^GGht ai. each affected feedwater ' { isolation bypass valve is restored to OPERABLE status 81solated or
+ ts m M closed $ within g tihours, otherwise be in HOT STANDBY within the next 6 l
hours, N
- c. With one or more feedwater preheater bypass valves inoperable, operations Q 3.7.3 2
_._____,_._.__,m_._,..,,,,_ may continue provided m--.__ _ ,-,,m,,- zw .,.,
. , _ , . m. _~ ~~m
.. _--m -,---.--.m
-u, _ u,.-u,
,,m.,___
each affected feedwater 978481 preheater bypass valve is restored to OPERABLE statusglsolated or closed *J within M ghours, otherwise be in HOT STANDBY within the next 6 17-11 4 21 hours. mm,_..________,_m..,__,m..--__-_._,m __> m_
,r m,._a-a..m~
_m-m L a-.w u- _ . se__v._ a._m _m_.m..a .% m u,._-=-.. . _ A_=_x.- m w r , ,cs a.__ _e__ _,,m
. ,m, g
I _am ____ _ m,_ ,._m . . - = - _---wes _ _ e_.tu_m
- __ .. .m m _A_ _._ um, .. _mu. ._ ..., ,
u-0 3.7.3 2
- -ay
,u,m_u- = *--
- c. _.- _,n. L.._s, w.~=
__,-- -_ _ _are. ___ n m m ___._ _mr-?n..a,,= _, m _. . . m.axm.w- > --- -- -. - - - - w.t .em- - o- % = n. - m. .u _m.._m_,ma<.____1._,.x__ 7-00-65
.,_ ___ , m,_.,_.-____..,_ _ _ m._a_
- --.2..- - 2ir-- .'-1'v 0 3.7.3 2
_-.m sa_ ,n. _m, m,u_ _ .- =m 5 .
-t.ax u -ara w 6. s.aur e_.-.- e _w .- a xt m
- .__.___._r Yettffvalvei1Q1solatedJAricio$edionceJperZdayQ .. 7-it-M H 5
CPSES Mark-up of CTS 3N.7 3N. 7-9 1/29/99
- 'CREFS B.3.7.10
' BASES (continued)
. APPLICABILITY In MODES 1, 2, 3, 4. Egg and during movement of irradiated fuel assemblies c.c.d irir.; C= ?.LT=TIO"S. CREFS must be OPERABLE to control operator exposure during and following a DBA.
h th; Z FS i: regired t; ;;,,,; with th; reins; fra th; r;;;tur; cf ;r. Outsii .;;.;t; gr.; ter.k. CP 3.7 13 During movement of irradiated fuel assemblies and-GORE Al-TERAT 40NSr the CREFS must be OPERABLE to cope with the release from a fuel handling accident. ACTIONS U When one CREFS train is inoperable, action must be taken to restore OPERABLE status within 7 days. In this Condition, the remaining OPERABLE CREFS train is adequate to perform the control room protection function. However, the overall reliability is reduced because a single failure in the OPERABLE CREFS train could result in loss of CREFS function. The 7 day Completion Time is based on the low probability of a DBA occurring during this time period, and ability of the remaining train to provide the required capability, Bell CP 3.7-ED 0 3.7.10 14 i ;3 1 . . J..,... h # ? . . . , p .x. 's -; r_ c.. ;;; w:y,.c 4 mm ,- m-,*--4. m a.uw 1MEREitmisdREEBtitE24 hodft3 5.$$O$$$W. ?? . .. .
- . - .m gggr. 3 3, g. - ,: . . .p. ;. f gg f.j, g y; y r; . ;,, ., .
BG.1 and BL 2 In MODE 1, 2. 3, or 4, if the inoperable CREFS train oricontrol rops;bpfggla]33cannot be restored to OPERABLE status within the required Completion Time, the unit must be placed in a MODE that minimizes accident risk. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours, and in MODE 5 within 36 hours. The
- CPSESMarkup ofNUREG-1431 Bases -ITS3.7 B 3.7-S7 1/29/99
GREATGSCRilCS B 3.7.11 B 3.7 PLANT SYSTEMS l B 3.7.11 Control Room targny Air T. ,,;retur; Catrol MEghRkgggg System l (GREATGS M ) 1 BASES BACKGROUNO 1llOct$re)MEB3mmeGBFJleRitsunitsIERditlet a 3.7.11 1 CMCSIMEMiggp6,1to11lgglQq$$$] The GREATES (MBq provides temperature control for the control room dudgg]MllphMl!llLggeggi!!gg,opeptigpad fellwing is;?; tion of th; cetr:1 c;=. The GREATGS gigi consists of two ir.igniat ad redundant trains that provide cooling and heating of recirculated control room air. Each CitACS train inc]udes!tWolheating and cooling l unitscasists;fhating;;ils.;;; ling;;ils. instrumentation, and controls to provide for control room temperature control. Each; coo 11ng?uq1t'lp.tpvides35021ofttheleajx ausiheat; removal _ capabi1Jtyggt&1ts7 respect 19elTrains The GREATGS CIU]CS is a subsystem providing air temperature control for the control room. The GREATGS GREE is an emergency system parts of which may also ' operate during normal unit operations. A single train will provide the required temperature control to maintain the control room between.__._._ M*F and,_ 85m.m a0*Fs_- _o ,Q;^;,.,^f,,;; _____ ._,_, CP 3.7-ED r m..x
.w -.-s,m -. . - _ - - u n,_.u ,. . .. . - ,. - -
3IIC wrue,;'e v @ operation in maln':e n n control room temperature is 0 3.7.G-1 discussed in the FSAR. Sectiong 6M (Ref.1) #31314j1 ,
$$$[.$N.
L ItanemKlettetenstessammakemesernsehamwis { .. .'; ..ia y. ..m e., .. . 1, ; y. ., .j ,e ig ,; i 11 0 3.7.11 1 Q}_ % ' On ~ ~ . - . L < :y Lj i. . :. t ..n i. th i .L.l r :* L aj(g)T e e e r- '
,, ; >> ' .1 " > 3 ,m ,t . O G 6 -
ywch % .- -
. . m ~ ; ./.3. . .n,i . v.
- v. A jg .. ..
l IginopetbNti4RlWF2NTeted3RD11:enit:1:1
- BM1SIMGDREintERtL1hBBOMn8tBIR11ggggateriegtJilegd 199EofLtheleg]3Oggtgggpiett11ty3Mti)P8Va1]Al)1335 APPLICABLE The design basis of the GREATGS CRgg is to maintain the SAFETY ANALYSES control room temperature for 30 days of continuous occupancy.
- CPSESMarkup ofNUREG-1431 Bases -ITS 3.7 B 3.7-61 1/2939
CONVERSION COMPARISON TACLE FOR DIFFERENCES FROM NUREG-1431- SECTION 3 7 . Page 1 of 6 TECHNICAL SPECIFICATION CHANGE APPLICABILITY-NUPBER DESCRIPTION DIABLO COMANCHE WOLF CREEK CALLAWAY ^ CANYON PEAK 3.7-01 CIT A.1 1; rsLd; ;;d 7. u O!= A.2 i; _dd.d t: xant f;r VES N0; YES. YES YES
, r,.. ; tion with 1.~r.. ;ti; 52; ;;d . mttia;; ik p; ;r re.. ;;.tren fis maintai.ning CTS
'i;;'. trip m.61-t; with :.~r,.. _hl; C";. Th; C; pl;tica Ti;; t .; x t th; p cr . ..., . .;. ,. 71;.;; hi;;'. trip x; pint; i; st..~ :: 72 h;_r;. [ 0-3.7. L-4 3 stheJact therenisenstoet hte,the reductfoglin ; ssin;steenJaletnvalMQ!5SEtelleting.capabilitrand. plants Wh31MLagsencessmultiteositive_leederMot Tsuperstatucconfmasegggjiu 3.7 02 The CTS Applicability of Nodes 1. 2. and 3 is being retained in ITS 3.7.2 NO: DCPP is NO: CPSES is YES YES NSIVs. and ITS 3.7.3. [NFIVs]. adopting ITS. adopting ITS.
3.7-03 SR 3.7.3.1 is divided into two surveillances since both the stroke time and YES (per LA NO NO N0 the frequency requirements are different at DCPP for the feedwater 77/76) regulation / bypass valves and the feedwater isciation valve. 3.7 04 Requirements involving reliance on the SG heat removal system for heat NO - DCPP is YES YES YES removal in Node 4 would be deleted. adopting ITS 3.7-05 DNTRED ACTION B 1 and & M - ravised to state that restoration of YES YES NO: refer to M attleast"And M attleashtwo" [ARV] lines is required which 3.7-19. Q-3.7.41 will ettecuvely exit the s c>pecuve MLyVIRw ACTION. CP-3.7-ED NO refer to 3.7-19. 3.7-06 The CONDITION and REQUIRED ACTION for two or more inoperable [ARV) lines is YES YES NO: not part NO: not part limited to two [ARV) lines and the CONPLETION TINE is revised from 24 to 72 of CTS. of CT3. ' hours per the current licensing basis. A new CONDITION C is added. 3.7-07 Revised Conditions A and C to be consistent with CTS. The ITS as written NO: not part of NO: not part YES YES would have allowed the OPERABLE EES train to remain in standby during CTS. of CTS. movement of irradiated fuel. + 3.7-08 SR 3.7.5.1 is revised to add a note consistent with the CTS and the plant NO: AFW valves YES YES YES specific design. The verification of flow control valve position is have a correct deferred until conditions are appropriate. position. CPSES Conversion Comparison Table - ITS3.7 H29M9
l L i i l ADDITIONAL INFORMATION COVER SHEET i ADDITIONAL INFORMATION NO: Q 3.8.1-33 DC APPLICABILITY: CP Q 3.8.1-20 CP 1 Q 3.8.1-17 WC 1 REQUEST: .CP Bases for ITS SR 3.8.1.8, STS Bases page 3.8-19 DC(3.8.1-33) . Bases for STS SR 3.8.1.8 WC(3.8.1-17) Bases for ITS SR 3.8.1.9, STS Bases page 3.8-20 ; Bases for STS SR 3.8.1.9 i Bases for ITS SR 3.8.1.10, STS Bases page 3.8-21 ; Bases for STS SR 3.8.1.10 i Bases for ITS SR 3.8.1.11, STS Sates page 3.8-23 l L Bases for STS SR 3.8.1.11 1 l Bases for ITS SR 3.8.1.12, STS Bases page 3.8-24 Bases for STS SR 3.8.1.12 Bases for ITS SR 3.8.1.13, STS Bases page 3.8-25 Bases for STS SR 3.8.1.13 Bases for ITS SR 3.8.1.14, STS Bases page 3.8-26 ; Bases for STS SR 3.8.1.14 j Bases for ITS SR 3.8.1.16, STS Bases page 3.8-27 l' Bases for STS SR 3.8.1.16 Bases for ITS SR 3.8.1.17, STS Bases page 3.8-28 ! Bases for STS SR 3.8.1.17 Bases for ITS SR 3.8.1.18, STS Bases page 3.8-29 Bases for STS SR 3.8.1.18 .! Bases for ITS SR 3.8.1.19, STS Bases page 3.8-30 l Bases for STS SR 3.8.1.19 The Bases for ITS SRs 3.8.1.8,3.8.1.9,3.8.1.10,3.8.1.11,3.8.1.12,3.8.1.13,3.8.1.14, L e 3.8.1.16, 3.8.1.17,3.8.1.18, and 3.8.1.19 state, "This Note does not prohibit the application of
- i. LCO 3.0.5 or the performance of this SR to restore equipment Operability." These are proposed differences relative to the Bases for STS SRs 3.8.1.8, 3.8.1.9,3.8.1.10,3.8.1.11, 3.8.1.12, 3.8.1.13, 3.8.1.14, 3.8.1.16, 3.8.1.17, 3.8.1.18, and 3.8.1.19.
