ML20117J491

From kanterella
Jump to navigation Jump to search
Forwards Status of Tech Spec Issues from SER Section 16, Resolutions to Issues & Listed Revised Draft Tech Spec Pages.Description of Unresolved Issues Requested
ML20117J491
Person / Time
Site: Hope Creek 
Issue date: 05/13/1985
From: Mittl R
Public Service Enterprise Group
To: Butler W
Office of Nuclear Reactor Regulation
References
NUDOCS 8505150123
Download: ML20117J491 (61)
v • d • e


Text

)

Public Servce Eutrc and Gas Company 80 Park olaza, Newark, NJ 07101/ 201430-8217 MAILING ADDRESS / P.O. Box 570, Newark, N J 07101 Robert L. Mitti General Manager Nuclear Assurance and Regulation May 13, 1985 t.N

+.%

N Director of Nuclear Reactor Regulation S. Nuclear Regulatory Commission 1 Norfolk Avenue sda, Maryland 20814 4:

Mr. Walter Butler, Chief

-Licensing Branch 2 91 vision of Licensing MPORT TECHNICAL SPECIFICATION ISSUES l

' STATION s

.rrent list which provides a status of t;

ification Issues identified in Section 16 l

.luation Report (SER).

Items identified as chose for which PSE&G has provided responses b

atation of status has been received from the

.ill consider these items closed unless notified

^

[

In order to permit timely resolution of items

(

ad as " complete" which may not be resolved to the a satisfaction, please provide a specific description s,

.ne issue which remains to be resolved.

s; Enclosed for your review and approval (see Attachment 3) are the resolutions to the SER Technical Specification Issues listed in Attachment 2.

Also enclosed (Attachment 4) for your use and incorporation into the Hope Creek Generating Station Draft Technical Specifications are five (5) sets of the-following revised Hope Creek Generating Station Draft Technical Specification god pages:

8505150123 850513 hI PDR ADOCK 05000354 l

y PDR MP85 81 02 1-vw h9% W A'I O The Energy People w

.n m

E' f

Director of Nuclear Reactor Regulation 2

5/13/85 Pages ix 3/4 3-37 3/4 8-25 3/4 8-29 3/4 3-40 3/4 8-26 3/4 8-30 3/4 3-43 3/4 8-27 3/4 8-31 3/4 8-24 3/4 8-28 These pages are submitted as Revision 4 to the Hope Creek Generating Station Draft Technical Specification and have been revised in accordance with the resolutions to the SER Technical Specification Issues provided in Attachment 3.

Also included are-copies of the updated Hope Creek Generating Station Draft Technical Specification List of M

Effective Pages (LEP).

Should you have any questions or require any additional information on these items, please contact us.

Very truly yours, b.L. WXY 9 Attachments C

D.

H. Wagner USNRC Licensing Project Manager (w/ attach.)

A. R.

Blough USNRC Senior Resident Inspector (w/ attach.)

MP85 81 02 2-vw t

l l

Attactnent 1 SER j_

TECHNICAL SER R. L. MITIL TO l

SPECIFICATION SECTION A. SCHWENCER ISSUE NUMBER SUBJECT STATUS IEITER DATED l

1 2.4.11.2 Service water intake temperature Cmplete 4/10/85 2

2.4.14 Closing of doors and hatches Cmplete 4/10/85 l

3 3.9.6 Pressure isolation valves Open 4

4.4.4 Thermal-hydraulic instability Cmplete 4/10/85 5

4.4.4 Single-loop operation Cmplete 4/10/85 l

6 4.4.5 Crud effects Cmplete 4/10/85 7

4.4.6 Icose parts monitoring system Cmplete 4/10/85 channel operability 8

5.2.2 Safety / relief valve (SRV) test Cmplete 5/13/85 program 9

l 9

5.2.5 Reactor coolant pressure boundary Capplete 4/10/85 l

leakage rates 10 5.4.6 Reactor core isolation cooling pung Complete 4/10/85 testing 11 5.4.7 Residual heat removal system pump Cmplete 4/10/85 operability 12 6.2.1.6 Torus /drywell vacutn breaker and Open vent system testing l

13 6.2.1.6 Vacuts breaker position indication Cmplete 5/13/85 accuracy 14 6.2.3 Testing of inleakage rate and draw-Complete 4/10/85 down time 15 6.2.4.1 Isakage testing for valves with Open resilient seals 16 6.2.6 Containment isolation valve leakage Open MP85 81 02 4-vw Page 1 of 4

m (Cont'd)

SER TECHNICAL SER R. L. MITTL 'IO SPECIFICATION SECTION A. SCHWENCER.

ISSUE NtNBER SUBJECT STA'IUS IEITER DATED 17 6.2.6, 6.7, Main steam isolation valve leak rate Open 15.6.5.2 testing 18 6.2.6 Various valve leak rates.

Open 19 6.3.4.2 Emergency core cooling system Cmplete 5/13/85 (ECCS) subsystem flow rates 20 6.3.4.2 ECCS subsystem operating sequence Cmplete 5/13/85 21 6.5.1.3 Water seal bucket drain tap Cmplete 4/10/85 surveillance 22 7.2.2.3 Testability of plant protection Complete 5/13/85 system at power 23 7.2.2.8, Anticipated transients without Open 7.6.2.2 scram mitigation 24 7.2.2.9 Reactor mode switch Conplete 5/13/85 25 7.3.2.3 Freeze protection of water-filled Open lines 26 7.4.2.3 Remote shutdown system operability open 27 7.6.2.1 Iow-pressure /high-pressure systems Open interlocks 28 7.6.2.3 Average power range monitor Conglete 5/13/85 electrical protection assemblies 29 7.7.2.2 Nonsafety-related equipment Cotplete 5/13/85 operability 30 8.3.1.3 Diesel generator connected loads.

Complete 4/10/85 31 8.3.1.7 Load sequencer logic complete 4/10/85 32 8.3.2.7 DC system monitoring Cmplete 4/10/85 MP85 81 02 5-vw Page 2 of 4'

, (Cont'd)

SER TECHNICAL SER R. L. MITIL TO SPECIFICATION SECTION A. SCHWENCER ISSUE NUMBER SUBJECT STATUS LETTER DATED 33 8.3.3.3.5 Testing of breaker time-overcurrent Complete 5/13/85 trip characteristics 34 8.3.3.4.1 Periodic system testing Complete 4/10/85 35 8.3.3.4.2 Load sequencer testing Cmplete 4/10/85 36 8.3.3.5.4 Testing of fuses Complete 4/10/85 37 9.1.3 Fuel pool cooling system pumps Open 38 9.2.1 Station service water punp testing Complete 4/10/85 39 9.2.2 Safety auxiliaries cooling system Complete 4/10/85 and reactor auxiliaries cooling system pump availability 40 9.2.2 Safety auxiliaries operability to open ensure diesel generator cooling 41 9.2.7 Control area chilled water systen Open availability 42 9.3.1, Air quality testing Complete 5/13/85 9.3.6 43 9.3.2 Core damage estimate procedure

'Ihis is a confirmatory item.

44 9.5.1.5 Fire watch Cmplete 4/10/85 45 10.2 Turbine steam valve inspection Cmplete 4/10/85 46 10.4.4 Turbine bypass valve surveillance Cmplete 4/10/85 47 15.2 Turbine bypass system and level Cmplete 5/13/85 8 high-water trip performance 48 15.4.9 Scram speed Complete 5/13/85 49 15.6.4 Primary coolant activity Complete

.5/13/85 MP85 81 02 6-vw Page 3 of 4 l

l

1 (Cont'd)

SER TECHNICAL SER R. L. MITIL 10 SPECIFICATION SECTION A. SCHWENCER ISSUE NUMBER SUBJECT STATUS IEITER IRTED 50 15.6.4 Main steam isolation valve closure Cmplete 4/10/85 time 51 15.9.3 SRV failure reporting Complete 4/10/85 52 15.9.3 Automatic depressurization systm Cmplete 5/13/85 logic I17D1W MP85 8102 7-W Page 4 of 4

ATTACHMENT 2 SER

. TECHNICAL SPECIFICATION SER ISSUE SECTION SUBJECT 8

5.2.2 Safety-relief valves test program 13 6.2.1.6 Vacuum breaker position indication accuracy 19 6.3.4.2 Emergency Core Cooling System (ECCS) Subsystem flow rates 20 6.3.4.2 ECCS Subsystem operating sequence 22 7.2.2.3 Testability of plant protection system at power 24 7.2.2.9 Reactor mode switch 28 7.6.2.3 Average power range monitor electrical protection assemblies 29 7.7.2.2 Nonsafety-related equipment operability 33 8.3.3.3.5 Testing of breaker time-overcurrent trip characteristics 42 9.3.1, Air quality testing 9.3.6 47 15.2 Turbine bypass system and level 8 high-water trip performance 48 15.4.9 Scram speed-49 15.6.4 Primary coolant activity 52 15.9.3 Automatic depressurization system logic DPD:az 5/10/85 MP85 96/07 01

ATTACHMENT 3

SER Technical Specification Issue No. 8 (SER Section 5.2.2)

Safety-Relief Valves ( SRV ) Test Program The nominal pressure setpoints of the SRVs are distributed in three valve groups with a minimum setpoint of 1,108 psig and maximum of 1,130 psig.

Total relief capacity at set pressure is approximately 105 percent of rated steam flow.

Before valves are installed, the SRV manufacturer tests the valves hydrostatically for response, set pressure, and seat leakage to certify that design and performance requirements j

have been met.

During the preoperational test program, specified manual and automatic actuation is verified, as recommended in R/G 1.68.

The valves will be removed for maintenance, are inspected and tested in accordance with ASME Code,Section XI.

The test program will be included in the plant Technical Specifications.

Responset HCGS Draft Technical Specification Section 4.0.5 provides the requirement for inspection and testing of these valves in accordance with ASME Section XI.

MP 85 64/07 7-mr a

SER Technical Specification Issue No. 13 (SER Section 6.2.1.6)

Vacuum breaker position indication accuracy Appendix A also requires that redundant position indicators be placed on all vacuum breakers with redendant position indication and an alarm system in the control room.

The vacuum breaker position indicator system should be designed to provide the plant operators with continuous surveillance of the vacuum breaker position.

The indicators should have adequate sensitivity to detect valve openings that would not result in leakage greater than that from a 1-in, diameter opening if all valves were at this maximum offset.

The applicant has indicated that each valve is equipped with redundant valve position indicators that indicate and alarm in the main control room.

The sensitivity of the indicators is sufficient to detect an offset greater than 0.01 in. at the valve centerline.

The flow through the eight suppres-sion-pool-to-drywell vacuum breakers with each offset of 0.01 is equivalent to the flow through a 0.5-in. - diameter hole, which is less than the 1-in. criterion in Appendix A to SRP Section 6.2.1.1.C.

The applicant has also indicated that the redundant position i

indicators are visually observed and verified at each l

refueling outage in accordance with ASME Code,Section XI, to confirm that the remote valve indications accurately reflect the valve operations.

The accuracy verification shall be in accordance with the instructions provided by the valve supplier and will be included in the Technical Specifications.

The staff finds this acceptable.

Response

HCGS Draft Technical Specification 3/4.6.4 requires test and calibration of the position indicator every 18 months.