L Comment: The Notes for ITS SRs 3.8.1.8,3.8.1.9,3.8.1.10,3.0.1.11,3.8.1.12, , I 3.8.1.13,3.8.1.14,3.8.1.16,3.8.1.17,' 3.8.1.18, and 3.8.1.19 do not provide any exceptions.- The proposed Bases differences appear to be in conflict with the Notes. No justification has been provided to support the proposed differences. Revise the p - suLmittal to provide the appropriate Justificatxx1, or conform to the STS. L FLOG RESPONSE (original): ])lt DdBGEBl@($l [ e.. .
. . ~ J 4 : H i>. 7 a~161 A 4 J. 7 i V i f e J% P STF-283," Eliminate Section 3.8 Mode Restriction Notes" was not incorporated into the FLOG conversion
,: applications since the traveler was still undergoing significant revisions at the time of submittal. ! The FLOG attempted to address these notes in the Bases through the application of LCO 3.0.5. [ These notes should not restrict the ability to credit post-inaintenance testing that can be shown to provide satisfactory performance of Surveillances. As dison, sed in the telecon on December 10,1998, the FLOG believes this traveler to be a high priority traveler and would like to see resolution of this issue prior to issuance of the license amendment. However, the FLOG has
~
mvised the proposed ITS to incorporate the CTS requirements applicable to testing "during i
~ ^ ^
~ l
)
I shutdown" to facilitate the schedule for issuing the amendment. Should this traveler be ) resolved prior to issuance of the license amendment, the FLOG would work with the NRC to j incorporate this traveler into the ITS. I 1 l l MM ZdKpoUgglggglgghf_ggLBasps as l m?N13BabetRBRM001ttproMtsed IEE23dnWporaw.jheylS, J ammldmmenNeapggtteggggmatgehul@twik1 FLOG RESPONSE (supplement): For Comanche Peak, SRs 3.8.4.7 and 3.8.4.8 were overlooked when the original RAI response was prepared and submitted. By this supplement, these two surveillances are also modified such that the mode restriction notes match CTS. ATTACHED PAGES-Attachment 14, CTS -3/4.8 - ITS - 3.8 Enci5A ' 3.8-25 and 3.8-26 j i i l l j i
~ 1 1 DC Sources-Operating 3.8.4 1 1 SURVEILLANCE REQUIREMENTS (continued) ; i SURVEILLANCE FREQUENCY
.SR 3.8.4.6 %0TC This Surv;illen;; ;h;il not b; p;rfer;;;;d in M00: 1. 2. 3. er 4. llsw;ver credit ;;;;y bc :f3'l8f393'1 t; ken for unpi;nned ;;;nt:; th;t satisfy
^ "
T3;8420h4
. Verify each battery charger supplies "B-RSA 2 E4001 300 asps at 2 {-1M} 130 V for 2 8, 18; months; hours.
LBs SR 3.8.4.7 - - - - - NOT E S - - - - - - - - -
- 1. The modified performance discharge !
test in SR 3.8.4.8 may be performed in l lieu of the service test in SR 3.8.4.7 i oncCper2601sjgths. Once p;r 3-0-38 l 50 ;;;;nths. 0 3.8.4-10 i l
- 2. erifyJtegettgeentEduring MODES *3Rh l
l 5fL6;opwith s..;11 not he cerfer;;;d i u h Survei,len;;yretof.Gloaded;-TW 43.8-2033 ~~ D C 1. 2. 3 r L :'l cver. ;rci.t ;;,*y b; teken ;;r unpi;nned events th;t 3.8 50 sati:;fy thi:; 0",. 0 3.8.1-20 CP
........................................... mumammmmmmmmme Verify battery capacity is adequate to 18J.nnthy _
supply, and maintain in OPERABLE status, BB;j the required emergency loads for the design duty cycle when subjected to a battery service test. (continued) CPSES Mark-up ofNUREG-1431 -ITS 3.8 3.8 25 in989
-.. . . - .. .- .~ . - -
i DC Sources-Operating i 3.8.4 ; l i l l i SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY l 1 SR- 3.8.4.8 --- -
- m e ----- 3.8 50 0 3.8.1 20 cp l (yemggg
$N$EN4ff--r7_ g b13M'Tggg7py((
I
@~'CC S3.8420 @
DE$N.'.cr. credit
...r...... . . ...
;;;[55 t$kN'-$r
..... ... ., ...i ; O j
j
........................................... J
'l l
Verify battery capacity is > 80
- of the 60 months :ga )
manufacturer's rating when subjected to a " performance discharge test or a modified M ; performance discharge test. l 10 18 months i wheri' battery 13.8-1fd shows degradation or has reached 85% of B-expected life l with capacity !
< 100% of
, manufacturer's rating M 24 months when battery has reached 85% of ;B4 the expect'ed life with capacity 2 100% of manufacturer's rating
. CPSESMark-up ofNUREG-N31 -1TS 3.8 3.8-26 U29/99
J ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: - Q 3.8.2-02 CP APPLICABILITY: CP 1
- f. REQUEST: CP B-PS
- ITS SR 3.3.1.12 What is the justification for deleting parts d & e of this NUREG's surveillance?
Comment: - The licensee should provide an adequate justification, or retain the NUREG language. i FLOG RESPONSE (original): ITS SR 3.8.1.12 is converted from CTS 4.8.1.1.2f.5).' Parts d and e are not included in CTS 4.8.1.1.2f.5) and may be excluded from the ITS on that basis alone. In addition, essentially the same features are tested by ITS SR 3.8.1.9 which supports not adopting the new requirements of STS SR 3.8.1.12. i
~
FLOG RESPONSE (revised): ITS SR 3.8.1.12 is converted from CTS 4.8.1.1.2f.5). Parts d and e are not included in CTS 4.8.1.1.2f.5) and may be excluded from the ITS on that basis alone. In addition, essentially the same features are tested by ITS SR 3.0.1.0 SE18j1;j9, which supports not adopting the new requirements of STS SR 3.8.1.12. ATTACHED PAGES: ) None, i l
I
< . ADDITIONALINFORMATION COVER SHEET p,
ADDITIONAL INFORMATION NO: . Q 3.8.4-19 . APPLICABILITY: CP i i~ REQUEST: L Bases for ITS SR 3.8.4.7, STS Bases markup page B 3.8-53 Bases for STS SR 3.8.4.7-Bases for ITS SR 3.8.4.8, STS Bases markup page B 3.8-54 Bases for STS SR 3.8.4.8
% The Bases for ITS SRs 3.8.4.7 and 3.8.4.8 state, "The SR is modified by a Note.
This Note does not allow the surveillance to normally be performed in Modes 1, 2,3, or 4. This Note does not prohibit the application of LCO 3.0.5 or the performance of this SR to restore equipment operability." This is a proposed
- l. . difference with the Bases for corresponding STS SRs 3.8.4.7 and 3.8.4.8. The
! Bases cannot modify tha TS.L The prohibition on performing this SR in Modes 1 and 2 is all inclusive, and cannot be negated by a Bases statement. This is an Issue that must be resolved as part of TSTF-283. L Comment: Revise the submittal to provide the appropriate justification or conform to the STS. l
. FLOG RESPONSE (original): See response to Comment Number Q 3.8.1-20 CP.
- FLOG RESPONSE (supplement): .The Bases for SRs 3.8.4.7 and 3.7.4.8 have been revised such the Bases description for the mode restriction notes reflects the CTS and the revised ITS 1 (see the response to O 3.8.1-20 CP in this letter). l ATTACHED PAGES: I Attachment 14, CTS -3/4.8 - ITS - 3.8 ;
l. ' ~ Enci5B B 3.8-53 and B 3.8-54 I l l.- i 0
.. . . - .- ~ . - - - -. .. =
I l DC Sources-Operating B 3.8.4 BASES , SURVEILLANCE SR 3.8.4.7 REQUIREMENTS (continued) The modified performance discharge test is a simulated duty cycle consisting of just two rates: the one minute rate published for the battery or the largest current load of the duty cycle. , followed by the test rate employed for the performance test, both , of which envelope the duty cycle of the service test. Since the ! ampere hours removed by a rated one minute discharge represents a very small portion of the battery capacity, the test rate can be changed to that for the performance test without compromising the results of the performance discharge test. The battery terminal voltage for the modified performance discharge test should remain i above the minimum battery terminal voltage specified in the l battery service test for the duration of time equal to that of l the service test. i l A modified performance: discharge test is a test of the battery l capacity and its ability to provide a high rate, short duration ] load (usually the highest rate of the duty cycle). This will often confirm the battery's ability to meet the critical period of the load duty cycle, in addition to determining.its percentage of rated capacity. Initial conditions for the modified performance discharge test should be identical to those specified for a service test addittuP;tysfdis' hetgeIrateEmustrenvelope.;the c_ duty 3&l@fs)heIs'agiceLtestdfithelmod,1fjed1 performance dischatapitestissipeffgesedagitieumalarytce: test. 7 T UDO Wi40 KJ2 Bat 10Cthe l T Q-3.8.1 20 CP
- . _ _ _ . ~
i
.......... . .. . .. ..... ,~........, ..~ ..........~ ....
' ::'T. ~'2. 2. ., :
*~ 1.".';" . '"L... .':. : '.'.:,".' "L.*:'. ."r.
. .. ".". .,*,C. .. .'. ~".s"':" .
SR 3.8.4.8 A battery performance discharge test is a test of constant current capacity of a battery, normally done in the as found condition, after having been in service, to detect any change in L the capacity determined by the acceptance test. The test is intended to determine overall battery degradation due to age and usage. A battery modified performance discharge test is described in the Bases for SR 3.8.4.7. Either the battery performance discharge (continued) CPSES Mark-up ofNUREG-H31 Bases -ITS 3.8 B 3.8-S3 1/29M9
m F DC Sources-Operating B 3.8.4 BASES i test or the modified performance discharge test is acceptable for satisfying SR 3.8.4.8: however, only the modified performance discharge test may be used to satisfy SR 3.8.4.8 while satisfying the requirements of SR 3.8.4.7 at the same time. . i The acceptance criteria for this Surveillance are consistent with ; IEEE 450 (Ref. 9) and IEEE 485 (Ref. 5). These references ! recommend that the battery be replaced if its capacity is below 80% of the manufacturer's rating. A capacity of 80% shows that ! the battery rate of deterioration is increasing, even if there is i ample capacity to meet the load requirements. The Surveillance Frequency for this test is normally 0 3 s.4 20 l 60 months. If the battery shows degradation, or if the i battery has reached 85% of its expected life and crxity i: c 100* cf the nauf=turcr'; retirsi, andicapacityds3J00*lof thelmangfactutorisitatjng3the Surveillance Frequency is reduced to
-la 18 months. However, if the battery shows no degradation but has reached 85% of its expected life, the Surveillance Frequency is only reduced to 24 months for batteries that retain capacity 2 100% of the manufacturer's rating. Degradation is indicated, according to IEEE 450 (Ref. 9), when the battery capacity drops by more than 10% relative to its ayeragg capacity on CP 3.8.G-1 the previous performance test or when it is 210% below the I manufacturer's rating. Tte n irc x rcic: erc Tttis i frgquefhqEigconsistentwiththerecommendationsinIEEE450 (Ref. 9).
Thh M is modified by a _ iStn0tel48fSIt0lVetify 0'3'8'1'20 CP thfi&wa1_ = a s. - d $ X 3 1 5 N f @ M it N D tei g nLe, i offdl
- sv.w.
"' " '17 * ~ . .!"' I'l l ' "'_'C, '~" ' " ",'I' "_ *!!! _' "'"' !!L _ . . . < _
g"' C_ '.,.r' Z. ' ' ".' ...,T..
'.2. ".. .!" ".". ". l'.~ '.m".' C_'. .' ". ". e".;,? 2. .
' ' " ' " ' ' " ~ ' " "
REFERENCES 1. 10 CFR 50, Appendix A, GDC 17.
- 2. Regulatory Guide 1.6, March 10,1971.
- 3. IEEE308191(.
- 4. FSAR. Chapter 8.
5.- IEEE48519_7J. (Continued) CPSES Mark-up ofNUREG-1431 Bases. -ITS 3.8 B 3.8-54 ' 1/29M9
a I L l i l T ADDITIONAL INFORMATION COVER SHEET I ADDITIONAL INFORMATION NO: APPLICABILITY: CP, WC, CA Q 3.8.10-01 CP !
- Q 3.8.10-01 WC l s Q 3.8.10-01 CW l 3 - Q 3.8.10-01 DC ~ {
j REQUEST: CP. . DOC 03-06-LS CW(3.8.10-01) _ JFD 3.8-45 ITS LCO 3.8.10 )~ WC(3.8.10-01) . STS LCO 3.8.10 C . CTS 3.8.3.2 - Bases for ITS LCO 3.8.10, STS Bases markup
- page B 3.8-85
, STS LCO 3.8.10 specifies,"The necessary portion of the AC, DC, and AC vital bus electrical
, power distribution subsystems ..." Corresponding ITS LCO 3.8.10 specifies, "The necessary
'* portion of the Train A or Train B AC, DC, and AC vital bus electrical power distribution subsystems ..." JFD 3.8-45 states that the' power distribution systems have been revised to 1
. retain the CTS requirement that one train shall be operable when shutdown. Corresponding . I CTS 3.8.3.2 states, "As a minimum, the following divisions of electrical buses shall be~ l i energized in the specified manner: ..." DOC 03-06-LS merely restates the proposed change.
t Comment: This LCO does not seem to be consistent with the Bases for LCO 3.8.10 or I .. . LCO 3.8.2. The LCO indicates that gust train of AC; DC, or AC vital bus electrical power ~
; Li s required. .However, the Bases for LCO 3.8.10 as well as 3.8.2 indicate that a second ' .j
} train of AC, DC, or AC vital bus electrical power may be required. This inconsistency
- needs to be addressed.1Also, Action A.1 is an allowance to declare required features . 1
[ inoperable that is based on two trains of electrical power being required. Action A.1 is I l not appropriate for the LCO as written. JFD 3.8-45 and DOC 03-06-LS do not explain 1 f- why the proposed difference is. acceptable. ' Revise the submittal to provide the
' appropriate justification for the proposed difference.
p L FLOG RESPONSE: (original) For DCPP see response to Comment Number Q 3.8.10-04.
- For CPSES, Callaway and WCGS, the ITS will be revised to reflect the CTS for the
. requirements associated with power supplies for supported systems during shutdown FLOG RESPONSE: - (revised) The markups associated with the CTS and ITS for this change
- are being restored to the version provided in the' original license amendment request. However, the enhancement provided for-DOC 03-06-LS-26 is retained; and, a new Bases modification is
.. provided to clarify that only one train of Class'1E AC and DC power and distribution is required to support equipment during shutdown conditions.
ATTACHED PAGES:
~
Attachment 14,j CTS -3/4.8 - ITS - 3.8
. Enct 2 . 3/4 8-13 and 3/4 8-19
., , ,a., -, . . .a
( - l i I Enci 3A 7
- Enci 38 - 4-Enct5A ' 3.8-17,3.8-27,3.8-35 and 3.8-39
. Enci 5B - B 3.8-34, B 3.8-34a, B 3.8-35, B 3.8-57, B 3.8-57a,~ B 3.8-71, B 3.8-71a,. !
. B 3.8-72, B 3.8-84, B 3.8-84a, B 3.8-85 and B 3.8-85a Encl 6A - 6 ;
' Enci 88 7 I
4 W l 1 l' L l-4
ELECTRICAL P0ldER SYSTEMS A.C. SOURCES SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 ' As a minimum, the following A.C. electrical pc.;r ;;ur;cs shall be OPERABLE:
- a. One circuit between the offsite transmission network and the Onsite Class 1E Distribution System,(gggggggggyFI308 Egg;;B4and IE D L1) Day fuel tank containing a minimum volume of 1440 gallons of fuel, 101E01F;
- 2) A fuci stcr;;; systc cent:ining a ;;ini;;;;; volu:: cf 05.000 ZG"j; g;11;r.3 of fuel . ;nd 70199fS]
ag) -A fuel transfer pump 2 and-MaWeiiTXDelEStoG9eISystestforJtheT OPERABLEidieselfgeneratof 109 A c0&tS{ftjggM31RisuBlVO.lumejofz75j.000lgaRgns;ofif uel cP 3.8 005
.NEK2j{ 2)$1be31$1Mgyentory191thT;a?lubeIoH21eveltEaneyeM1]
~ he$cismun11prel;oD1thejlubelol]LdipgicKEar!d e y01M8d T53ff$$1%AMATJa;RZa ,4G^.Ciftps_sutelG80Ipjsfg7foCag1_eastione~ ~~
l E1aW8Mratt91tytta 101E48WQ
-APPLICABILITY: MODES 5 and 6. )
1 48 M 0 3.8.3-01 CP ACTION: ,
- a. With less than.the above minimum required A.C. electrical power
" sources OPERABLE, immediately suspend all operations involving CORE ALTERATIONS positive reactivity changes, movement of irradiated. fuel
__ _____ ____. , _ ... m
.M. fH. ,i.U..JRM.,.R.1_*"***"d*3Reih3
,__2.
_..__m_ , . . , _._____ [e p ;py -& J "i ' "" . ."t' ' "
- 1"" _" 1.'." , !!""' 2" ' L . '" _ ' ": : _ " '"' " ? , . _ .
gly 4g- ]l C "2 1._ " "" _ " '. " "_' _ "r" '
- a . "' r '_ " " " " '_ ,' '! " ',,'"m ; '_' . . _* '_'I "' " ' " '_ _ "" ' " " *
"gg a *;"' ""?", ,"_U.";
;"".'.l 7_ ,.
,,.,,... ..;..r' t?"". ;1._;I!._. ;; ' !!_".
,; ?".."'
; 77g L
"_ ' "M , , $. .
l'_' ;;;;; or.. gqg. ,
.. ......., . ....t . ".7.. . .us ,,
vessel fle,r.;;. immediately initiate corrective action to restore the @jg required sources to OPERABLE status as soon as possible. ErI15g DWfRMNDNRRItfRDEtniiGLs3 dig $01 6_. mmrmemnremiwwsen
- b. With the' fuel oil storage system total particulate contamination not e 4
within limits, restore the storage system fuel oil particulate vQ1iO1FMd C contamination level to within limits within seven (7) days or immediately declare the associated diesel generator. inoperable and perform ACTION a. If less than the minimum required A.C. electrical power sources are OPERABLE.
- Markup ofCurrent TS3N.8
^
3N.8-13 10989
D.C. SOURCES . SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.2.2 As a-minimum, tw; 125" 0.0. :t:tien bett;ric; cf en; tr:in end t 1;;;t ;n; :::cciet;d full ;;p ;ity ch:rger f;r ;;;h r;;;ir;d bettery :h:11 iEb M $ be-OPERAlH:E-M3R 4 L.W j P'4; -
. k _ ._ M M ,
y ."+ g . " ",,L
- o.3.8.10 01 cP APPLICABILITY: MODES 5 and 6.
ACTION: With the required battery train and/or required full capacity chargers inoperable. Lamediately;declatezaffect_ed'ir_equired; feature (s); inoperable;or ;02h19yLS1 immediately suspend all operations involving CORE ALTERATIONS. positive reactivity changes, or movement of irradiated fuel; initiate corrective
' action to restore the required battery train and full capacity charger to OPERABLE status as soon as possible. nd within 0 hour;. . .
d;pr;;;;ri;; :nd vent th; ";;;ter 0;;1:nt Sy;t;;;; through :t 1;;;t : 2.00 701Y5EAM
;;;;r; inch V:nt.
SURVEILLANCE REOUIREMENTS 4.8.2.2 The above required 125V D.C. station batteries and full-capacity chargers shall be demonstrated OPERABLE in accordance with Specification f02-15ELS1
' 4.8.2.1. IloteG@urve1])an.ceIRequitegehtsI(J812111cli,^3dslefan,diflateinot Clf! RIME 8Mol@gerfor!!!!!!J l
p i ! CPSESMarkup ofCTS 3N.8 3N.8-19 12989 l-
l l CHANGE NIABER MiHC DESCRIPTION SR 3.8.3.3 would require that DF0' properties of new and stored DF0 are tested in accordance with, and maintained within the limits of, the Diesel Fuel Oil Testing Program. In addition, the SR 3.8.3 Bases will contain additional descriptive material regarding the DF0 testing requirements of the current SRs. These changes are consistent with NUREG 1431. 4 01 38 LG The fuel oil storage tank cleaning SR would be moved to licensee controlled documents. This change is consistent with NUREG 1431. 01 39 LG The fuel oil transfer piping leak test SR would be moved to licensee controlled documents. This change is ! consistent with NUREG 1431. i The requirements for staggered DG testing would be deleted I 01-40 LS 25 and replaced with a requirement to test each DG every 31 days. Deleting staggered DG testing is consistent with NUREG 1431 results in no change in the frequency of testing for each DG. This change is acceptable because studies have shown that staggered testing has negligible impact on equipment reliability. It'is not as safety significant as originally thought, it is difficult to ; implement operationally, and may increase the chance of human error test performance. 01-41 M' .e AC Sources - Shutdown LCO would be changed to spech that the required AC sources must be powering, or capable j
- of powering, the required AC distribution busses.
This change is an additional restriction consistent u s.10 01 e with the implicit assumptions for operation during shutdown conditions. This change is consistent with NUREG 1431. (See also CN 03 06 LS 26 01~42 M Not applicaDie w CTZ. Sa wnversion comparison table (enclosure 38). 01 43 M The AC Sources Shutdown Action statement would be revised to specify that the offsite circuit must be capable of supplying power to the required onsite buses. This assures the single operable circuit is performing a ~ vital function. Explicitly requiring entry into the applicable actions of LC0 3.8.10 clarifies the appropriate action to take if the onsite distribution train becomes de energized. This is consistent with NUREG 1431.