M P85 90/07 1-mw

SER Technical Specification Issue No. 19 (SER Section 6.3.4.2)

Emergency core cooling system subsystem flow rates The NRC staff will require the applicant to test the ECCS subsystems (except for the ADS) every 9 2 days, in accordance with the Standard Technical Specifications (NUREG-0123), to show that specified flow rates are attained.

Also, the NRC staff will require that a test, in accordance with the Standard Technical Specifications, be performed every 18 months in which all subsystems are actuated through the emergency operating sequence.

These tests comply with GDC 37.

Response

HCGS Draft Technical Specification 3/4.5.1 requires flow tests in accordance with Specification 4.0.5 and provides minimum flow rates.

The Technical Specification also nequires that system functional tests be performed once every 18 months.

These are consistent with the Standard Technical Specifications.

L l

l l

l M P85 90/07 2-mw

SER Technical Specification Issue No. 20 (SER Section 6.3.4.2)

ECCS subsystem operating sequence The NRC staff will require the applicant to test the ECCS subsystems (except for the ADS) every 92 days, in accordance with the Standard Technical Specifications (NUREG-0123), to show that specified flow rates are attained.

Also, the NRC staff will require that a test, in accordance with the Standard Technical Specifications, be performed every 18 months in which all subsystems are actuated through the emergency operating sequence.

These tests comply with GDC 37.

Response

The functional tests required in HCGS Draft Technical Specification 3/4.5.1 will demonstrate the proper actuation of the systems.

This is consistent with the Standard Technical Specifications.

M P85 90/07 3-mw

SER Technical Specification Issue No. 22 (SER Section 7.2.2.3)

Testability of plant protection system at power The staff will verify that the Technical Specifications for Hope Creek include appropriate surveillance requirements to require periodic (online) demonstration of the operability of the RPS and ESF instrument channels logic and actuation devices.

Response

HCGS Draft Technical Specification 3/4.3.1, Reactor Protection System Instrumentation, provides surveillance requirements for the RPS, and Technical Specification 3/4.3.3, ECCS Actuation Instrumentation, provides surveillance requirements for the ESF instrument channels and actuation devices.

These Technical Specifications are consistent with the Standard Technical Specifications.

l l

l l

M P85 90/07 4-mw

s.

u ')

SER Technical Specification Issue No. 24 (SER Section 7.2.2.9)

Reactor mode switch The staff will verify that the Technical Specificat ions include appropriate functional tests for the IRM and APRM channels for the purposes of ensuring that the reliability.

of the reactor mode switch is maintained..

s

Response

HCGS Draft Technical Specification Table 4.3.1.1-1, items 1 and 2 provide the appropriate functional tests for the IRM and APRM channels which ensures the reliability of the reac-tor mode switch.

DJD:cag M P85 96/06

?

SER Technical Specification Issue No. 28 (SER Section 7.6.2.3)

APRM electrical protection assemblies On the basis of its conformance to-the aforementioned criteria, the staff concludes that the conceptual design of the proposed modifications to the APRM system power supply configuration is acceptable contingent on implementation of acceptable surveillance, maintenance, and testing procedures that will be in conformance with the reactor protection system Technical Specifications.

Therefore, the staff considers this concern resolved.

The applicant is required to implement, by means of a Tech-nical Specification, surveillance, maintenance, and testing procedures for the Class lE EPA solid-state protective devices located in the APRM power source configuration.

~

These procedures should be similar to those provided for the EPA solid-state protective devices located between the RPS M/G sets and the RPS distribution panels.

Response

HCGS Draf t Technical Specification Section 3/4.8.4.7, Power Range Neutron Monitoring System Electrical Power Monitoring, has been developed to provide the above requirements for APRM electrical protection assemblies.

M P85 90/07 5-mw i

i

~

' !! i

..3 D85 M! PAN 4f Alf07taal MedlTehts SYSTDI ALitTt! CAL POWR Muttegrag

~L 9aewhen mener~,ng t.fstem (aJMs)

'=

'3.8.42 elastris power aanftering channels for eash faservios per-s range, N S pow r s e ly shall to OptaABLE.

6 At all times.

O y ra eNMS Wth one,NM.Selastris seaftering shonnel for an inservice yo.asv-a.

rants fasperehle, restore the i gemer monittri shenne to status withia 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> er g,q:3s assesi p ev. van a NMS power sappi r

NMS

.N M-- circ'8M'.

Wth both,[NMs h.

estric esattering.shannels for en faservice po*887 ren a.

pouer i

rele, restore at least one electris peuer itering channel to status within se ajautes or6deemergi e 3

one assestated pe aec range NMS power supply -Qaedse circui+.

r-yy re a NA4S 4.8.4 7 The above specifiedj electric annitertag channels shall to determined OptRABLE:

a.

At least once per 6 months by performance of a OWsEL FISCTIONAL TEST, and b.

At least esce per 18 aanths by demonstrating the OptRASILITY ef ever voltage under voltage, and under-protective instrumentatIen by povforesace of a OWeEL SRATION taaluding staulated asteestis actestion of the protective relays tripping logic and evtput sirsuit treakers and verifying the fellesing setpoints.

1..ever-voltage 1 132 VA80his 4 h 132. VMV (60s & )

6'

)

2.

Ih8er-voltags 1 Iof Vht, *(Bos A.

'), lotVE* Uhis 3.

under-frequency 1 57 H z - 0 + 1 '7.

3 3

  • $wal sdpoints fo be codemacd b hel) Medstuenterfbr, y

i t

fle M CA 85 k.

l s/4 e 31 AN.T i

t I

i A

u1

- - - - - ~ ~ ~

SER Technical Specification Issue No. 29 (SER Section 7.6.2.2)

Nonsafety - related equipment operability The applicant stated that the assumptions of performance of the nonsafety-related equipment listed in Table 7.1 are based on extensive failure-rate data for other equipment with similar design and quality requirements.

In addition, the Hope Creek Technical Specifications will include appropriate provisions regarding availability, setpoints, and surveillance testing that are presecribed by the NRC's Standard Technical Specifications for all of these systems / components except the recirculation runback feature.

The staff will verify that the Technical Specifications include limiting conditions for operation and surveillance requirements for the nonsafety-related systems / components (except for the recirculation runback feature) discussed in this section of the SER.

Response

The HCGS Draft Technical Specification Sections identified below provide the required limiting conditions for operation and surveillance requirements for the nonsaf ety-related equipment listed in SER Table 7.1.

HCGS Draft Technical Nonsafety-Related Equipment Specification Section (1)

Vessel level 8 turbine trip 3/4.3.9 Feedwater/

Main Turbine Trip Systems (2)

Vessel level 8 feedwater 3/4.3.9 Feedwater/

trip instrument channel Main Turbine Trip Systems (3)

Turbine bypass system 3/4.7.10 Main Turbine Bypass System, and Table 3.3.1-1, Note J (4)

Rod sequence control system 3.1.4.2 Rod Sequence Control System M P85 90/07 6-mw

SER Technical Specification Issue No. 29 (SER Section 7.6.2.2)

Nonsafety - related equipment operability (Continued)

HCGS Draft Technical Nonsafety-Related Equipment Specification-Section (5)

Rod block monitor 3/4.3.6 Control Rod Block Instrumenta-tion, and 3.1.4.3 Rod i

Block Monitor Channels (6)

Instrumentation, control, 3/4.4.2 Safety Relief electrical, and mechanical Valves, and 4.0.5 equipment associated with the relief function of the

. safety / relief valves l

I l

f I

l L

i i

l l:

l-I i

f M P85.90/07 7-mw l

l J

,-m x,,,

,r

..,....,,,,e._,.

,m.,

.r,-.,~,

SER Technical Specification Issue No. 33 (SER~Section 8.3.3.3.5)

Testing of breaker time-overcurrent trip characteristics Periodic testing of'the breaker's time-overcurrent trip characteristics will be included in the plaat Technical Specifications.

. Response HCGS Draft Technical Specification Sections 3/4.8.4.5 and 3/4.8.4.6, Class lE Isolation Breaker Overcurrent Protective Devices, have been developed to provide the above testing requirements.

i h P85 90/07 8-mw

~

v C LAn iE.150LATao,4 5AEMER

^^ ~ W OVERCURRENT PROTECTIVE CtVICES

'h_7-TAL; ? R i a***"

LinluMS-CW WITION FOR OPERATION 3.8.4MA11 C'~~ ~- ~ ~~ ~^"C-2 ---%a'45 5errt:r overturrefit protective 6

~

shall be OPERA 8LE.

gg

, devices shoun in Tale 3.8.4 APPLICA81t!TY: OPERATIONAL ITIONS 1, 2 and 3.

g;pp.(q, tog gad) 5 g

I TJ !!:

,---^ ' -- G?rr'p E

im With one er eere of the "~ *~

overeveren_tprotectivedevicesshowninTaele3.8.stg}1 inoperable, declare r a.

inoperele andjppy..;

. w. i IS8168'sh e r-the affecteef at or aff

uses, 1.

or '.0 :- 4.

Y ci it reake ze

  • ?. 4.

J ci t(s)

' tr ing socia ci it'bre c(

/)

wi n 72 asrs v ify t i tb dar be i

[reqf+reseve the inoperable circuit brea i

at est e

e7 480 It reui br==

roe service ; O--S n =; ;c::':-} within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and verify Fa the inoperable breaker (s) to be (cad ;# at Isant oece per 7 days

-'d thereafter.

ftY fy n

The previsions of Specification 3.0.4 are not applicable to evercurrent Mt x : -m

":"-r = -'

r b.

devices in "" " ;r

.M' - sesmu' --(olt ctrcuits which have the inoperable circuit

, _;' - ' r "

c-- - =--.

breaker O ;-':I nth SURVEILLwt ddLIfbT5 t'ach ef the_ pass, it. isetr+ ten bec4sws-.:. :=&~ _- ::-- overturrent

.--_2_,.

I shall be demonstrated CPERA8LE:

^^

4.8.4 protect we devices shown in Table 3.8.4 At least once per 18 aanthe:

6

( " ", ;-' j ggy a.

circui b rs l

sodt 1

tingbas[s,at1ast of sy verifyi was are PIRAS by set

ing, a re the ircui breaka

.; : - :... O and pe orei :

a)

A SRATION f the socia pre ive

lays, b) la i system for 1 test ich i ludes feuta

~

tc tion a the stas and verifyi tha each I

re and ociated ircui breake and ove u

t rol ci its fun tion as designet.

c) e each c rcuit bei sker found i reble ring se unctions ts, an additi anal repiesenta ve s le o

^^ ' : : _ ;' :M the cir mait tre ikers o the i ra le ftypeshe aise be functierally tes tad unt 1 na a re f4 Ivres are f er all ci rcuit br eakers < f that h ive bee n i

yi lytesy p -

m Here sneat 3/4 SM Rw.+

"S m 7 ;

u f

.=

t

10JAN313 tucmCALf0WN SYSTRE

( delg +"e ek t5

/nd m.kn %

l gtiyee n.ihi (Cutinued) j

}

ty selecting and functionally testing a repre b

l 4

Circuit heesters selected for functional testing shall to selected en a rotating haste. Testing of these circuit tre g

l sha11 consist of injecting a current with a value equal te.;. _Z wat af

4. 6 '-:, C

.71,,;f ;.:

L{1es delay e :,; i_ C.*ans omfying cired4 brte]rers l

the pickup of the shortthat the circuit breaker operates within f

for width for that current specified by the manufacturer. The

,i g M e / g ; 6 s,og d, 5tdf *.' P g,, g,, % >

instantansees element shall to tasted by injecting a current he fync4?taal +tsiia% equal ta attn of the pickup walue of the elem M p3 1AO% EIaA80ESty d %A no inteA" M IAS SI M %tional ties delay.. Molded case aircuit breater tes beperdersMk aise follow this precedure encept that generally no aere than I

Med 7 y.R use,4 f,,gy,,sofruatafs 4/Mjdt/

tuo trip elements, time delay and instantaneese, will to i

4hc +ime-involved.4 Cirevit breakers found inopers

.g., ge rif3 tasti For each circuit breater found inspetable ering

' " ' d e g,. d ris 9 sopere on.

l f

dad pickur 4UkMlen these functimal tests, a additioner representative s k

f the insperette type c

of 4ke 4rlf 8ftaf"t!*f at least 115 of all the circuit brea ert ot d until ll t

. # - shall aise to functiona y as efound er all circuit treakers of functionally testad.