~
. .01 44' LG' The AC Sources Shutdown action statement reference to crane operations with loads over the spent fuel pool would be moved to licensee controlled documents. Eachl]1Cbjtse( CPSES Description of Changes to CTS 3N.8 ' 7 U29/99
CONVERSION COMPARISON TABLE - CURRENT TS 3/4.8 Page 4 cf ' 9 - DESCRIPTION , Diablo Canyon Comanche Peak Wolf Creek Callaway 01-36 A f.a tb ;. r fata lif.t; cf Mt c. 0.0 ;;: 0.0. Lip) -.t;i- ,; c -.teir. ; c _ WA VesBN usal f ai r li;tts. M/A fxta li;it;. WA 01-37 The specific requirements for sampling new diesel fuel oil Yes Yes Yes Yes LG (DFO) prior to addition to the storage tanks and for sampling the stored DF0 once every 31 days would be moved
'to the Diesel Fuel Oil Testing Program, which would be referenced by ITS SR 3.8.3.3 and described in ITS 5.5.13.
01-38 fuel oil storage tank cleaning requirements, would be moved Yes, moved to FSAR Yes, moved to TRM '0,
. ;i ';i-ir.; C5 Yes.
LG to licensee-controlled documents. yesanopelito,J53 moved to rSAR 01-39 Fuel oil transfer piping leak test, would be moved to. Yes. moved to FSAR Yes, moved to TRM No, not in CTS No. not in CTS LG licensee controlled documents. 01 40 The requirement for staggered DG testing would be deleted Yes Yes Yes Yes LS-25 and replaced with requirement to test each DG every 31 days. m ,% A 01-41 The AC Sources - Shutdown LCO would be changed to specify Yes /"Yes Yes - Yes M that the required AC sources must be powering. or capable s 0-3.8.10-01 CP l of powering, the required AC distribution busses. 01-42 CTS 3.8.1.2, CTS 3.8.2.2, and CTS 3.8.3.2 applicability Yes No, maintain CTS No. maintain CTS No, maintain CTS M would be revised to add, "during movement of irradiated fuel assemblies.* 01-43 An AC Sources - Shutdown action statement would be revised Yes Yes Yes Yes M to specify that the offsite circuit must be capable of supplying power to the required onsite buses, and, therefore, to all equipment required to be operable in the applicable modes. 01-44 Reference to crane operations with loads over the spent Yes: moved to FSAR Yes, moved to Yes: moved to USAR Yes: W 3 0-3.8.2 05 CP LG fuel pool would be moved from the LCO action to licensee- Beses-FSAR moved controlled documents. to FSAR 01-45 The requirement to initiate corrective action is expanded Yes Yes Yes Yes M to match the applicability of the TS. 01-46 A note would be added to the AC Sources - Shutdown action Yes Yes Yes Yes A statement to enter the Distribution Systems LCO if one required train has no electrical power. 01-47 The SRs required for AC sources operability in Modes 5 and Yes Yes Yes Yes LS-4 6 would be revised to include only those SRs which are applicable. The Note listing exceptions to SR required for Modes 5 and 6 in current TS 4.8.1.2 would be revised to include additional SRs. CPSES Conversion Comparison Table - CTS 3M.8 H29)99
AC Sources-Shutdown l 3.8.2 l 3.8 ELECTRICAL POWER SYSTEMS ] 3.8.2 AC Sources-Shutdown LCO 8.2 e following AC electrical power sources shall be OPERABLE:
- a. One qualified circuit between the offsite transmission network and the onsite Class 1E AC alpetrical oower 3.845 dhtribution4bsystents+ required by LC0 3.8.10,'
CDistribution Systems-Shutdown"; and j - 0 3.8 10 1 CP
- b. One diesel generator (DG) capable of supplying one train of tha ^ 9 += c1= " :.E C electrical power distribution subsystemtst J quired by LC0 3.8. f APPLICABILITY: MODES 5 and 67 -
- 3.8-29 u Caring ;;;;;;nt of irradiated fuci assc;blics.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME l A. One required offsite ---
-- NOTE - -- - l circuit inoperable. Enter applicable Conditions and Required Actions of LC0 3.8.10, with-ene the
- ?3.845 ?" i required train de energized
- ~-
as a result of Condition A. j l A.1 Declare affected Immediately required feature (s) ! with no offsite power I available inoperable. OR A.2.1 Suspend CORE Immediately ALTERATIONS. l AND. (continued)
. CPSES Mark-up ofNUREG-1431 -ITS 3.8 3.8-17 U29/99
DC Sources-Shutdown 3.8.5 l-3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources-Shutdown
-LCO 3.8.5 N CThpiriggTRWhDC electrical power ,
3.8 45 l hERBL " to supportQ electrical power distri)g$ttain"OGthe DC required u;1on subsystentst 0 3.8 10 i cP by LC0 3.8.10. " Distribution Systems-Shutdown." i APPLICABILITY: H0 DES 5 and 67 l Ouring ;;;;;;nr,t of irradicted fuel es;;;blic:.
#3.8529 L::.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Onc or ;;;;re r"equired A.1-1 Declare affected Immediately $3.8-45%~ DC electrical power ' required feature (s)
'~-
subsystems inoperable. inoperable. ?EDWJ QR A.2.1 Suspend CORE Immediately
. ALTERATIONS.
88Q A.2.2 Suspend movement of Immediately irradiated fuel assemblies. AND A.2.3 Initiate action to Immediately suspend operations involving positive reactivity additions. ANQ (continued) l l CPSES Mark-up ofNUREG-1431 -ITS 3.8 3.8-27 1D989 i I E I
Invr.rters-Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Inverters -Shutdown LCO 3.8.8 G w train?E oC R8 invertersshallbebPERABLE ; to suppo he onsite Class 1E AC 3.8-45 vital bus e trica power distribution 0 3.8 10 1 cP subsystentst required by LC0 3.8.10. " Distribution Systems - Shutdown. " i APPLICABILITY: MODES 5 and 6- ) During ;cv;;;nt of irradicted fuel es;;;blies. 3.8-29'a ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare affected Immediately inverters inoperable. required feature (s) BE] inoperable. i E A.2.1 Suspend CORE Immediately ALTERATIONS. I ARE A.2.2 Suspend movement of Immediately irradiated fuel assemblies. AND. A.2.3 Initiate action to Immediately suspend operations involving positive reactivity additions. ARQ (continued) CPSES Mark-up ofNUREG-1431 -D53.8 3.8-35 1/29/99
Distribution Systems-Shutdown ! 3.8.10 I 3.8 ELECTRICAL POWER SYSTEMS ; 3.8.10 Distribution Systens'-Shutdown : 1 LC0 3.8.10 %essary portion otNhesTraittAMorFTrairiDC. DC. and AC vital bus elec<;rica s puwer aistriounoT 3 8'45 i subsystems shall _ l be OPERABLE to support ne trairilogequipment Q 3.8-10-1 CP l requires to be OPERABL . l APPLICABILITY: MODES 5 and 6-Ouring ;;;cv;;;r.t of irradicted fuel Os:::blics. l3.8_-29A ACTIONS l CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare associated Immediately AC. DC, or AC vital supported required bus electrical power feature (s) j distribution inoperable. 4 subsystems inoperable. ; A.2.1 Suspend CORE Immediately 1 ALTERATIONS. M l A.2.2 Suspend movement of Immediately irradiated fuel assemblies. M l A.2.3 Initiate action to Immediately l suspend operations involving positive
- reactivity additions.
M (continued) CPSES Mark-up ofNUREG-N31 -ITS 3.8 3.8-39 1/29/99
. . - . - ~ . - - . -
1 AC Sourcss-Shutdown ; B 3.8.2 l BASES (continued) APPLICABLE analysis assumptions and design requirements are allowed SAFETY ANALYSES within the Required Actions. This allowance is in j (continued) recognition that certain testing and maintenance activities must be conducted provided an acceptable level of risk is not exceeded. During MODES 5 and 6, performance of a significant number. of required testing and maintenance activities is also required. In MODES 5 and 6, the activities are generally planned and administrative 1y controlled. Relaxations from MODE 1, 2, 3, and 4 LCO requirements are acceptable during shutdown modes based on: i
- a. The fact that time in an outage is limited. This is a risk prudent goal as well as a utility economic consideration.
- b. Requiring appropriate compensatory measures for certain conditions. These may include administrative controls, 4 reliance on systems that do not necessarily meet typical design requirements applied to systems credited in operating MODE analyses, or both.
- c. Prudent utility consideration of the risk associated with multiple activities that could affect multiple systems.
- d. Maintaining, to the extent practical, the ability to perform required functions (even if not meeting MODE 1, 2.
3, and 4 OPERABILITY requirements) with systems assumed to function during an event. In the event of an accident during shutdown, this LC0 ensures the capability to support systems necessary to avoid inmediate difficulty, assuming either a loss of all offsite power or a loss of all onsite diesel generator (DG) power.
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i AC Sources-Shutdown i l B 3.8.2 l I j i BASES (continued)
^
- Y. :
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w 'mgyet6ry3g I &810n1 M M9ei M Theing t Q&W*I sign.:someIcases3 ppparef6Iate3tsedWeh?inc . Jgetrets[ designed;td idgggg!Kgtta131thelMredidefensKjn;depthi The AC sources satisfy Criterion 3 of th MC l'clicy Stat;. ant ' l 10CfR50361@l2M11}. l LC0 e offsite circuit; capable of supplying the 'onsite Class 1. , power distribution subsystem (s) of LCO 3.8.10, " Distribution ' Systems-Shutdown." ensures that all required loads are powered
'from offsite power. An OPERABLE DG, associated with _
the distribution system train required to be OPERABLE b - LC0 3.8.10, ensures a diverse power source is available 0 3.B.10 01 & H to provide electrical power support, assuming a loss of the offsite circuit. Together. OPERABILITY of the required offsite circuit and DG ensures the availability of sufficient sources to operate the unit in a safe manner and to mitigate the consequences of postulated events during shutdown (e.g. fuel handling accidents). CPSES Mark-up ofNUREG-1431 Bases -ITS 3.8 B 3.8-34a 109/99
E AC Sources-Shutdown B 3.8.2 BASES (continued) i The qualified offsite circuit must be capable of maintaining rated fregtency and voltage, and accepting required loads during an accident, while connected to the Engineered Safety Feature (ESF) bus. Qualified offsite circuits are those that are i described in the FSAR and are part of the licensing basis for the unit.
~
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The DG must be capable of starting, accelerating to rated speed (4411RBlyandvoltage,andconnectingtoitsrespectiveESFbus l on recejpt det;; tion of a bus undervoltage sjgnal. This sequence must be accomplished within 10 seconds. The DG must be capable of accepting t!g required loads manual]f within the
;;;;.cd 1;; ding ;;qu;re; intervals, and continue to operate :
until offsite power can be restored to the ESF buses. These ! capabilities are required to be met from a variety of initial i conditions such as DG in standby with the engine hot and DG in ; standby W M1JJd! at ambient conditions.
~
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. CPSESMark-up ofNUREG-1431 Bases -ITS3.8 B 3.8-35 129/99
DC Sourc:s-Shutdown B 3.8.5 l ~
-B 3.8 ELECTRICAL POWER SYSTEMS
- B 3.8.5 - DC Sources-3hutdown j
, 1 a BASES BACKGROUND A description of the DC sources is provided in the Bases for i LC0 3.8.4, "DC Sources-Operating." APPLICABLE The initial conditicns of Design Basis Accident and CP 3.8.G 1 SAFETY ANALYSES transient analyses in the FSAR, Chapter 6 (Ref.1) and Chapter 15 (Ref. 2), assume that Engineered Safety Feature - systems are OPERABLE. The DC electrical power system provides normal and emergency DC electrical power for the diesel generators, emergency auxiliaries, and control and switching during all MODES of operation. The OPERABILITY of the DC subsystems is consistent with the initial assumptions of the accident analyses and the requirements for the supported systems' OPERABILITY. The OPERABILITY of the minimum DC electrical power sources during MODES 5 end C :nd during .;n ;;nt of irradicted fuci o.3.8.5 03 s x 21ics ensures that:
- a. The unit can be maintained in the shutdown or refueling condition for extended periods; l
- b. Sufficient instrumentation and control capability is available for monitoring and maintaining the unit status; and
- c. Adequate DC electrical power is provided to mitigate events )
postulated during shutdown, such as a fuel handling accident. IK6@EsMd3l[Qtteltechhihl afeci . I' u=a.::.a MRM10
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DC Sourcas-Shutdown B 3.8.5 BASES i . . ;: . .; . . p,, . ... - 4v. .
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The DC sources satisfy Criterion 3 of the N"C "clicy St;t; ;rt 1REFRS0]dM QQ # Hiti. i LCO- TheMDC electrical power subsystc:;;;. c ch =bsy;te;;; consisting of two batteries, atll_ east;one fullj:apacity, battery charger per battery, and the corresponding control equipment and interconnecting cabling within the 0 3.8.10 01 CP train, are required to be OPERABLE to support;one . 1; talin igired trek:; of the distribution systems required OPERABLE by LCO 3.8.10, " Distribution Systems-Shutdown." This ensures the availability of sufficient DC electrical power sources to operate the unit in a safe manner and to mitigate the consequences of postulated events during shutdown (e.g., fuel handling accidents). Irpstmilimelectat@HMwerMIMribigg@systesits supporMRtM!rpeltraggorgIMeetdS12WetlisystagMienitM sRonwagenetRMWDIMMI.isnientimsomgsopsystensis2psMag iconoonente
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. CPSESMark-up ofNUREG-H31 Bases -ITS3.8 B 3.3-57a - H29/99
~ _ - - .
. ~ ~ - . - . - . . _ - . - .-- - - - . . - - .
Inverters-Shutdown
- B 3.8.8 B 3.8 ELECTRICAL POWER SYSTEMS I i
[ B 3.8.8 Inverters-Shutdown I b BASES
- l. .
BACKGROUND A description of the inverters is provided in the Bases for ; LC0 3.8.7, " Inverters-Operating." l 1 e i APPLICABLE The initial conditions of Design Basis Accident (DBA) and CP 3.8.G 1 SAFETY ANALYSES transient analyses in the FSAR, Chapter 6 (Ref.1) and ! Chapter 15 (Ref. 2), assume Engineered Safety Feature , i systems are OPERABLE. The DC to AC inverters are designed to ! provide the required capacity, capability, redundancy, and reliability to ensure the availability of necessary power to the l Reactor Protective System and Engineered Safety Features ! Actuation System instrumentation and controls so that the fuel. Reactor Coolant System, and containment design limits are not exceeded. The OPERABILITY of the inverters is consistent with the initial assumptions of the accident analyses and the requirements for i the supported systems' OPERABILITY. The OPERABILITY of the minimum inverters to each AC vital bus during MODES 5 and 6 ensures that:
- a. The unit can be maintained in the shutdown or refueling condition for extended periods:
- b. Sufficient instrumentation and control capability is available for monitoring and maintaining the unit status; and
- c. Adequate power is available to mitigate events postulated during shutdown, such as a fuel handling accident.
adesgassesgatang*Ieste11mgI3tralRitgchnjcal [ MUN Es6hh.ta Krisk 0 3.8.10 01 CP asItegenspyatsitsemicmsp6ciffeatmganelttain 9IAtMEBR1tsatR11agatGdgs!!gishagalmAttions.us alpixelsmangBeTataltspfmandspelsasialiartistjordRTt4 t RN114MBRIGBld113BIBN1 pee &WRINEENGPRM11K!N!t 6mui Sh ggLtjgggg!1 pag;gsresidmegoppottgL9yltg1181Eele@rtcal CPSESMark-up ofNUREG-1431 Bases -ITS3.8 B 3.8-71 1M989
l Inverters-Shutdown B 3.8.8 BASES (continued) DBer'NgSlassRE@gygffgeistposiand i LM ' i 0 3.8.10 01 CP
- .:;? *
. . Q :j SQpt; M pg qp; n.. . , .
.. . . a n.:9;Mbetion^:ere metM4MfMEDE#Wesselectrjemstoget"21herplastistaft masourcesIsod;tlistititutionisystems tesarethatwwmessed aeve1Loffeinisaliristgis; maintained '
(RequentigNfalyed@Xasintaining:aldesired; defense:1n i' depth)RThe3}evellof,1 detail?;involvediin itheiassessment;w11.1 varyiwi.thitheisignificancelofjtheiequipment-being'.supportedJ~"In some cases;tprepared; guidelines:areiused;which;1ncl_ude: controls designedjoimanageltisKandzetainjheldesited.defenselin; depth! The inverters were previously identified as part of the distribution system and, as such, satisfy Criterion 3 of the NP,C Policy Stetac;.t 1_0CMWJc)_(2Rij. I I l l' CPSESMark-up ofNUREG-1431 Bases -ITS3.8 B 3.3-71a 1/2989
Invirt rs-Shutdown B 3.8.8 ; I BASES' (continued) i i LCO 9 Rih J A. i :; c . d. " , : T . :: s a+ .? r m WP*' Q 3.8.10 01 CP m f . ' gl
.m, ll..
. . .. . y 6 M JJ8; E The inverters ensure the
- availability of e.ectrical power for the instrumentation for systems required to shut down the reactor and maintain it in a safe condition after an anticipated operational occurrence or a postulated DBA. The battery powered inverters provide i uninterruptible supply of AC electrical power to the AC vital l buses even if the 6.9 kV safety buses are de energized. !
OPERABILITY of the inverters requires that the AC vital bus be i powered by the inverter. This ensures the availability of I sufficient inverter power sources to operate the unit in a safe ! I manner and to mitigate the consequences of postulated events during shutdown (e.g., fuel handling accidents). _~ req @MEMitaEbusIelectricallpowetdistrjbution subsystem 3$1styported;byjene3 rain 20fj1nvertersqWhenithe secondgs@pystemunf#cattphbusletectticali poweridistobution is;needed2 p pppottaedundant; required;systess gequipmentzend l compongRtMbMgpA$tgrAirEMEbeigyergizedlfttistahylpyajlab]( sourcenstmitahimacurtgEgusNQAMEfpglgpothe ngli f u e++ m e .~ e .30!maisislamiassaggg - l 9ppl lth8Bimituimtda!g j
.. . . . . _ . + _ . . . . _ .
e - _ . , . . - ~ _ _ , . - ! gl8 g :,+ : >.W3q4 0 - f( ryC$$jDl%%M@ Dgi" . x.W m.n. .O . h o. : 4 2 M AftetegG i l APPLICABILITY The inverters required to be OPERABLE in MODES 5 and 6 end , , during m.wat of irradisted fx1 :::dlic: provide assurance l l that:
- a. Systems to provide adequate coolant inventory makeup are available for the irradiated fuel in the core;
- b. Systems needed to mitigate a fuel handling accident are available:
l
- c. Systems necessary to mitigate the effects of events that L-- can lead to core damage during shutdown are available; and (continued) l l
CPSESMark-up ofNUREG-1431 Bases -ITS 3.8 B 3.8-72 1/2989
Distribution Systems-Shutdown B 3.8.10 B 3.8 ELECTRICAL POWER SYSTEMS B 3.8.10 Distribution Systems-Shutdown BASES BACKGROUND A description of the AC, DC, and AC vital bus electrical power distribution systems is provided in the Bases for LCO 3.8.9,
" Distribution Systems-Operating."
. APPLICABLE The initial conditions of Design Basis Accident and SAFETY ANALYSES transient analyses in the FSAR. Chapter 6 (Ref.1) and Chapter 15 (Ref. 2), assume Engineered Safety Feature (ESF) CP-3.8.G 1 systems are OPERABLE. The AC, DC, and AC vital bus electrical power distribution systems are designed to provide sufficient capacity, capability, redundancy, and reliability to ensure the availability of necessary power to ESF systems so that the fuel, Reactor Coolant System, and containment design limits are not. exceeded.
The OPERABILITi of the AC, DC, and AC vital bus electrical power distribution system is consistent with the initial assumptions of the accident analyses and the requirements for the supported systems' OPERABILITY. The OPERABILITY of the minimum AC, DC, and AC vital bus electrical power distribution subsystems during MODES 5 and 6,
;r.d durir.; ;;;;nar.t of irredi;ted fuci ssdlics ensures that:
- a. The unit can be maintained in the shutdown or refueling condition for extended periods:
- b. Sufficient instrumentation and control capability is available for monitoring and maintaining the unit status; and
- c. Adequate power is provided to mitigate events postulated dur ing shutdown, such as a fuel handling accident.
ItCadditieggo3h920W10eseM#Eestablj shed; b.ffhe technicaljepec1Dgg1MfiittuGp] antistaffcausti al so 0 3.8.10 01 CP waagenhutMcIJAgisRamtmr1ealaupiiertJ~ts ~~ e81rita11tisimpreceptawyngyguel
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tautsaggggggggglBI"3hilWRflJdlRtLtiotts11Esupported2M p byJthe~J:echnicq}Jggcjffggj;1gpend300jpeentinot; req 0 ired:by 1 _ the:specjficat1MSBEspDtributetito21skifeductionfandst CPSESMark-up ofNUREG-1431 Bases -ITS 3.8 B 3.8-84 in9M9
, ._ _. __ _ _._ . ~ . . . _ . .
l 1 1 l Distribution Systems-Shutdown l '- B 3.8.10 l BASES (continued) l l l Q 3.8.10 01 CP M' ; . . '. 3;; ' ; { , , . ',, - '
-ygg3
( _ 80$MMus, inot?,avaitattig 12(that ,
.nfenegreemeAnnessenatassegmessex:ptov$deathe ;
noseutgeestigetsupportrignespimassetzessesses:these alterneseJpeusEsources?and distribution systems;tolassure1that the: desireedeve1% spinal!Osk;is; maintained;(frequently referreditoLas'esintair!1ng[aldesired defenselin: depth)MThe levelrofidetail'; involved;1n;theirasiessment:iwill:l vary with the significance.;ofithe requipmentibeing: supported TSRIn;some Lcases? l' prepared.; guidelines? ate:used Mich; include;; controls; designed,to
;;M_st_andreta1Etheldesired;defen.se;1nidepth; The AC and DC electrical power distribution systems satisfy Criterion 3 of the NRC I'clicy Statement 10CFR50;36(c)(2)(ii). ,
a s. CPSESMark-up ofNUREG-1431 Bases -ITS 3.8 - B 3.8-84a 1/29/99
i l l l Distribution Systems-Shutdown . B 3.8.10 I ; l I l BASES (continued) l LCO - Various combinations of subsystems, equipment, and components ! are required 0FERABLE by other LCOs, depending on the specific l
. plant condition. Implicit in those requirements is the required l OPERABILITY of necessary support required features. This LC0 l explicitly requires @nergization of the portions of one2trainJof the electrical distribution system aEnecessary to support OPERABILITY of eqp339tpErequired systems, equipment, and I
components-all specifically addressed in each LC0 and implicitly required via the definition of OPERABILITY. 0 3.8.10-01 CP Maintaining these portions of the distribution system energized ensures the availability of sufficient power { to operate the unit in a safe manner to mitigate the consequences of postulated events during shutdown (e.g., fuel handling accidents). i l The'.ACat'^ . Idistrjbution1 subsystems 2are7 supported by one.trajn, ectricalf powerisourceslasltequired: by;LCO sis;z Eshut_domy i Ih83FMidtsM10ectticalroowerad1stelbagion.12subssstem11.s N'
#3629'8M4RIRl$yStMMf809e$tdatd NkN bc z . . .u . e. . s a y;.; e geH. + omeggmentsa Mfim:m J H . zw 3 J$pche$httShejgggitM j,.3 .,, ~mHBbRummEWMMi-glct, x - . .- :.;. % s.W . : v f A . , t $ .