T sei ng and fenelly testing a resenta ve saeple f each of en a time basi. Each resentati 11 inal at feast of all of type. The ensi test 11 cens ef a destrutti saeple tas unich strates t the fue its

's sign crita 14. Fuses found i rette resis he reples with Li I

duri these fonal sting shal'Per each fupe found i ette retien.

fus prior 14 resuming itional foresentati e saapie l

ng these' w iens, ts, an

- of t least its of all es of type shal' to funct 11y er all fuses of t

tad until 'ne more f lures are have nehn functi 11y tasted J-At least enes per og senths by subjecting each circuit trea inspection and preventive maintanense in asserdance w D.

prepared in conjuncties with its annufacturer's recomme e

M e

8 e

ed i

I G

6use m e.xs -

t.4 x... a.,

I

~

TA B1.E s. S.4,s - (

p,g47 c1An IE. tsoi.4Tierd adsaxex, g

PAoTecTwc envics.s

}cvsrcuxAsalT SY 4 Loc 4 saggg)

(54a4xa4 TAtrPEb 4so vs. eews4 cacotT susse_s l, " TYPE. A AR,- 54-30 Class 13 Class 18 R

"1'-- 1E M Descristian Circuit A

Ereaker Ee.

Reactor Aus111 aries Cooling l

105410 52-41011 System Pump 1AP209 Radoeste and Service Area 108410 52-41014 NCC 108312 108410 Reactor Buildi ly Air 52-41024 Bandling Unit 1 Reacter Aus111eries Costing 105420 52-42011 System Pump 18F209 i, Rodneste and service Ares 103420 52-42014

' NCC 103322 Reactor Building Eshaust Fan 105420 52-42014 ISV301 109430 Reactor Buildi ly Air 52-43024 Bandling Unit 1 Centrol Red Drive Pump 1AP207 108430 52-43014 Centeel Red Drive Pump 10F207 108440 52-44014 Reactor Building Supply Air 108440 52-44024 Sandling Unit 1AVB200 i

Radwaste Area Supply Fan OSV316 l

108440 52-44034 Reactor Area NCC 108252 108450 52-45011 Radweste Area Eshaust Fan 193450 52-45014 OhW305 Emergency. Instrument Air 198450 52-45034 Ceepressor 10E100 Reactor Building Eshaust Fan 108450 53-45024 ICV 301 Reacter Area NCC 108262 198460 52-46011 s

5 R,ev. Y 3l+ $ - A lo t

f i

-tww-w

--v-

--w=r

e. w e sr,=--,-,.---em-,- - - - -. -

--*wh-e

-imr w.er,-e-

--c-v----

--w-,-

---'------w

ew=

= + --

TABLE 3. C.4. E - (

~

c. LAM IE. ISoLATscel ME4kgA, ovsruaAEAIT PAoTecTave. Devica.s P43e 2. of 2.

i L. Ce*4iaded g-Class 15 Class 15 Circuit A

r. al--- It w nameristian Breaker So.

53-44014 105460 Radweste Area Eshaust Fan OBF20S 52-47011 108470 teacter Area ICC I M172 53-47014 105470 Radueste Area Eshaust Fan OCV305 8

108470 Radueste Area Su0 ply Fan 0&V316 52-47024 105470 Technice! Support Center 51-47021 IEC 003474 10e480 Reacter Area arc 10sas2 53-4s0)1

~

52-48024 10ses0 asector mettetet Esteest Fan 1&V301 i

480 V4C. McLbED CASE. C.tn cutt Sna. Age.x,s l T YPe. HF&t5 0 l

Class IE.

Chas f.

h. Class lE Leal. Descr41h.81 a

g;g;+

g-no.

areasser public Addrese Systen Inverter 10e451 190496 53-451023 Secerity System Inverter 0AD499 108471 1

M555 Caaiphe laViN tog 44g St.,44 tc45 lod 445 O

E l

3/4 g-m Rev. 4

e 4* LASS IE. IsoLATtorJ 84 sage 4-ELECTRICAL POWER SYSTEMS [

f r- _ _ __. _.. -........

...=.

i 0VERCURRENT PROTECTIVE Otv! cts LIMITING enunITION FOR OPERATION ( conTwufb) 3,3,4gAtt "" ^-L -- i s;haTF W~0PtRAstt.C= E0ation-conduc overturrent protective G-devices shownl Y Ia9n M.4 4,ga#7,,pfg OPERATI ITIONS 1, 2 and 3.

priury Aad. tmur j y APPLICA8TLITY:

b

~

ACTION:

--? M With one or mere of the ?-'= / - "JU-;3;-
"***'^I~fn_operaale, declare l

a.

overcurrent protective devices shown in Tante 3..

l the affected system or component inoperable and app the appropriate (e

ACTION statement for the affected systes, and

[ circu t(s) byFor $ 0 - 4.

U kV ci itbreayrs,e.;?nergi the j' " 9 4.1 kVl poing assoc sted nt ircuit aker(s i

with n 72 hou and we ify the undan circu breake be i

at east one per 7 s there ter,

_440_v9 itcui breake

' remove the inocerable circuit breaker (s) 2.

Froe service y ' ::- :n 2: ;. ::' :-} within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and verify

'at least once per 7 days theinocerablebreaker(s)tobe'c;;_.;;.:A dhA*

thereafter.

Otherwise, be in at least HOT 5 HUT 00kN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The provisions of Specification 3.0.4 tra_nat_ applicable to overcu..,._, WJL e

D.

" ';;;f --g" 19 -- M. ; = wwumu.,@ rM1t circuita whic 99.

devices i bysaiier ' ;:M:I ; ^-

SURVEILLANCE dtIN$O cl*Ds ta. isol4fism braker tratian3ambstyP overturrent 4.8.4.

ach of the 8 ^3' IshallbedemonstratedOPERAs%

protective devices shown in Table 3.4.

a.

least a per 8 months tage '"p;" ;-'; ircuit_

g rs that the un v By ri breakers,_' : :7..;M_,_h basi by sel ng, on rotas at le t of a

Pt

...,0 ne perf ruing:

circui A

L CALI RATION o<

the as 1sted rotect e relays and !

i e Surved.act

)

X'n ated system f m:tional test ch inct s sinut tad j

AeIuirerients. 4.S.4,5.,

tc tion of the sy and trifyi that sa re ay and as ociated ircuit akers d over urrent t

c rol ci its f ion as sfgned.

)

r each c rcuit b her feu inoper le dur ng thes l

unctional tests, additi

1. rep entati sample of the ci uit brea ers of inos anle

.-' ' -'^

/typeshal aise be functio 11y tes ur.til ne more failu s are found or all reuit breakers et that t a have een functiom 11y tes

[

/

s Noot e,eead

/

CE-!'! '-_:- 'S 3/4ap28 stev. 4-t l

TABLE. 3. U.4. la - (

r 8 44 IE. IS6LATas4 5454ssA fye l of L ovsAuAA&#r enomveva. Osveces jpgtH4M mod S4ckuP clicutT SAs4xsts) l i

430 VAC. Moldel Case Cireuif Ermaars

'^

Tye HP isi ~ '

Class II.

l***+IM Trly T.,4 SYsvaM scrotrans47 Po48s4sb c.',cui+ tratorer Wo.-

a t-t a sc45 lbStit

  • r D4 tog /ste vac. Dis +ribofien TM P4nel 10Ytot l

s t-sit.e45 Ies1LL

!"M tet/tts V4c Disfelbu4/e n TM thge( f oY tet J

5'L-131e43 Ioet%L TM 1ss'/sto VAc f)s'sfd6u+/est M

lbiel 88Y to3 st. t4 t#43 os 242.

"T H ut/ iso VAc. bisfr-bfI..,

'M

!?sneI toYno4 st-tsto z.i t e s 2.s t.

IM 54adat Hasder Dowaviewn Drain g2-sszaot i ea a.s t_

-rM 2se(44! n v4lv e As-H V-F01 (

5 t-t%LIS:

l os t%1.

IM M szy co+6m e/. s,41 443 Supply s s - tssi o t.

losast T84 Valve l kP-NY-s avt a f L-1%L 1%L i e Sts t ZM M aim $+84at II'ts. A MSIV Dufhaerd Valve IKP-HV-51s46 51 - L318 4 i e o a LS L TM Seal das Supply 51 L %Ll1 %

( 0 & tS t, gg Main Sim.g Line. & M31V OMM j

5L - 1%L I4L to&Abt "TM S ul des Saff y VdIWf ( MP.W V-5155 6 l

l 51-z%Ll4L t o S LS E LM Mas'n Sfes-s Mae C MSIV Oofbee rd st - 1st 14 4 se s ss t-Te4 Sul das Supply V4tvc IMP-ofv 88M4 l

st-tst:43 sostgt z.g g,;= S4 sam Lt.ie b Msrv oufkaard 52-1%'895

( 8 "

  • 3 *-

'T'4 Ss41 44, sopfsy velve iKr. gV. rsus 81-14Ltt t t 06L4L 1 84 MS2v zabard, sat ses supply 51-14t ets s os t4L TM V4tw e. tEP - et v-ss t44 5 1. - 1 4 L t% L to & t4t ze4 g41. 54,4.% Line 4 Mss.V 2nbedr/

st-142.024 to re14L

-TM s=( das Sorr y valve (KP-Hv. sss44 t

Maia Siam Liae 4 MSIV lakaard i

s - a.4L LM tes t< t.

zg st-t4tc64 te6:41.

-rM Se4t 44s Sorriy Vd i' < (KP. g v-ssssa i

l s.t s+m, u,, c. a5xv 2 6 4 4 si.

u t 4i

... z4 t 2,4 KL g,4L a t3

(# S t41.

T *4 5#dl 44s Supply V4fvt I KP-84V-8838'4 3/4 8- *?