J e , .r_;y; ;; y_,7' - ). : g.: ,;,y ; .H-._. ; 3, . .,. y ; y e } 5 jbe g..m , . . . - <m .. . ,,,,..y ..7 , e . ...;.. ,
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l-M1*"11350ttsGRBIR AD11@letumustituum2#MarmppMapMmelett"M g gdun # U M M u M M ot.O g capabJg j electtiglimmasshSta= oLpettptamastertMharetyaMRisaletSpiteitly l requiteMBtingslinggggC9PRABAIUlM1Rhmpse3the ( c.__-:r r __7 5 :;.sm*w MeM M 2the (continued) CPSES Mark-up ofNUREG-1431 Bases -ITS 3.8 B 3.8-85 1/29199
t 1
- 1. Distribution Systems-Shutdown B 3.8.10 i
BASES (continued)
^
Q 3'8'10 01 CP l L4WPDH DA WEE 9EBBBB!al l APPLICABILITY The AC and DC electrical power distribution subsystems required to be OPERABLE in H0 DES 5 and 6, cr.d durir; ;;;;;;xr,t of . irradiated fuci ;;;;;;ilic:. provide assurance that: l l
- a. Systems to provide adequate coolant inventory makeup are available for the irradiated fuel in the core;
- b. Systems needed to mitigate a fuel handling accident are available:- !
- c. Systems necessary to mitigate the effects of events that can lead to core damage during shutdown are available; and
)
l I (continued) 1 CPSESMark-up ofNUREG-1431 Bases -ITS3.8 B 3.3-8Sa 129/99
CHANGE NLASER JUSTIFICATION l l look for damage to or degradation of the battery that would ; affect the operability of the battery, and that any damage or ' l degradation that does not affect battery operation would not fail ; L the surveillance acceptance criteria. This change is consistent ! L with industry Traveler TSTF-38. E 3.8 42 Not applicable to CPSES. See conversion comparison table l- (enclosure 6B). 1 3.8 43 For one DG inoperable, while in MODES 1. 2, and 3. the requirement in the CTS to confirm the OPERABILITY of the TDAFW j pump is part of ITS LCO 3.8.1. ACTION B.2 and a Note has l been added to make this requirement clear. Thelidentica}, l notelhasibeenladdedjjo3equiredLActionsJi2 and;C1'1B 0 3.8.1 01 CP 3.8 44 Not Used.
.8.1041 &
3.8 45 The specifications for power scources and power distribution systems are revised to retain the CTS requiremenpat vue u am ouusystem) shall be OPERABLE when aown. LCOs 3.8.5. 3.8.8 and 3.8.10 are. revised to require
" Train A or Train B" to support "one train" of equipment required to be OPERABLE. In several locations, the reference to -
l
" subsystem (s)" is changed to " subsystems" or " subsystem" and the i phrase "one or more" is deleted to be consistent with the overall i CTS requirement that one train be OPERABLE. The CTS requirement l to have one train of power sources and power distribution .
OPERABLE provides the support needed to operate in a safe manner j
- and to mitigate the consequences of postulated events during 1
3.8 46 N;t ;;pli;;ble t; CPSCS. 0;; cacac ;ic7 ca;;ri;;r, t;blC CP-3.8 004 Cril; r; Z. EMtMerAc am1.53Melgaisi13i!bu.1d:be J medifJie@CtMR10lR!sRMEEBlutte!RmWMits1M chE91K#RBoJt M2]!BWamD3Nif6eMitc31tayity , q[su_ _ W .I M fgotngtg L5.Eof
- v. 2
._tGiBAMME_BRElgingD._MGatt3R_elem.
. .- .- .t.ee.itenutnl4 11gits. Oxp ;f Hgwf e MM_Jjgylty reeiressenamnsimismissumpsttframergineer4th' enarinesi.tc e theEmlu!6]Dfit!IpgiMEcGttepl38nd3@g are_11ab31ty3GtguaBM!BRLap111tygtaccuratejyatonitoring cMIgt!MEwdvig 3.8 47 Not applicable to CPSES. See conversion comparison table (enclosure 68).
- E8fjg Nogappl1_cableitsiqSESMTpoJLver11o[compatison,Itable (encloisore;sen CPSESNUREG-1431 Differences -ITS3.8 ^ 6 1/29M9
.. m .. .
1 CONVERSION CONPARISON TABLE - ITS SECTION 3.8- 7 *f 7 ' NUMER DESCRIPTION Diablo Canyon Comanche Peak ' Wolf Creek Callaway 3.8-43 A Note is added to ITS 3.8.1. ACTIONSZgg B.2 and C.J;to Yes .Yes Yes Yes state that the TDAFW pump is required to meet the redundant features requirement fr r.: CC :.g.:/c in Node 1. 2, 3.8.1- 11 CP and 3 consistent with th 05, ;;;nSTSiReyjhNete . 3.8-44 Not Used. N/A N/A N/A N/A I 3.8-45 The specifications for power scources and power No. See CNs 3.8-13 Yes Yes Yes distribution systems are ravid to retain the CTS and 3.8-15. g ; ramt- _ m one train (subsystem) snali be OPERABLE ] m
~
/ when shutdown.
3.8 46 Footnote (c). of ITS Table 3.8.6-1 would be modified to Noj: At hdopting lutEG Ne Yes Yes nom , retain '.";lf C. a current TS requirements for using - por.di_ng; pergitini charging currert as a substitute for specific gravity measurements. 3.8-47 The ITS LCO 3.8.3. 00folTION B requirement for a 'per Yes No. No No diesel generator" lube oil storage system is revised to reflect the current design of a shared system between units. 3A48 Lheseichengar,LocityJtedutxtinangeaumitme@E forAbg Ng No les No Loa (Shedder a anAgegpnglioedAWJAMil,5)1,jpjG)ES Q 3.8.2-14 NC Kagd,L62 33-49 ItametmatsdiMis.Noten;8hs Yes No No pq I3NKipmen$ctoile31!$algi[pM490m$4ptEctigstfalfot 0-3.8.4-07 interittericonnections11ErnespedJan3Isig4Mizland . SILAsd152 3.8 50 The., Notes a toRsurveillegoe;tMitgomMLwould 2bgjud1[ led yee%5eeJFD Yes Yes les ! lolmake,themicensigteg$LWJ)LCTSitequjirements,1 3,8;53 CPSES Conversion Comparison Table -ITS3.8 1)29199 ; r
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: 3.8.B-02.p APPLICABILITY: CP REQUEST: !- p. Bases Pace 3.8-31 l SRs 3.8.1.21 and 3.8.22 Comment: It appears that these SRs might be better located in Section 3.3 of the TS. l 1 Response (supplement): The surveillances associated with the sequencer have been evaluated and it has been determined that these surveillances belong with the specification that requires the sequencers to be operable and which provide required actions when the LCO is l not met. The sequencer surveillances should remain in ITS 3.8.1. l The calibration SR for_thg.safelghsequencer;is deleted because it is a duplicate of ITS SR 3.8.1.18. The TADOT SR is renumbered. l l ATTACHED PAGES: See response to NRC Ouestion Q 2-13 l l
l l 1 1 ADDITIONAL INFORMATION COVER SHEET l 1 ADDITIONAL INFORMATION NO: CP-3.8-005 APPLICABILITY: CP i REQUEST: 1 Revises the markup of CTS 3.8.1.1 (LCO and ACTIONS I. and J.) and CTS 3.8.1.2 ( LCO and ACTIONS d. and e.) to match the CTS markup with changes approved in j CPSES License Amendment 60/46. Only wording and format changes are involved. Since
~ there were no technical changes, no changes to the ITS are required.
ATTACHED PAGES: Attacnment 14 CTS -3/4.8 ITS - 3.8 l Enci2 3/4.8-1,3/4.8-4,3/4.8-13 and 3/4.8-14 Enci 3A 3 Enci 3B - 1 l l 4 i I l' l I 4
3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.'1 A.C. SOURCES-OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following{C. ;1;;tricci p;w;r scur:Is}shallbe OPERABLE:
- a. -Two physically. independent circuits between the offsite transmission network and the onsite Class 1E Distribution System, and
- b. Two separate and independent diesel generators, each with:
-1)' A separate day fuel tank containing a minimum volume of 1440 gallons of fuel, A ;;p;r t; Fu;l Stor g; Sy;t;; ;;nt ining : ;ini;u; y01-01-Al' ~'
vela;; cf 00,000 gallen; cf fuel, and A separate fuel transfer pump , g 109 A a> 3.8 005 j A rueE.stor.ageISys.terfogeach; diesel;genetatoriconta1%n_ >j alminimumyolume;of186j o0_0;ga11 onsTofJfuel - AIllabeTe11)linW$oG31thZal'l ubeIo1El evelp_'a!1 eVel 37 K0144843 NEW belowit!!ejlowltunJ1931Eop.ithe;1 ube.loj];di psti ck,j7 and NEW Gt;GMZCXM;&;R@ssute218EpsigIfoCAt 198.StfMMYOM 0 3.8.3 01 CP 1
- APPLICABILITY: MODES 1, 2, 3, and 4. l ACTION: l
- a. With'one offsite circuit of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirement
' 4.8.1.1.la. within 1 hour and at least once per 8 hours thereafter. If cither dicaci ;;ncretor h;s not b;;G
^
t$'1'-03338
' ~ " "
su;;;s; fully t;sted within the p :t 24 h;urs, d;;;n;trat; its OP "J.0ILIT by perfer;ing Surv;ill;n;; "scquir;;;nt 4.0.1.1.2;.4) for ;;;h ;;;h dicsci ;;ncreter. ;;perot;iy, witP 21 h;;r:.'- Restore the offsite circuit to OPERABLE status within 72 hours MjdJtD&tfRCdeyE(CEdistMVPKol 2~01404Mj
~
fJi1HMitDIlpttitJ;0 lor be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
.;; ring perfer;;n;; ef Ourvcill n;; ;;tivitics es r;quir;;;nt for 1011' 03-LSj
' ~ ~ ~ '
ACTION :t t;;;nt:, th; ;ir roll t;st shell not b; p;rfor;;d. J Markup ofCurrent TS 3N.8 3N.8-1 H29/99
.- .- - ~ . . - - - -. - - .- . . . - - - . - . - . .. -.
4
^
ELECTRICAL POWER SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) ACTION (Continued)
- g. With the fuel oil storage system total particulate contamination not within limits, restore total particulate iO1401?A'/j
; contamination to within limits within 7 days or immediately declare the associated diesel generator inoperable and perform ~
the applicable ACTION for an inoperable diesel generator (s).
- h. With the properties specified by Surveillance Requirement
- 4.8.1.1.2d.2 for new fuel oil that has been added to the fuel h01401 ~Ad
~
oil storage inventory not within limits, confirm that the stored fuel oil properties are within limits or restore the stored fuel oil properties to within limits within 30 days or immediately declare the associated diesel generator inoperable and perform the applicable ACTION for an inoperable diesel generator (s). (01s49;LS] 1NEW Withithe FeeEStorageiyo1&MauwhantW1 y:12 86,00 gal jgteatenthanlegd ?f 74:6iO;galloris fifuel?"ota crie eramners "VJ#aAE;;;iCQWrei. _ , torace Syst' E sthie EMI900Egallons_Jsltn1n;MT houts __
==-1 r +2 dtesel /
c se; c~%2rO=*'ZC#RfC _- medwpvMog C_an is _~_ isy f amf**1PEMEffl%@JM ,1 109 A CP 3.8 005
$1 W1tT;Ftpb$to ym;ypaputem SEtO74'600Zgallonslo ,
lessif9Mai ute1FMieclarelthe associgp6M otMppppfJiltlestg63performithelapp]icab_ 8CTION"htlagpfgggtgl@Djitj@pgtetyggfD] MEN W,ith;tlig@G$unam ingggggggLg16CMeteM13beJ oy .. thei m FXO er M.migh ytte;end 500<484Q pffg L} m p g .,;p apffitoj W. 8 ' N Y 'yhy
. v a c: c ..
y';:t.%u iW Y N ;O'.. P "'f3($Dhef.]b]M y}QC E MW
$'h M:L i- --- O - 1^.""r__, _A - e .n f a ssoc -
W ~- Q 3.8.3 01 CP
,, ,,,9E,..
dies _e
- - -- -.~. mm.re_-- waW"i ate ~d
$eFAggninop2Lbig
~
M DecL utredMeggg.(s@tth353ffGMip0We.y3yal] able
.estenguistsmedandantRsRtrad;;&aturet snis 2 Inopec 2"01 ~~ - fi[Q ino 123rimptuftMal14t,#1erfa#tneMUMlfpow(Gts Macuttentst:11gia@eng121tymfagluJdant; 1 21.H tequL _
pneltgRfeatgeGT@tedundantEfealutg2 lDl0Df.M1WitrWRthe2JMMEiA 0 3.8.1 01 CP co_ns,1(etedigygguiteci n
)
l Markup of Current TS 3N.8 3N.8-4 U29/99 1 1
ELECTRICAL POWER SYSTEMS l l A.C. SOURCES l SHUTDOWN LIMITING CONDITION FOR OPERATION L S 3.8.1.2 As a minimum, the followin K.L. : r OPERABLE: 1;;trical p;;;r :;;j;;; shall be
- a. One circuit between the offsite transmission network and the L Onsite Class 1E Distribution System.. MLC01(}l8E2 and i
L
- b. One diesel generator w+tM depabWef?llgiplyf9elanaltrairl, l ortheI455.11NMfMlllET@is$tjjNation;Sy!)ppAtegitediby [ 1 41.g l
@ME3 Q 3.8.10 01 CP
- 1) Day fuel tank containing a minimum volume'of 1440 gallons of fuel.
L
, 301012AP] l i 2) A fu;l :ter;;; ;y;t;;;; ;;ntaining : ;;;ini;;; v;1u;;;; cf 1 05.000 K;;;; g llen: ef fu;1. ;nd >01449-LSj B2) A fuel transfer pumpg JZcNEAEFuellStorwm aorane,UrtMDLt 101esewim m. 109 A l
containigglalaintauslvolueelofd5J090; gallons 3fjfuel CP 3.8 005 NEWSJKilube!b1Eillglatet'yNitMaBubeToil51eVelEagleV.el?13 ..
' ~ ~
belowiti!![TicaLS861eveEonithe2Lubelo11[dipsti. ckyand ?01h48%j gr@ EWE:t;-t;EMCTM;iV;rlPresstfre]tJ18_05ps,ig1forlat.J.least one ,01:48-(j 1 star, ting 11rireceiveta l APPLICABILITY: MODES 5 and 6. 1 48 M l 0 3.8.3 01 CP ACTION: i
- a. With less than the above minimum required A.C. electrical power I sources OPERABLE. immediately suspend all operations involving CORE i '
ALTERATIONS, positive reactivity changes, movement of irradiated fuel l b $NNi 3 ;;;r t.,; fu;' ster;;; Lngly . Or cr;;; ep; ration with 1 ! pec., en .,ithin 0 h;;r;. d; pres:uriz; :nd v;nt th; R;;;ter 0;;1ont ?,01%% 1 Sy;t;; thr;;;h ; grc ter then er ;qu:1 to 2.00 ;;;;r; inch v;nt. In ; addition, when in "00E 5 with th; r;;;ter ;;;1:nt 1;;p;-net fill;d. ?.01 % XyQ cr in "000 0 with th; w:ter 1;;;l 1;;; then 23 f;;t ;b;;; the r;;;ter l' v;; sci fieng;, immediately initiate corrective action to restore the {01 @ 'd required sources to OPERABLE status as soon as possible. Entetl lippitab]EAgapsg5ARRIMfM4tIFnMfEW113liENWeCifde3 @lM@j ggsmirespH3Dharingitttewout redytfatstgmfej F
- b. With the fuel oil storage system total particulate contamination not 71 01 .?013ApJ within limits, restore the storage system fuel oil particulate contamination level to within limits within seven (7) days or immediately declare the associated diesel generator inoperable and perform ACTION a. If less than the minimum required A.C. electrical power sources are OPERABLE.
Markup ofCurrent TS 3M.8 3N.813 1/29/99
^
l
l l l ELECTRICAL POWER SYSTEMS
' LIMITING CONDITION FOR OPERATION (Continued)
EMM 1
- c. With the properties specified'by Surve111ance' Requirement i 4.8.1.1.2d.2 for new fuel oil that has been added to the fuel oil storage inventory not within limits. confirm that the stored. fuel oil properties are within thirty (30) days or immediately declare the associated diesel generator inoperable and ,
.per form ACTION a. If less than the minimum required A.C.
! electrical power sources are OPERABLE. ! IEW M if;,22With? ?S35temivolumeN1 h **+ " ; G ;t; Q [01i49&LSi L SuggggaII . fifuel I a . x .- -- - . a store - f , 18191855CVoluterof e751900 ID00Psh . .;3 gately2 cec nara *
- lese E M etotdnoperabl.
5053.; d p fore K I 1 09 A l CP 3.8 005 l ! eg WithXtheiFue115toragelSystes;vol umelequalsto?. 65. 600ll gal l ons l or, 1essMjamediatelyLdecl areithellassoci ated;di esel, generator 2inopetablelandlperfotalACIIONE NEWJHWithithelDGilube701Rinventory.IldsisIthanfalleVe131MbeloW3Ethe? low;rup . leveEbutsgreater3hanta11eveU12abovelthe;endTofathellube oil 3"014 '~"j 48AM dipstj clu r,estore.ttheslube3tliinventorygto:Ma31 eveJ 11E, bel owlthe
.lowirun11 evel #1 thin 381hpursloglamediatel yidecl are:theTassoci ated diese]igenerateN1Jgp69hjA2
!gntythelpsyttjggmplyrgpreysurgp8g;gjgggg .....,
_ l
...,..n- ... . -+. ... - - - ..
l U - K ;gjpgedigte ._jyl@glareithelassociatedidiese]I3enyator, [,3j[301cP inopetable, . . .. .. SURVEILLANCE REQUIREMENTS 4.8.1.2 The abe;e required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the requirements of E01E4ELS$ Specifications 4.8.1.1.la and 4.".1.1.2' (an;- l (18IljE281JJ43MMHb)lejdJfJl.1),f.t ] for Specifiestion L l-
' IlotelthatstheIspecifjpations3181121;2a5)Ef.2)Rf3)Rf.4).(except[ auto 3 101147?LSd sequencing)SUEandIM)lareyrequitedito beloperable3D_u.tido2not tequir.eldemonsttatinglogeta_b111tylb,ylp Aermjpg;theselsuftve111ancesg i
. gb "P L - AL m=a=J11==** Lam & JLa-amal Jm mu&- J J &- 9A - - m & L ei fmm
-l/_.
,. n'"n. ""llI. .'2. m.. ' " " '. .' !. .! ' .I " .' '!!. _. ' I. .*.. *. ._ ."E.
. usm!
ov '..y".'.I..a. ' *.o ICI_'?!", v . !!.2:.2 "_'". s"01i31W,1
- L.'s:
e;;r.d refuelir,; Out;;; for 'Jait 2.
- Markup ofCurrent TS 3M.8 3N.8-14 1/29/99 1
I
.w + + , ., - - -- r . . - - -
1 L CHANGE I l NLMIER EC DESCRIPTION This change is acceptable because it would assure that appropriate actions are taken to assure the OPERABILITY of J required systems before requiring a plant shutdown and is consistent with NUREG 1431. l l 01 07 LS-3 CTS SR to start all DGs simultaneously at least once per i 10 years or after any modification which could affect DG starting interdependence would be revised to delete the requirement to' perform the SR during shutdown. This test l does not require the DG to be paralleled and loaded onto L the offsite source. In addition, the DG remains OPERABLE during this SR. This change is consistent with NUREG-1431. [0108 LS 8 CTS 3.8.1.1 Action requirement to demonstrate DG l operability within 8 hours would be increased to 24 hours. l Extending the time required to demonstrate the operability of the remaining operable DGs would allow 24 hours to determine the operable DGs are not inoperable due to a ; common cause failure or demonstrate operability of the ! remaining operable.DGs by testing. This proposed change avoids unnecessary DG testing. This change euld allow the same time period (24 hours) for determining j operability of the remaining operable DG(s) as the Action ! I for one inoperable DG currently allows and is consistent with the recommendations of GL 8415. " Proposed staff actions to improve and maintain diesel generator reliability". This proposed change is consistent with NUREG 1431. s 01 09 8
%t und RerBeisitheFearkEofiCTSI3;83!13Ea_
ACHOREMREBERRtiO352EDXiRTELMIMIaB d."35]$mMSWhigggrWth3:h84006 m?Menelet!60M6 Mon 1Dlording 6 01 10 M Not applicable to CPSES. See conversion comparison table (enclosure 38). 01 11' TR 1 Several CTS SRs would be revised to clarify that an actual actuation signal, as well as a test or simulated signal. ! may be used. This change would allow satisfactory automatic systems actuations from actual signals to be used to fulfill the requirements of the SR. This proposed L change is acceptable because data obtained during the L performance of the surveillance must still be obtained and the acceptance criteria must be satisfied before credit can be taken for the actual actuation, e.g., an unplanned l event. 1 CPSES Description of Changes to CTS 3M.8 3 1/29A9
- CONVERSION _COMPARIS0N TABLEi. CURRENT TS 3/4.8. Page 1 cf f 9.-
TFr4NICAL SPECIFICATION CHANGE APPLICABILITY -l. c DESCRIPTION- ~Diablo Canyon - Comanche Peak Wolf Creek Callaway 01-01 TS requirement for minimum diesel generator (DG) day tank Yes Yes Yes Yes A fuel oil volwe and fuel transfer pump would be moved to taproved Technical Specification (ITS) Surveillance Requirement (SR) 3.8.1.4 and SR 3.8.1.6. TS requirements for diesel fuel oil storage would be moved to ITS LCO 3.8.3. 01-02 Footnote would be revised to specify "may* instead of "shall" No: CTS footnote. No. CTS footnote Yes Yes A in reference to the DG start being preceded by an engine specifies "may." specifies "may"_ prelube period to minimize wear on moving parts that do not. get lubricated when the engine is not running. 01-03 TS 3.8.1.1 Action requirement to demonstrate DG operability Yes Yes No. Already No. LS 5 with an offsite circuit inoperable, or;;two offsite circuits deleted per Alread E 0-3.8.1-02 CP l iroperable, r wit' ;r. ;ff;ite ;;r;;1t r.d : DC i.;;.u ;,k. Amendment 101 y is deleted. delete d per Amendment 112 01-04 This proposed change would revise TS 3.8.1.1 to require No: 10-day A0T .Yes Yes Yes N that with one or more A.C. electrical power sources . proposed as Change-inoperable, all A.C. electrical power sources be restored 01-32-H. to operable status within 6 days from the time the first A.C. electrical power source became inoperable. 01 05 This proposed change incorporates the NUREG-1431. provision Yes Yes Yes Yes LS 6 of " determining the operable DGs are not inoperable due to a cosmon cause failure " which avoids unnecessary testing of operable DGs. into Actions for one DG inoperable and for one DG sad an offsite circuit inoperable. In addition, the-requirement to complete DG testing regardless of when the inoperable DG is restored to OPERABLE status would be deleted. 01-06 Current TS 3.8.1.1 Action allowed time for verification of Yes Yes Yes Yes LS-7 required redundant feature operability would be increased from 2 to 4 hours. The requirements would be moved to LCO 3.8.1 Action 8. and the shutdown requirement would be replaced with a requirement to enter the required feature's action statement. 01 07 The CTS SR to start all DGs simultaneously would be revised Yes Yes No. Not in CTS No Not in CTS LS-3 to delete the requirement to perform this SR during shutdown. 01-08 The CTS 3.8.1.1 Action requirement to demonstrate DG Yes. Yes' Yes Yes LS-8 operability in 8 hours would be changed to 24 hours.