Aev. Y

TABLE 3. D.4

(, - t C' 44 IE. ISOLATasM M64ergA

l P e t * + t-9 l

ousauaAsart PneTecTave cavacas CONTINUE.b st-14L(45 t OSE4 L XM M aia SteA M b[4( D MSIY 3ebder=d, 5t-Lil4 188t4 L TM Seal 44s ker y Valve. (KP-WW-sT314 t

ltWcu bise.8uge To Firadw4er-51 2.4t :5f 1 c82.41 JM s t-14 L tt4-somz4L iM valve i AE - HV - Pong Fed.nfer U=e cross Tie Isel44/as st-tsteM 888tSt.

Iai toez)L T,4 velve g4g,.g v-4t44 5t-tSt t s t 1

4 e

i

+ker l **$a*+"-

i m /u,+,5 e

G 4

Y t

  • e

-e-.

,---,m-,-,,,,,.,m,--.,.,,,

.,n,.,.,-

z SER Technical Specification Issue No. 42 (SER Section 9.3.1, 9.3.6)

Air quality testing The service and instrument air systems will initially meet the requirements of American National Standards Institute (ANSI) Std. MCll.1-1976, using non-oil-lubricated air compressors.

The applicant has committed to perform periodic air quality testing of the air systems to ensure compliance with the requirements of ANSI Std. MCll.1-1976.

This should be incorporated into the plant Technical Specifications.

The applicant has committed to have the PCIG and instrument air systems meet the requirements of ANSI Std. MCll.1-1976, using non-oil-lubricated air compressors as part of the preoperational startup tests.

The applicant has committed to perform air quality testing in accordance with ANSI Std.

MCll.1-1976.

The applicant stated that the maximum particle size after the filter will be 3.0 microns.

The filters will be inspected quarterly with the system testing to ANSI Std.

MCll.1-19 76 every ref ueling.

On failure to meet acceptable air quality, branch lines are to be tested to determine the extent of problems and corrective action needed.

This should be incorporated into the plant Technical Specifications.

Response

The instrument air system is not included in the Standard Technical Specifications nor is it included in the Technical Specifications for other BWR plants (e.g.,

Limerick, Susquehanna).

The requirement for testing the air quality has no limiting condition for operation of the plant.

The periodic testing of the air quality is included in the plant operating procedures.

M P85 90/07 9-mw

SER Technical Specification Issue No. 47 (SER Section 15.2)

Turbine bypass system and level 8 high-water trip performance In analyzing anticipated operational transients, the applicant has taken credit for plant operating equipment that is not normally reviewed by the staff because it is not considered essential for safety.

The staff has discussed the application of this equipment generically with General Electric.

On the basis of these discussions, it is the staff's understanding that the most limiting transient that takes credit for this equipment is the excess feedwater event.

Further, it is the staff's understanding that the only plant operating equipment that plays a significant role in mitigating this event (excess feedwater) is the turbine bypass system and the level 8 high water level trip (close turbine stop valves).

To ensure an acceptable level of performance for Hope Creek, the Staff's position is that this equipment be identified in the plant Technical Specifications with regard to availability, setpoints, and surveillance testing.

Response

HCGS Draft Technical Specification Sections 3/4.7.10 Main Turbine Bypass System and 3/4.3.9 Feedwater/ Main Turbine Trip Systems provide the required availability, setpoints, and surveillance requirements for the turbine bypass system and the level 8 high water level trip.

M P85 90/07 10-mw

I SER Technical Specification Issue No. 48 (SER Section 15.4.9)

Scram speed The analysis of the rod drop accident has been performed on a generic basis by the General Electric Company and is reported in NEDO-10527, " Rod Drop Accident Analysis for Large Boiling Water Reactors," and Supplements 1 & 2 to that report.

The calculation is performed under the following conservative assumptions:

(1 )

No thermal-hydraulic feedback is assumed.

(2)

The least negative Doppler coefficient anticipated is used.

(3)

The rod drop speed is assumed to be that measured for the rod design plus three standard deviations.

(4)

The scram speed is the Technical Specification value.

Response

HCGS Draft Technical Specification Section 3/4.1.3.3 requires an average scram insertion time of 3.49 seconds.

The rod drop accident analysis referenced above used a value of 5.00 seconds.

Therefore the Technical Specification requirement of 3.49 seconds is conservative based on the rod drop accident analysis.

M P85 90/07 11-mw l

w

p.

SER Technical Specificat' ion Issue No. 49 (SER Section 15.6.4)

Primary Coolant Activity A guillotine break of one of the four main steamlines is postulated to occur outside the primary containment, downstream of the outermost isolation valve, resulting in mass loss from both ends of the break.

The primary coolant loss is assumed to be limited by steamline flow limiters to a maximum release rate of 200% of rated steam flow, and by Technical Specifications which ensure the maximum closure time of the main steam isolation valves (MSIVs) is 5.5 sec.

Mass loss from the broken steamline terminates when the MSIVs are fully closed.

The applicant has calculated that 99,400 lb. of water and steam would be released to the atmosphere before the MSIVs would close following such an accident.

The staff followed the recommendation of SRP Section 15.6.4 (NUREG-0800) and conservatively assumed 140,000 lbs. of coolant would be released.

As specified in SRP Section 15.6.4, doses were calculated for a long-term (Case I) and short-term (Case II) primary coolant Technical Specification limits on iodine activity as given NUREG-0123, " Standard Technical Specifications for General Electric Boiling Water Reactors."

The staff's calculated doses are listed in Table 15.1.

The atmospheric dispersion values (x/0) used in accident evaluations are in Table 15.3.

The assumptions used in the staff analysis are listed in Table 15.4.

The resultant doses for the short-term limits are within the guideline values of 10 CFR 100, and for the long-term limit are less than a small fraction of the guideline values of 10 CFR 100.

These results meet the acceptance criteria of SRP Section 15.6.4.

To provide suitable limitations on the offsite radiological consequences of this accident, the staff will require that the BWR Standard Technical Specifications on primary coolant activity be incorporated into the Hope Creek Technical Specifications.

Response

The primary coolant activity limits are given in HCGS Draft Technical Specification Section 3/4.4.5, Specific Activity.

The limits are consistent with the limits in the Standard Technical Specifications.

l l

MP 85 96/02 1-mr l

l

t l

SER Technical Specification Issue No. 52 (SER Section 15.9.3)

Automatic depressurization system logic i

i By FSAR Amendment 5, the applicant adopted the results of the BWROG report ("NUREG-0737, Item II.K.3.18 - Modification of Automatic Depressurization Systems (ADS) Logic--Feasi-bility for Increased Diversity for Some Events" dated October 28, 1982) on TMI Action Plan Item II.K.3.18.

The applicant has committed to modify the ADS logic to bypass the high drywell pressure trip after a sustained lower water level signal and to add a manual switch that may be used to inhibit ADS actuation if necessary.

This is consistent with Option 4 of the BWROG study and is acceptable to the staff with the following conditions:

Technical Specifications must be provided for the bypass timer and manual inhibit switch.

Response

HCGS Draft Technical Specification Section 3/4.3.3 ECCS Actuation Instrumentation, Tables 3.3.3-1, 3.3.3-2, and 4.3.3.1-1 have been revised to provide the required tech-nical specifications for the bypass timer and manual inhibit switch.

i l

I I

i l

M P85 90/07 12-mw l

t I

l

4 0

s'l RR*: 22X M h

E

  • 8. 11

.e 5

E i

f 7.

E

i T

8.

il

,s; 1,

i

-Es g.

c

--- % 5

=-}

3 = ;-

aaaa aaa '3_l.

s aa i

v lEg y

c g=l g;

y bs E.

aaaa aaa IE

%j ]l$.

aa I

l t

i.

s

[i yl

$n T

E l

?-

I NE T I1 is3 n.

3,

~

g E.

mj 1:

m

ja I g.

s_

s.;.3;'4$n e

3,E.*!.qs 3

y-

m g

g

=g 45 8

L.

.A ~:

}M8l ws,e n

E

~

g g

m e

a a

3! j. fs.. p~

i i

e e

e 4

I a s-

.s:-

g ev 6-min g

g=

4

' I -li-l g!"AII =1 g

k. ',

4 3

E[' i g

s s

< )a 1 3 m eL u3--s i

4 g

i....ea

.3-a sg 6.

s c

a a

jligstsif ai r

)1 F i

i m

c g

in J.4 5

s.!

b.

1 h

.=

iI }

si it 2 t

t 1-g1yIs s

2 E 3.

1 m

t g

si e+

igla 11l l '[g[n* I

  1. r 1 - I b., b

..rse..

al I s u I

3! g*:I8 82 2~:

I 4

8 i

E

_ i_ H_."

aa 3-r.,3. s g

3al 23

! jai H.

3 3: :

,g---

,13] 5 3

1 I

vI;f 5E lle:

I :13 5t s]

er a

af I2lm) 1 3

-.. u lil i.;

3[]j 4;a44.: a a m 31;i r5viH o

1 g

Mi

\\

l E

E EEEli aa b

b b be anI b h 4

nd i

37 woes entse 3/4 3-99" R*V. 4 3,

i

""-07: 00' )

I l

i i

,i TABLE 3.3. -2 (Continued)

EERGENCY CORE C0OLING SYSTEM ACTUATION INSTMBENTATION SE ALLOWABLE l

3T i

T TRIP SETPOINT VALUE _

j 7)

TRIP FUNCTION AUTOMATIC DEPRESSURIZATION SYSTEM

> -1363 inches l

)

{

4.

>-129) inches

  • 5{41.881psig Reactor Water Level - Lou Lou Lau, Level 1 3 1.68) psig O

a.

< 105't. seconds

< 1117 seconds l

b.

Drywell Pressure - Nigh IE1451 psig,(increasing) I psig,(increasing),

ADS Timer

??:y"- a ~ns Core Spray Puey Bischarge Pressure - High 3 (155) p ig, (!- r -5 ;). l i

c.

d.

l i

Yf:p'- 5 i2 s' 51153 psig (increasing) l

(

  • W R LPCI Mode Pump Discharge Pressure-High

> (440 psig, increasing >YT.,;'

(l?5) ?. (!~~%L \\

e.

?

? :y: - 5

> 433) laches

> (11.5) inches l

n.s i

Reacter Vessel Water Level-Lou, Level 3 11 4 l

llA "

  • f.

j Manual Initiaties g gs,;,3,w, g

ell Pressure, n T re e r-g g,,,g pg -

h.

4 DS Dry t uwt-s~ A

~ pg.

e.

Aus r%s T

5.

LOSS OF POE R 297r 63 4.16kwBasigelts (t940)+(999) volts a.

4.16 kw Emergency (tus Underveltagey/75 g-,:; Basis -

q;;;) w a.

(Less of Voltage engg.

b.

120 v ps-ja

(+:erve'TEs,,g teetten welts a

Q

  1. r
c. <(

sec. time

< k,7sec. time delay y

delay 0.07 I

a.

4.16 kv ta Asiny ap/r

/va o

i 3r/r t97 volts G;Ji3S) welts 4.16kwEmergency)BusUnderveltage c.,

l b.

3-(Segraded Voltage (**))

b.

120 y sis -

Welts

) welts

[

l M ( M,1j#rES)3"3 yf dela;y...,,..W, sec. time s..,,.., sec. time

<as 4Y c.

delay. >/#.y i

" See Bases Figure B 3/4 3-1.

The vel s shoun are the maximum that will not

(** This is an inverse time delay voltage relay.

j Same weltage conditions will result a decreased trip times.)