,.!n n? f NeHsed Revjsetthtmar$up_oJRhhbMdtE0 pndMONs NMNo N/AYeq N/ANo NMg A 1A4DddOJnJLCEARih2ddAggedLAILTigggggsc4AM9 CP-3 8-005 mRtchitheiqLeergpatitiLcheggesmge!stliigg$gSAicense -
m ___ Amenement 60/46.9 CPSES Conversion Comparison Table - CTS 3N.8 1/29/99
_ _ . _ - . _ _ . _ . . _ _ - - .. _ . _ _ _ _ - . _ . ~ . _ . . _ . . _ _ . _ _ _ _ l I l 1 l-1 ADDITIONAL INFORMATION COVER SHEET ! ADDITIONAL INFORMATION NO: CP 3.8-006 (new) APPLICABILITY: CP I REQUEST: In response to an NRC question concerning TS 3.3 which applied to CPSES only,
' CPSES made changes to JFD 3.8-37 in ITS 3.8. JFD 3.8-37 is also applicable to other FLOG
- plants, however, the changes made by CPSES were not applicable to the other plants. To correct this situation, new JFD 3.8-54 was created which is identical to the CPSES revised L version of JFD 3.8-37 and JFD-37 was restored to the original version. JFD 3.8-54 is applicable to CPSES only, while JFD 3.8-37 no longer is applicable to CPSES.
ATTACHED PAGES: Attachment 14, CTS -3/4.8 - ITS - 3.8
. Enc!SA 3.8-15 Er,cl 6A 5 and 6a Enci6B 6 and 7a s
1
- 7. g -
i I l r l'
AC Sourc:s-Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SRETjE131 QQ1lipteZM'igp!!lGCRg 183!!lRtj 2
%)
$ e n.cyt j Q 2 13(3.3) 0 3.8.8 01p EL.#-3.5UUb)
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ST@lM BASIS] \ i- CPSESMark-up ofNUREG-1431 -ITS3.8 3.8-15 1/2989 i
CHANGE NUMBER JUSTIFICATION l
'(enclosure 68).
I I 3.8 33 NUREG 1431 LCO 3.8.3 Condition B. and SR 3.8.3.2 would be revised I to note use of a dipstick level for verification of lube oil - inventory consistent with the Comanche Peak CTS. The Lube Oil Level at CPSES is measured by a Lube Oil Dipstick and not by gallons of oil. Specific limits are outlined in the Bases. The current CPSES Technical Specification does not require measurement of Lube Oil Level.
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s_L1. r___1__..__ ens ; . suuiw g vi ew vous % vvi. l i 3.8 36 . Adds note, per current TS, that allows one SI sequencer channel l to be bypassed for up to 4 hours for surveillance testing I provided the other channel is operable. ;
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l 3.8 37 The [:cqcx;r urnillene requirc ~nt ] fre.;; ^urr;,t TS Sc; tion ! 9 ..1J L_ _JJ_J A_ AL. TTP TLJ_ J_ ____J_A__A .JLL ut iner* 9,/ W A 7.W www s %e ww us.www kw burw ass. s aa a e ad wvssw ad kwsib a E,a i rivv wu - j$1 M_.. 1 ..LJ_L _JJ_ _ $ ftM -_..J_.--1, f _ .a &L_ 1.7w . , nww. wiu u ws u wwwa usa cvv . v3w s # wis~ s a b a v1 wsav j _ en , _ _ _ _ _ _ _ _ _ . .
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.~ - J a. s. 2..w.t p;rfer ;n;; dischers; t;^t in ITS 0", 0.0.4.0 te b; p;rfered 0 3.8.4 10 in lieu of the scrvicc test in ITS Sa 3.8.'.7 at cr.y tir.c.
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- i. cst is ; t;;t th;t a v;lep;; th; ;;rvice t;:t with respect to th; discherg strent being greater th= or ;q=1 to th; service test, ad the =p heur r; ;= d is 1.rg;r. Thi; cha g; is
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gHdleLUDEgigpl5H]Egl3pMefglM0Le16Bli 3.8 39 ITS SR 3.8.4.6 would be revised for current licensing basis. The restriction to not perform this SR in H0DE 1, 2, 3, or 4 would be deleted. The battery charger test is not required to be performed during shutdown since the backup chargers could be in l service, maintaining the DC subsystem operable during performance of this SR. CPSESNUREG-1431 Differences -ITS 3.8 5 InM9
l-CHANGE NUMBER JUSTIFICATION m unr,-anumemenanmanneenrremeda
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r le a.ys W M h f 1SIW ]810 2211A Ladde( 3o " f 0-2-13(3.3) i c8 m X@ltf.3tJplgg$Mgl@81kHY cp.3.g.006 ofithe]lg&M4Atluencer$!j3This serve 1NasmsggggnBREMugSf1Dby&3121gunctfog] unit:1algasutsgEEBR!M!!sNds3mtesitriatidefineit.ta3 cope oDthemitxlem l l L I. i l. 1 CPSESNUREG-1431 Differences -ITS 3.8 6a 129/99
a CONVERSION COMPARISON TABLE.- ITS SECTION 3.8'. 6 ef 7 NLASER DESCRIPTION Diablo Canyon Comanche Peak Wolf Creek Callaway , 3.8-35 ";; ntis ;f 15 0.0.2. 5 0.0.5. IS 3.".0. ;;d !5 VesW}- Ne--Mfected Nor-Meeeted Nor - . . 3 I 2.0.10 mld k J ...d 0: ;dd ; r.;t; ;t;tir.; ^J ; !5 '00 ,,~;ifisti ,n ; ; 7., ;ific;ti .s ;-f AMeete 0.0.0 i; =t g li;dl;. ";i; i; ,,..1.t;r.t .;'th !r.d.-. i r.;t g lic ci; f;- 7.;t glicil; f ,- d Tr;.ci;r 57 30.ggggd fxl x.. ..t .:'"3 fxl x.. ./..g spee4M eetiene-we-not gli;21; f;- f;.;;l 'i movement-5 3.8-36 A note would be added in accordance with the CTS for CPSES ho Yes No No i that allows one SI sequencer channel to be bypassed for up to 4 hours for surveillance testing provided the other ' channe plRe. s
/ A f h 3.8-37 g; [C;e.. . 0";' .
c . . ..; 5 2 .3 ; d k ' ' ' 0; No; not in CTS 'VesMogiSeep Yes. Yes tk !5. 318:54 o . , , ,s ;
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s [ p- -- . 3.8-38 II:> a a.6. ^ .7 ^.,a t Z:M " '=1 =t u ="- 1 " Yes Ves-No Yes PR Ves-9! modified performance discharge test in SR 3.8.4.8 to be ! performed in lieu of the service test in SR 3.8.4.7 at any time. 3.8-39 ITS SR 3.8.4.6 would be revised for current licensing Yes Yes Yes Yes , basis. The restriction to not perform this SR in mode 1.
- 2. 3. or 4 would be deleted. ,
i Yes No No No i 3.8-40 ITS SR 3.8.1.7. SR 3.8.1.15. and SR 3.8.1.20 would be-revised per DCPP CTS to add a requirement to verify DG ; achieves proper speed within 10 seconds after start signal. 3.8 41 The phrase. *that could degrade battery performance." would Yes Yes .Yes Yes f be added to clarify the purpose of the battery inspection. ; This change is consistent with industry Traveler TSTF-38. 3.8-42 An Action is added to the LCO for an inoperable autaamatic No. not in CTS No. not in CTS Yes Yes load sequencer to immediately declare the affected DG and ! offsite circuit inoperable. [ CPSES Conversion Comparison Table -ITS3.8 1/29A>9 ! a _ _ . _ _ . . _ . _ _ , _ _ . _ . _ . _ _ _ _ _ _ _ _ _ . . _ _ . . . . _ _ _ _ . . . . _ _ . _ _ _ _ - __._.m_________._m._._ - ___mm___..._ _ _ _ _ _ . _ _ _ . . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ __
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. CONVERSION CONPARIS0N TABLE - ITS SECTION 3.8 . 7 eof 7:
- Diablo Canyon Callaway NLDBER DESCRIPTION- Comanche Peak .Wo1f Creek [;
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; ham W:ckha,9Actaenessa Mdmoettstalitojanuseetth&ill 2 M IDE requirements!appucepeltettheiloss;0f;cRe;0tithelbuses Q 3.8.E -4y that*WRIEN a sustana ga _sa vogacreeing;Is y p ps les u Q-3.s.4 u E 'i mm.--> i . an-- hsummma
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M 53 m*a i naA-w yes NonSee'EIL3,,83M l1g15penERa8sStEl l Q-3.8.1 33 oc g ' (g u_m.m.i St.+.m - m ehman -shamue= = n=== llo; snot 11rLCTS Yes DtJERAL24AaN M tp1 M canhyg . Kannth11msannhamnetnadstnasamanrtsflPRIARII ITY In$iN g.2-13(3.3) .t pkthisol_ CP 3.8-046 -- ; suom131anceiwesamlnesteAttosLESBlable4JL@fuistjgnal 1 Unit. alla,thnetssghnjiiulatinedht I scopatofathecs utN1DAlgggggqialsgiincjylada j
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! 1 ( .. ADDITIONAL INFORMATION COVER SHEET ! l ADDITIONAL INFORMATION NO: CP 3.8-007 (new) APPLICABILITY: CP )
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