(f X is value that ensures adequate NPSN and precludes air ent,ry due te vertexing.)

result in a trip.

t j

{## Y is (5) t ? :. A.; z r ! a i r L ;?.I l

.s.pr eets.

r / 4:34

,,.aer /

/

i

1 c

TABLE 4.3.3.1-1 (Continued) y T,

EERGENCY CORE COOLING SYSTEM ACTUATICII IN5im3IENTATION SURVEILLANCE REQUIREMENTS r

Q CMAISIEL OPERATIONAL e,

4 f

j CHAfGIEL FUIICTIONAL CHA18 DEL ColelTIONS FOR lAllCH l
j, CHECK _

TEST CALIBRATICII SINtVEILLA10CE REQUIRED l

4 TRIP FWICTICII 1

4$

AlficMATIC DEPRES$URIZATION SYSTEM 4.

4 Reacter Wessel ideter Level -

1 a.

Law Lew Low, Level 1 5

M R

q 1, 2, 3

M

{

1 1, 2, 3 b.

Dryuell Pressure - Nigh 151 1, 2, 3 1

1 c.

ADS Tleer IIA M

, i,i,

Q g

d.

Core Sprey Pump Discharge Pressure - MlWi (SF M

(R1 1, 2, 3 e.

MIR LPCI Itede Pump Discharge J

Pressure - High

$5[

M JKJ 1, 2, 3 4

1 f.

Reacter Wessel teater Level - Law, f

Level 3 5

M RO 1, 2, 3 l

/M4At IIA 1, 2, 3 Manuel Initiatten IIA l

hf.5.yLd55 d 5 [50hk N-N.

da hff[

e a.

4.16 kw Emergency Bus Under-l

.p voltage (Less of Voltage)

M4 IIA R

1, 2, 3, 4**, 5**

I s

M b.

4.16 kw Emergency Bus under-voltage (segraded Veitage) 5 M

R 1, 2, 3, 4**, 5**

e f

All other l

$(f) Manuel Initiation switches sha11 he tested at least ence per le senths during shutd ma ---t af circuitry reentred La he tested for automatic system actuallan.2 l

ame 11 tihen the ' system is required to be OPERABLE per Specification 3.5~2.

Required SPERABLE uhen E5F equipment is required to be OPERABLE.Ilot regoired to l

I-e I

l g Ulh C.Wde. %sp 6\\. A \\ead ome e m 4.js.

I f

l

ATTACHMENT 4 Revision 4 HCGS Draft Technical Specification Pages L

= ~. -

HOPE CREEK GENERATING STATION DRAFT TECHNICAL SPECIFICATIONS l

LIST OF EFFECTIVE PAGES i

Revision Pages Numbers Index 0

1 2

11 2'

111 0

iv 0

v 0

vi 0

vii 0

viii 0

ix 4

l x

0 xi 2

xii 0

xiii 0

xiv 0

xv 0

xvi 0

xvii 0

l xviii 0

l xix 0

xx 0

xxi 0

Section 1.0 0

l 1-1 0

l l-2 0

l l-3 2

l Insert A to pg. 1-3 2

1-4 2

Insert A to pg. 1-4 2

Insert B to pg. 1-4 2

L Insert C to pg. 1-4 2

l-5 2

Insert A to pg. 1-5 2

1-6 2

l Insert A to pg. 1-6 2

Insert B to pg. 1-6 2

l.

1-7 2

Insert A to pg. 1-7 2

1-8 2

1-9 0

Section 2.0 0

2-1 0

2-2 0

2-3 0

2-4 0

i Bases for Section 2.0 0

Note 0

MP85 20/09 1-db Rev. 4

__.. -. - - _ - __ _ _ _. _. _,~._,..,. _. _ _.. _ _ __ _ _ _ _ _ ____ _ _,.._ ____ _. _, _._ _ _ _,.,,. __ _

C 5/85 HOPE CREEK GENERATING STATION DRAFT TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES Revision Pages Numbers B2-1 0

B2-2 0

B2-3 0

B2-4 0

B2-5 0

B2-6 0

B2-7 0

B2-8 0

B2-9 0

Section 3.0 & 4.0 0

3/4 0-1 0

Insert A to pg. 3/4 0-1 0

3/4 0-2 0

3/4 0-3 0

3/4 1-1 0

3/4 1-2 0

3/4 1-3 0

3/4 1-4 0

3/4 1-5 0

3/4 1-6 0

3/4 1-7 0

3/4 1-8 0

3/4 1-9 0

Insert to pg. 3/4 1-9 0

3/4 1-10 0

3/4 1-11 0

3/4 1-12 0

3/4 1-13 0

3/4 1-14 0

3/4 1-15 0

3/4 1-16 0

3/4 1-17 0

3/4 1-18 0

3/4 1-19 0

3/4 1-20 0

3/4 1-21 0

3/4 2-1 0

3/4 2-2 0

3/4 2-3 0

3/4 2-4 0

3/4 2-5 0

MP85 20/09 2-db Rev. 4

i l

l 5/85 HOPE CREEK GENERATING STATION DRAFT TECHNICAL SPECIFICATIONS l

LIST OF EFFECTIVE PAGES Revision j

Pages Numbers 3/4 2-6 0

l 3/4 3-1 0

l 3/4 3-2 0

l 3/4 3-3 0

l 3/4 3-4 0

l 3/4 3-5 0

l l

3/4 3-7 0

3/4 3-8 0

3/4 3-9 0

l 3/4 3-10 0

l 3/4 3-11 0

l 3/4 3-12 0

l 3/4 3-13 0

3/4 3-14 0

3/4 3-15 0

3/4 3-16 0

3/4 3-17 0

3/4 3-18 0

L 3/4 3-19 0

3/4 3-20 0

3/4 3-21 0

l 3/4 3-22 0

l 3/4 3-23 0

t 3/4 3-24 0

3/4 3-25 0

3/4 3-26 0

i 3/4 3-27 0

l 3/4 3-28 0

l 3/4 3-29 0

3/4 3-30 0

3/4 3-31 0

3/4 3-32 0

l 3/4 3-33 0

3/4 3-34 0

3/4 3-35 0

3/4 3-36 0

l 3/4 3-37 4

Insert A to 0

I page 3/4 3-37 l

3/4 3-38 0

i 3/4 3-39 0

MP85 20/09 3-db Rev. 4 I

i 5/85 HOPE CREEK GENERATING STATION DRAFT TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES Revision Pages Numbers 3/4 3-40 4

3/4 3-41 0

3/4 3-42 0

3/4 3-43 4

3/4 3-44 0

3/4 3-45 0

3/4 3-46 0

3/4 3-47 0

3/4 3-48 0

3/4 3-49 0

3/4 3-50 0

3/4 3-51 0

3/4 3-52 0

3/4 3-53 0

3/4 3-54 0

3/4 3-55 0

3/4 3-56 0

3/4 3-57 0

3/4 3-50 0

3/4 3-59 0

3/4 3-60 0

3/4 3-61 0

3/4 3-62 0

3/4 3-63 0

3/4 3-64 0

3/4 3-65 0

3/4 3-66 0

3/4 3-67 0

3/4 3-60 0

3/4 3-69 0

3/4 3-70 0

3/4 3-71 0

3/4 3-72 0

3/4 3-73 0

3/4 3-74 0

3/4 3-75 0

3/4 3-76 0

3/4 3-77 0

3/4 3-78 0

3/4 3-79 0

3/4 3-80 0

HP85 20/09 4-db Rov. 4

. __ _g 5/85 HOPE CREEK GENERATING STATION DRAFT TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES Revision Pages Numbers 3/4 3-81 0

3/4 3-82 0

3/4 3-83 0

3/4 3-84 0

3/4 3-85 0

3/4 3-86 0

Insort to pg. 3/4 3-86 1

3/4 3-87 0

3/4 3-88 0

3/4 3-89 0

3/4 3-90 0

3/4 3-91 0

3/4 3-92 0

3/4 3-93 0

3/4 3-94 0

3/4 3-95 0

3/4 3-96 0

3/4 3-97 0

3/4 3-98 0

3/4 3-99 0

3/4 3-100 0

3/4 3-101 0

3/4 3-102 0

3/4 3-103 0

3/4 3-104 0

3/4 3-105 0

3/4 3-106 0

3/4 3-107 0

3/4 3-108 0

3/4 3-109 0

3/4 3-110 0

3/4 3-111 0

3/4 3-112 0

3/4 3-113 0

3/4 3-114 0

3/4 4-1 0

3/4 4-2 0

3/4 4-3 0

3/4 4-4 1

3/4 4-5 0

3/4 4-6 0

MP85 20/09 5-db Rov. 4 t.

5/85 HOPE CREEK GENERATING STATION DRAFT TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES Revision Pages Numbers 3/4 4-7 0

Insert A&B to O

page 3/4 4-7 3/4 4-8 0

3/4 4-9 0

3/4 4-10 0

3/4 4-11 0

3/4 4-12 0

3/4 4-13 0

3/4 4-14 0

3/4 4-15 0

3/4 4-16 0

3/4 4-17 0

3/4 4-18 0

3/4 4-19 0

3/4 4-20 0

3/4 4-21 0

3/4 4-22 0

3/4 4-23 0

3/4 4-24 0

3/4 4-25 0

Insert B&C to O

page 3/4 4-25 3/4 4-26 0

3/4 4-27 0

3/4 4-28 0

3/4 5-1 0

3/4 5-2 0

3/4 5-3 0

3/4 5-4 0

3/4 5-5 0

3/4 5-6 0

3/4 5-7 0

3/4 5-8 0

3/4 5-9 0

3/4 6-1 0

3/4 6-2 0

3/4 6-3 0

3/4 6-4 0

3/4 6-5 0

3/4 6-6 0

MP85 20/09 6-db Rev. 4

c 5/85 HOPE CREEK GENERATING STATION DRAFT TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES 1

Revision Pages Numbers 3/4 6-7 0

3/4 6-8 1

Insert A to pg. 3/4 6-8 1

Insert B to pg. 3/4 6-8 1

Insert C to pg. 3/4 6-8 1

3/4 6-9 0

3/4 6-10 1

3/4 6-11 1

3/4 6-lla 1

3/4 6-llb 1

3/4 6-11c 1

3/4 6-11d 1

3/4 6-lle 1

3/4 6-11f 1

3/4 6-llg 1

3/4 6-12 1

3/4 6-13 0

3/4 6-14 0

Insert A&B to 0

page 3/4 6-14 3/4 6-15 0

Insert to pg. 3/4 6-15 0

3/4 6-16 0

3/4 6-17 0

3/4 6-18 1

Insert A&B to 1

page 3/4 6-18 3/4 6-19 0

3/4 6-20 0

Insert A&B to O

page 3/4 6-20 3/4 6-21 0

3/4 6-22 0

3/4 6-23 0

3/4 6-24 0

3/4 6-25 0

3/4 6-26 0

3/4 6-27 0

3/4 6-28 0

3/4 6-29 0

3/4 6-30 0

MP85 20/09 7-db Rev. 4 ye c,

p-,

am

-,e y.

,p w

+7----t-

-fw

--e,,.w y

  • - - - ~ +-

c 5/85 HOPE CREEK GENERATING STATION DRAFT TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES Revision Pages Numbers 3/4 6-31 1

3/4 6-32 0

3/4 6-33 0

3/4 6-34 0

3/4 6-35 0

3/4 6-36 0

3/4 6-37 1

3/4 6-38 0

3/4 6-39 1

3/4 6-40 1

3/4 6-41 0

l 3/4 6-42 1

3/4 6-43 0

3/4 6-44 0

3/4 6-45 0

3/4 6-46 0

Insert A to pg. 3/4 6-46 0

3/4 6-47 0

3/4 6-48 0

3/4 6-49 3

3/4 6-50 3

3/4 6-51 3

3/4 6-52 1

Insert A to 1

page-3/4 6-52 3/4 6-53 0

3/4 7-1 0

3/4 7-2 0

Insert E&F to O

page 3/4 7-2 3/4 7-3 0

Insert to pg. 3/4 7-3 0

3/4 7-4 0

3/4 7-5 3

Insert A to pg. 3/4 7-5 3

3/4 7-6 0

3/4 7-7 0

3/4 7-8 0

3/4 7-9 0

3/4 7-10 0

3/4 7-11 0

MP85 20/09 8-db Rev. 4

C i

i

/

}

6 5/85 HOPE CREEK GENERATING STATION DRAFT TECHNICAL SPECIFICATIONS x

c LIST OF EFFECTIVE PAGES J

Revision Pages Numbers 3/4 7-12 0

3/4,7-13 0

3/4 7-14 0

l Insert B&C to O

page 3/4 7-14 3/4 7-15 0

Insert D to pg. 3/4 7-15 0

3/4 7-16 0

3/4 7-17 0

3/4 7-18 0

1/4 7-19 0

3/4 7-20 1

3/4 7-21 1

3/4 7-22 0

3/4 7-23 1

Insert to pg. 3/4 7-23 0

3/4 7-24 0

~

3/4 7-25 1

Insert to pg. 3/4 7-25 0

3/4 7-26 1

Insert to pg. 3/4 7-26 1

3/4 7-27 1

Insert to pg. 3/4 7-27 1

3/4 7-28 1

Insert A&B to page 1

3/4 7-28 3/4 7-29 0

3 t

L 3/4 8-1 0

Insert A to pg. 3/4 8-1 0

Insert B to pg. 3/4 8-1 0

3/4 8-2 0

Insert to pg. 3/4 8-2 0

3/4 8-3 0

Insert to pg. 3/4 8-3 0

3/4 8-4 0

}

3/4 0-5 0

Notes to pg. 3/4 8-5 0

3/4 8-6 0

3/4 8-7 0

3/4 8-8 0

Insert _ A to pg. 3/4 8-8 0

MP85 20/09 9-db Rev. 4 x

5/85 HOPE CREEK GENERATING STATION DRAFT TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES Revision Pages Numbers 3/4 8-9 0

Insert A to pg. 3/4 8-9 0

Insert B to pg. 3/4 8-9 0

3/4 8-10 0

Insert A to pg. 3/4 8-10 0

Insert B to pg. 3/4 8-10 0

3/4 8-11 0

3/4 8-12 0

Insert to pg. 3/4 8-12 0

3/4 8-13 0

Insert to pg. 3/4 8-13 0

3/4 8-14 0

Insert to pg. 3/4 8-14 0

3/4 8-15 0

3/4 8-16 0

3/4 8-17 0

3/4 8-18 0

Insert to pg. 3/4 8-18 0

l 3/4 8-19 0

3/4 8-20 Sheet 1 0

3/4 8-20 Sheet 2 0

3/4 8-20 Sheet 3 0

l 3/4 8-20 Sheet 4 0

l 3/4 8-20 Sheet 5 0

i 3/4 8-20 Sheet 6 0

3/4 8-20 Sheet 7 0

3/4 8-21 0

3/4 8-22 Sheet 1 0

3/4 8-22 Sheet 2 0

3/4 8-22 Sheet 3 0

3/4 8-22 Sheet 4 0

3/4 8-22 Sheet 5 0

3/4 8-23 0

l 3/4 8-24 4

l.

3/4 B-25 4

3/4 8-26 4

3/4 8-27 4

3/4 8-28 4

3/4 8-29 4

3/4 8-30 4

3/4 8-31 4

MP85 20/09 10-db Rev. 4

F c

5/85 HOPE CREEK GENERATING STATION DRAFT TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES Revision Pages Numbers 3/4 9-1 0

3/4 9-2 0

3/4 9-3 0

3/4 9-4 0

3/4 9-5 0

3/4 9-6 0

3/4 9-7 0

3/4 9-8 0

3/4 9-9 0

3/4 9-10 0

.3/4 9-11 0

3/4 9-12 0

3/4 9-13 0

3/4 9-14 0

3/4 9-15 0

3/4 9-16 0

3/4 9-17 0

3/4 10-1 0

3/4 10-2 0

3/4 10-2 0

3/4 10-4 0

3/4 10-5 0

3/4 10-6 0

3/4 11-1 2

3/4 11-2 2

3/4 11-3 2

3/4 11-4 2

3/4 11-5 2

3/4 11-6 2

3/4.11-7 2

3/4 11-8 2

3/4 11-9 2

3/4 11-10 2

3/4 11-11 2

3/4 11-12 2

Insert A to pg. 3/4 11-12 2 3/4 11-13 2

3/4 11-14 2

3/4 11-15 2

3/4 11-16 2

3/4 11-17 2

MP85 20/09 ll-db Rev. 4

a 5/85 HOPE CREEK GENERATING STATION DRAFT TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES Revision Pages Numbers 3/4 11-18 2

Insert A&B to pg. 3/4 11-18 2

3/4 11-19 2

3/4 11-20 2

3/4 11-21 2

3/4 12-1 2

3/4 12-2 2

3/4 12-3 2

3/4 12-4 2

3/4 12-5 2

3/4 12-6 2

3/4 12-7 2

3/4 12-8 2

3/4 12-9 2

3/4 12-10 2

3/4 12-11 2

3/4 12-12 2

3/4 12-13 2

3/4 12-14 2

Bases for Section 3.0 and 4.0 0

Note to pg. B3.0&4.0 0

B3/4 0-1 0

B3/4 0-2 0

B3/4 0-3 0

B3/4 1-1 0

B3/4 1-2 0

Insert A to pg. B3/4 1-2 0

B3/4 1-3 0

B3/4 1-4 0

Insert to pg. B3/4 1-4 0

B3/4 2-1 0

B3/4 2-2 0

B3/4 2-3 0

B3/4 2-4 0

B3/4 2-5 0

B3/4 3-1 0

B3/4 3-2 0

B3/4 3-3 0

B3/4 3-4 0

MP85 20/09 12-db Rev. 4

a 1

5/85 HOPE CREEK GENERATING STATION DRAFT TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES Revision Pages Numbers B3/4 3-5 0

B3/4 3-6 0

Insert to pg. B3/4 3-6 0

B3/4 3-7 0

B3/4 4-1 0

Insert B to pg. B3/4 4-1 0

B3/4 4-2 0

B3/4 4-3 0

B3/4 4-4 0

Insert to pg. B3/4 4-4 0

B3/4 4-5 0

Insert A to pg. B3/4 4-5 0

B3/4 4-6 0

B3/4 4-7 0

B3/4 4-8 0

B3/4 5-1 0

B3/4 5-2 0

B3/4 6-1 0

Insert to pg. B3/4 6-1 0

B3/4 6-2 0

B3/4 6-3 0

B3/4 6-4 0

B3/4 6-5 0

Insert to pg. B3/4 6-5 0

B3/4 6-6 0

B3/4 7-1 0

B3/4 7-2 0

Insert to pg. B3/4 7-2 0

B3/4 7-3 0

B3/4 7-4 0

Insert to pg. B3/4 7-4 0

B3/4 7-5 0

B3/4 8-1 0

B3/4 8-2 0

B3/4 8-3 0

B3/4 9-1 0

B3/4 9-2 0

B3/4 10-1 0

B3/4 11-1 2

B3/4 11-2 2

B3/4 11-3 2

MP85 20/09 13-db Rev. 4

y 5/85 HOPE CREEK GENERATING STATION DRAFT TECHNICAL SP',CIFICATIONS LIST OF EFFECTIVE PAGES Revision Pages Numbers B3/4 11-4 2

B3/4 11-5 2

B3/4 11-6 2

B3/4 12-1 2

B3/4 12-2 2

Section 5.0 0

5-1 0

5-2 0

5-3 0

5-4 0

5-5 0

5-6 0

Section 6.0 0

6-1 0

6-2 0

6-3 0

6-4 0

6-5 0

6-6 0

6-7 0

6-8 0

6-9 0

6-10 0

6-11 0

6-12 0

6-13 0

6-14 0

6-15 0

6-16 0

6-17 0

6-18 0

6-19 0

Insert A,B&C to O

page 6-19 6-20 0

6-21 0

6-22 0

6-23 0

6-24 0

6-25 0

6-26 0

Insert B to pg. 6-26 0

6-27 0

6-28 0

6-29 0

MP85 20/09 14-db Rev. 4

Q 10 JAN 1993 INDEX LIMITING CONDITIONS FOR OPERATION'AND SURVEILLANCE REQUIREMENTS PAGE SECTION 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES A.C.

Sources-Operating...............................

3/4 8-1 A.C.

Sources-Shutdown................................

3/4 8 l

3/4.8.2 0.C. SOURCES D. C. Source s-0perati ng............................... 3/4 8-h l

~

Jr D.C.

Sources-Shutdown................................

3/4 8-W A 3/4.8.3 ONSITE POWER DISTRIBUTION SYSTEMS 9

l3 Di stribution - Operating.............................

3/4 8-W

.* /Y Distribution - Shutdown..............................

3/4 8-X

\\

3/4. 8. 4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES.

A.C. Cir;;it: In:id: "-i : j Cent:f.= nt.............

3/4 8-15 Primary Containment Penetration Conductor Overcurrent A&

Protective Devices.................................

3/4 8 97-Motor Operated Valve The)1 Overlo d Protection.-AfrH*3/4 8M o er.ted alw. rhec overle Pr.+ec+ en -mer evemo 3/9 e-159 Z t Aohr r

Reactor Protection Systen Electric Power Monitoring..

3/4 8-er m 23 3/4.9 REFUELING OPERATIONS l

3/4.9.1 REACTOR MODE SWITCH..................................

3/4 9-1 I

3/4.9.2 INSTRUMENTATION......................................

3/4 9-3 3/4.9.3 CONTRO L ROD P0SITION................................. 3/4 9-5 3/4.9.4 DECAY TIME...........................................

3/4 9-6 3/4.9.5 COM1UNICATIONS.......................................

3/4 9-7 3/4.9.6 REFUELING PLATF0RM...................................

3/4 9-8

' cku IE Tso f.h.% Breh Oveccurrent Prokhvo Devic,e5 J/V g-2,4 Pa~er Rsn3e newon n.,, t.<.n3 syt,m Gfestm P.wsr-M.,,:{,.;,,y 3/4 g-3 \\

40STS (M/4) ix StV. If

E

'C RRMM

A; E

h W

E

8. jl

.t

    • 1

~

3"

.I w,

I..

g e

a i

i W5 t

3 s

i i

3-3 g a

$5_!

s mamm ame nNa u

g O,j g*

Egt e=g g_a y

,a

~~~~

~~~

s j!g.1 mj:!

ee It

^]I" N

o

[*N i

5 l

b

O 4 _52 E

=

c

-g'"

5 55 -

e to-

l J

M

=

"5 I

J8 eg

(?

i l

a 5E

    • d
dt i.

dt5 p q m:;: > e n

3 lla:ag 4

=

a.

g.~

m s

, = =

..e-2 2

t g g t * *i 5

~E 3

3 4'

q 1-

.3 2

. -r. g u t s2 A. l

.1"TS*.1 'i 1=

2 i.

cQ:

i.SS 4

1 5

% is 35I: 15 a~

o"-

  • W 3

S i.e Esn g 73

^-

.g,E g'

7 5

s$h:

a

'S.!s.k.!

g l i Y

3"I h

E'

=

J i s1.s_lm '.3 s

a8 2 r*

a 3

m!

s e

e:

.$ -s *;

a er a

e*

a "8

g-3 2" "M'I_8 ellgsI,al1o

.t.

g.

y,,,p3, 2. g.t

- it g _;

. t. :

gt e

4-l,4_I 8-3.L,,312 s

,L L,

I.

13 g a_

e1 M

=

3.

x3

-=

8 8

.g 3

aI 88 ost

'I::8s

"=-

ss.f1! a l

  • 8 J-2 j
.I.I2.1us.! eja:s 9 E

s ne s! *a.a t.s,.y.

8 p1 8

e

=

s=is 5 E-l mal r!a g.B.n

.: 2 I

5a v[s*e!!s,jeJ s-R 33a 3.L

.w, E

en ff J n.. q 2..e:

ew

a. sal a

I I2 g.

s s

m. s.,. s.

yev3m. p3 y.,it -

--st i a

e t.

a y

3 s

e

=la

. van

~

E Mu 4

tEEJ E

E

--3. = " 3 3 e

63 wi O

5 4

37 we9s ca.tet 3/4 3 Rev.4

..- 1 00-:T: (:r./*;

10 JAN 13B3 F

I F F

P U %

T p

at El l. Eit-3 M*g l !

W n!

3

. %I i

I

.c Z C

o 1.f

,. O 2

3 s. * ^ W, "M

E o

7 m;!"a Ie :.NasU rn

.ve i

.u j q., h h

pn.m

.!=88 Lup a

s a) n

..r m

l!

Rg_= m.

s :.

h gg-i 4 g ie x nu u b m 3

c

-z Iscoc ca j= sac;p we CCI s,N > A as,W e A M M,N w

D vi 1

g,e

$ Y AlvivlAN E

y r

r h

u c-

.h

.s a-3

  1. 6
4. m R
  • 2*h a

e v

gg 12.!

  1. 3*

.M

-. ' Le s _ : -'# %,h=e,s p

5 E,

". ]O

-s e

2 22,%

a v

1 a:c; o n t e a %.,

  • 12,

-I a

x=.

-g.-

vu w

J.

r=xg2 n.

g.gst e

- L7 1s

.n >!p en m

t,

>+

.rs a [ - s m,-

g~ a n

,ccJ.

e.ng g,

e As p, sa

=.

1.,

.i vi ANANo sbi v

g

?

?

W

Ej

\\h 4..

s

--y s s m

4= g.g a

2

=

p m

=

5a ed

-e

=

m 3

j, y

ji:-

f e

5 I

i F

s s

sh

.i

...r 1 e

c E

v o

F j j^

~

  1. 8-1 e-E e

es a

s s,p

.n a

,v s

's o

a et 3

3c ais p

a a

A 7'

e,,sl s. n!.

2 3

n I'

a s b; E,

3 s

g

}

I g

C m sE g Ai j

!$b si 3

"E4E d E '

j!

m 5'gt3"M E 8-4

.s dj. s

-i

. 't W

5.!&

k' JAW 3*

.3 1

.s

.l s*g j

%,E a

w

  • 8.
  • E-==Eu!

g m

m o

j.5..

"?8

  • ' ~

s' p pg M

e 33E;;

g a.asaw e

e e. p s 4

E *a E

e

.D " '

3/4 3 Rev. 4 ll

l L

l TABLE 4.3.3.1-1 (Continued) j y,

i7 EIERGENCY CORE COOLING SYSTEM ACTUATION INSTittstENTATION SURVEILLANCE REQIllREMENTS r

CHAl#IEL OPERATIONAL

j CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH TRIP FUNCTION CHECK _

TEST CALIBRATION SilRVEILLANCE REQUIRED J>;,F AUTOMATICDEP8ESSURilATI0ffSYSTEM 4.

a.

Reactor Wessel Water Level -

g R

A 1, 2, 3 Low Low Low, Level 1 S

M b.

Drywell Pressure - High 151 iM

(

4R 1, 2, 3 c.

A05 Timer NA M

, (n.

Q 1, 2, 3 I

I d.

Core Spray Pump Discharge Pressure - High (55 M

$R1 1,2,3 J

e.

WHR LPCI Mode Pump Discharge Pressure - High

$5[

M JNJ 1, 2, 3 A

f.

Reactor Vessel Water Level - Low, O

1, 2, 3 E

Level 3 S

M R

[hift NA 1, 2, 3

[

,q.

Manual Initiation MA NA M

q I, 2 3 h, ads Drysali Pressars gTherx

,,,,e 3

t.s.7t0550FPONERf.. e5 w s,.

g.

,,a a.

4.16 kw Emergency Bus Under-p voltage (Loss of Voltage)

NA NA R

1, 2, 3, 4**, 5**

i l

5 1

4 b.

4.15 kw Emergency sus Under-voltage (Degraded Voltage)

S M

R 1

2, 3, 4**, 5**

e All other l

$(f) Manual initiation switches shall be tested at least once per 18 months during shutdo r

i

=r 31 dann ma --t af circuitry reautred to be tested for automatic system actuat.ina 2 _

l When the system is required to be OPERABLE per Specification 3.f 2.

~

Required OPERABLE when ESF equipment is required to be OPERA 8LE.

l e

Not required to be OPERABLE when reactor steam done pressure is less than or equal to $100) psig.

l f

4 M Cahbr-de hp \\ add, d Iend once F M %s.

e j

i e

0

o v

C LASS IE. ISOLAT80sJ BAEAKEA h -TAIJeWEE-fkmue**" ** tid OVERCURRENT PROTECTIVE

~

LIMITINS M ITION FOR OPERATION

^ '^^-- ; overcurreNt protective z -t 1 :Wi'O ^SLt. K (Ass IE,Isol44s.

3.4.48Ali d---- 2r -'.4 6

shallbeCPd on bre'M devices shown in T ele 3.4

~

C APPt.ICASILITY: OPERATIONAL ITIONS 1, 2 and 3.

(97;pp.g, q,i.oq q art) 5

'y $

$ 8:

-' ^ ----

Wth one or more of the

^^'-#^

-" 'zni~;D-U^5 }1 I~noperatie, declare rotactivedevicesshowninTale3.8.4$

a.

~

overeu inoper ele and jppsy wm isoktorgb w r-the affet t or aff sr.am.

1.

or. 0 -- 4.

ci it reaka rg ze

,.S r 4. }

)

ci t(s tr ing he socia ci it b r(

wi n 72 rs v ify t i tb akar be 1

(/

at est a

r7 f+

remove the inocerele circuit breaker (s) 480 It reui brea se;vice O '

r-

20 0; ; cut:-) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and verify Fe at faaet once per 7 days the inocerele breaker (s) to be 'cnz.#a s.=

thereafte,.

OKi%"14 7e/A',mczfa7"? ""I'NN The provisions of Specification 3.0.4 are not applicable to overcurrent

- -m

-' - r = ~ ' -- >

r D.

devices in,"'" " r 5.D' - r asa um 2 r :(olt circuits which have the inoperele circuit c-

=r: --

' -- L breaker ' ;-':{3th

$URVIILLANCE trsT5 airam-t'ach of the Clau IE. iset4 Hen 2-e z,-- overturrent

.q-L__ _ ---

1 shall be demonstrated OPERA 8LE:

4.8.4 protective devices shown in Table 3.4.4 At least once per 18 months:

M ;" ;^^j 3gy a.

circui b rs medius 1

ting bas [s, at I ast of sy ver1ryi 1.nas in a ro are PIRAS by set

'-"g, the ircui breake at:

- :..;17 and pe orsi :

a)

A RATION f the socia pro ive

lays, l

b) ha i system unctior 1 test ich fru,1udes inula tc tion a the stas and verifyi g the each

'~

I re and ociated freut breake and ove rcu t

i rol si its fun :tien as designev c) e each c revit bri skar fe ind inopekable ing se

(

unctione tests, an additi anal rephsenta ve s le o

t ?:::: _ ;' :!' the cir cuit breakers o1 the i r le ftypeshal also be functiotally tes Lad unt I no i re f Ivres i

are found or all ci rcuit bi eakers cf that type hive Kionally testet

^

I w e snest 3/4 64M Rev. +

5"57'O u

l I

t I

,W t

=

r

g

~

~

1 Q JAN MS

( deH twe el", b>

ELKTal m ' M

/,j m. In.

  • 5 ggygttL=r 9 1Re effs (Continued)

J ty selecting and functionally testing a representative s q

of at 1esst M of each type of lower weltag Circuit treaters selected for functional testing shall to f

selected en a rotating taste.shall consist of injecting a c

..;, ; 1em.g I.

4.!, '.;;.tr rans vertrying J Z~,;f ;.'

L circoM brea]rers that the circuit tmaker operetas within Os time delay tend =

4 W t/ W;A solid

, the picts of the short,1as dele e For width for that current specified by the manufasturer. The instantaneous element shall to tasted by injecting a current ei N STAf C *.'P g;,, %>

equal to $25 of the picte value of the element and verifying M pe instantanoeusIy wi O ne intan*

h e h oc4it u l +'54ia

)

mdy lg perdfrm k

' 0a% Os cI M S I Ntional time delay.. Molded case cir efructofs 4/Mjafd aise follow this precedure ancepttwo tr 7'g m of prfaWe

)

tasting shall to restored to OptRABLE status prior to resu 4,gertfj4he Wat-For each circuit treaker found insperstle duringg,gg

)

I

'"'"+ euracterirtiessperation.

4M fiC""P e4g;brAfltq ggg gyggggggj ggggg, y ggggggggy pgppgggggg g k

f O s insperatie type of 4ke +rir cita'"ff./at least M of all the circuit trea art ot d until no l

y shall aise to functional y tes afound er all circuit treakers of functionally testad.

sel ng and ienally testing a resenta ve saspie

'T f each of en a ting basi. Each resentati saeple fases 11 fact at least of all of type. The ensi test 11 cens - of a destructi tas unich strates t the fus see its

's sign celta is. Fuses found i rable he replac with LE

/

j resis I'

duri these tonal sting shal' 'ereachfupefoundi rable ret <en.

itional espresentati e saspie f

prior ta resuming ng Oese ' unctional sts, an

---of t least 115 of all es of the type shal' he funct 11y tad unt11 'ne aere f lures are i er all fuses of t

have tehn functi 11y testadj J-At,least once per 43 aanths by subjecting each circuit tre inspection and preventive asintanence in accordance w b.

prepared in conjunction with its manufacturer's ressem t

I lion'clsek m e xs n.+

_... a,,

ll h

a TABLE L S.4.5 - (

cLA% IE. IsoLATacrJ Ms4ksA.

Pqe i 4 7.

PAoTecTavE esvacas

} cvsrcuxAEAT SY 4 Loc 4 stM4L)

(54a4Ks4 TAWPEb 490 vac. PowsA cacotT sn4xEds 1

TYPE. A AR-54-So Class II Class II

=a '*1aas II W Descristian Circuit A

Ereaker No.

Reactor Ausiliaries Cooling 105410 52-41011 System Pump 1AP209 Redweste and Service Area 108410 52-41014 NCC 10B313 Reactor Building Supply Air 105410 52-41024 Bandling Unit 1SVB300 Reacter Aus111eries Cooling 103420 52-42011 System Pump 13P209 I, Radweste and Service Aree 199420 52-42014

' MCC 108323 Reactor Building Eshaust Fan 105420 52-42024 13V301 Reactor Buildi ly Air 103430 52-43024 Bandling Unit 1 Control Red Drive Pump 1AP207 108430

$1-43014 Centrol Red Drive Pump IEP207 108440 52-44014 Reactor Building Supply Air 105440 sendling Unit 1AVB300 52-44024 Radweste Area Supply Fan OUV316 105440 52-44034 Reactor Area NCC 108252 198450 52-45011 Redweste Area Eshaust Fan 198450 52-45014 OAV305 Emergency, Instrument Air 198450 52-45024 Compressor 10K100 Reactor Building Eshaust Fan 108450 53-45034 ICV 301 Reactor Area NCC 108262 198460 52-46011 O

nav. +

e 3/+ t - a c, t

t

o TA St.E 3, S.4 E - (

C. LAM IE, tsocATec4 iMyggA, PAoTecTive Osvace.s Pye

2. o f 2.

ovsAcuAAs.4T L. Ce=4;wel.

p.

class I czess II

= -- 13 v--a Descristian ctremit aus h

108460 Radweste Area Ishaust Faa 52-46014 ONV205 108470 Reacter Area IICC 105272 52-47011 183470 Radweste Area Eshaust Fan 52-47014 OCV205 Redweste Arm M1y Faa M16 i

198470 52-47024 108470 Technical Support Center 52-47021 MCC 003474 10sese Reacter Area ascC 10s2s2 52-4s0.11

~

108480 Reacter Buildia0 Eshaust Fan 53-40024 IAv201 480 VAC. McL>ab CASE C.tM, cutt Sne.Agag,s

1. TTPt HF&tSO Ctess IE.

cge., ag,,

PJ8m CI4*S' IE L'*M. C>escrieflei circui+

go necaser M_

II OD 52-451022 Security System Inverter 0AD405 103473 52-471022 M555 Comfuier I"W8ff8f' 10644i 32,_441045 10D485 t

Rev. 4 3/4 g-n

a 4.

CLAS% iE. t SOLA flod 6,REAgg

_E'.ECTRICAL POWER SYSTEMS [

Ihi-'i CaTO;C =""*O" C SJ"O' OVERCURRENT PROTECTIVE OEVICES LIMITING E ITION FOR OPERATION ( CeteTWu d!C0

- Untration-conductep overcurrent protective

3. 8.4$A11 "='~- "-

'4 devices shownTATe%. ; -1 ssaTFiie OP(RA8LE.Q g;g,, g4 6 --

OPERATI NOITIONS 1, 2 and 3.

q 4,wl 644xur y APPLICA8TLITY

b

~

ACTION:

'- ::J" M With one or sere of the 7 '-- j - ;-f- ;3_;;-3.8.

f~fnoperaale, declare s.

overcurrent protective devices shown in Taele the affected systes or component inoperable and app the appropriate ACTION statement for the affected system, and

[ For f' O r 4.

3 kV ci itbreayrs,deAnergi the j' " 'h 4.1 ky]

circu t(s) by poing assoc ated undant ircuit b aker(s with n 72 hou and we ify the dundan circu breaker be 1pped at east onc per 7 s there, ter.

_440 vo circui breake

' remove the inocerable circuit breaker (s) 2.

From service W ' ::- :: ;!.; ;;;;M:-} within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and verify the inoperable breaker (s) to be 'c;;-....? at least once per 7 days

- - 42 Ji-thereafter.

Otherwise. be in at least HOT SHUTD0bN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> COLD SHUTDOWN within the felicwing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The provisions of Specification 3.0.4 tra_nat_ appl.icable to overcurretti

  • ;= = u k n.,n.% r (,;.; K. R;;,h) r b.

devicesjtt.P& -n ~hlt circuits which have the inoperable sfrcuit Z.t-f;;:f._i- **M

@- :;ker ' - " '

brea SURVEILLANCE ciam, ie. isel'fi8m brmker 2

1ratierrarutgGP overcurrent 4.8.4.

ach of the & -- ; - -E! --M 1shallbedemonstratedOPERAS%

protective devices shown in Table 3.8.4

,er78.ontos

'p' C ; G r.ast a.

ircuit ers tagehbasis that the um v By v rifyf rotat at le t of a

OPERAS by sel ing, on circui breakers -' :::7./.;;:4...;11 d perf reing:

A LCALIRATIONoftheas 1sted rotecti e relays and Ur Surve d.mcc

)

Et stad system f wtional test ch inc1 es sfauf tad geIgireme,th 4 %.4,5.,

tc tion of the system and erifyin that sa re ay and as ociated ircuit teakers ove urrent c

rol ci its f ion as signwd.

)

e each c uit b kar fe inoper le dur ng thes unctional tests, additi

1. rep entati sample of

/-'-'-

the c it brea ers of inos sole

^ ' - '

/typeshal also be functi 11y tes until no more failu s l

are found or all reuit breakers o1 that have een

[

/

function 4 11y tes s

3/4 Sp}28 Hoot e,senW Rev.4-

?

2-5?! ' r- 't-;

i

TA6LL 5. D.4. G - (

Ct44 IE. tSotAT88sJ S45488A Page l of Z OV8AtAsaA6AIT PacTacTsus. DavectS (pttp4M AND SacKuP c(4 cutt sde4xtAs) 430 VAC. Moldd!d. Case Circuif Brauers

~(ye HF E 5'

'^

6..

Class IE Cl rey;+ SamMar No._

Loca.fim Triy T. 4 SYsTsM scutemmar eov,4sb St-241045 108147.

-I' M Lo8/d10 V4C Distribofieg "f M P4nel to Y tat st-ss2.045 Io 5 1 2.1.

gg zagAas vec bisfel6uf /,n tm t%,( g ay s,t tar / azo vac talsfel6uflen Et-151e43 to e I w a.

TM M

ikael 80Y to3 st-L4Lo43 t ea 242.

-T M tet/izo VAc. bisfr16of ten

'M PaneI toYton s t. t 3 t e z.i sostst-2.M

    • 44 Header be.mMm Drain s t - n2. t o t i o s a.s s.

TM Ise(44!,n v4lv e i ns-H v-Fa : t 188151-IM M SIV Odn**c/. Seal 445 Swerly st-t%LI2I s 2.- 13s t 0 2 lo 62 % t TM Valve t kP - N Y-5 87.9 a s t - 152. lit toona sg ga;. s+,4, L;,4 A Kszy Ouu.4rg

. s2.- 2.3 1: 4 s e a tSL TM Sent das suppsy valve ikP-Hv.sts46 Msin steam Line & MS2V Cun**n(

52.

L stl'A s t oaast zg WL 1%t tiL 0&L5L

-fM Saal des Sorrfy Velve t MP.Wv.5HSEb SL-L%L I4 t 10SLSE LM Main Steam Li e c Mszv Oodu.r/

i st - 13t t44

$8 s sW TM Sul da.s Supply V41ve IMP-4v sss6a s t-t%t 43 sostst z.g g,;

u,,, t;.e b Mstv opfbaard 1

51-nt895 (8613'

'T M Sul 44* Sorply Vdive iKP-dV-5"78 st-14 tit i s ost4s IM Mste Zabur4. sent &45 sverly 51-141 a t%

s os t4L TM valv e, tur-se v-sst44 s s.- L4 t ts t so a z4t ze4 Mai, $444% Line 4 Mstv z Weg st - 142.o24 top 214L

-tut 544164s Sorr ty VAlr e (KI-NY"ISIid M4ia steam Line & M32v Im6acW' 5t-L4L LM test 4 t-IM Se4t des Surely faire t@- 8("-5815M st-t4tc64 c624L

-rm st-24tt41 s *

  • L4 L IM M*ia 80*
  • Li"* C d'l# ** **"<

st - L4t 83 te s a+t Tg seat des suerty Velve (KP-HV-58364 3/4 8-af hv.Y

g

~

TABLE 3.B.4..G - (

CLAM IE. (SoLATassJ S454sgA P e l ef L N

l Ov84mAA&dT PAoTECTavs. DEvacas CONT (NUSb st-14L H5 t es24 L IM Mala stfAM b[Mc D N61Y Imbatr'd, 5L-7Ab it4 toS24 L

~D4 Se4144, supp y W/ve, (gr.g y.gy 374 l

6 lt w c.u b; x u q e T. Fred e,-

ss-Mttid ios24t IM st.- 1.4 t tt4 sos 242 TM valve IAE - Hv-Foti paed safer Line d'ress Tie Isolafisq st-13t854 gost%t.

In st-ISLItt

  1. 0623L Tr4 Velv e # 4 g. W V-4:44 M4,gk4d de d$

[0 0

g y

5,+,, m r ~s

+"-

9 9

3}q t - 30 Ru. +

O i

~

I

?! id u ll.

i MM8 PANot AJEUTtsel Madsfabe SYSTEM _fLitTR!f4L POWER aw!Testm r

ly shall to GPERABLE.

_ qe. N

_,_.g.h_.,.f

's peer sgp i

rang

~

ArE2tpg1L1Tf: At all times.

2 yo,arfahaNM3 a.

eiestris sonitertag channei eer en smervt= 7..a r Men ene,NM.S ran power so ply faeperable, restore the feeperable peuer i

seni og channel to GPERAS 2 status wtthfa 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or Q" - d* **# T 3,,

assestated pev ven NMS power ogp1L..halei c.1rcubt.

^

r ---

~ L-NMS h.

M th both j e estris anniterf ag.shannels fier en Inservies per renga.

NMS pouer 1 faeperele, restore at least one electris pomer'teatterfag channel to states withia as afastas or 6 deen 45 3e i

the assestated F range. NMS power egely -t

  • '"*N*

~

EURvf!LLAuct s iRT.

4.8.4J. Th.e. abo.ve.speciffed[

ectris aan torfag shonnels shall to et.r.ed s.

At least ease per 6 anoths by performance of a OWeEL FWCTIONAL TEST, l

and t.

At least once per la months by demonstrating the OP DABILITV ef ever-voltage answ-voltage, and under f protective instrumentatIen by performance of a OWsEL BRATION includfag s h leted avtamat1s asteetten of the protective relays tripping legis and output siremit breakers and verifying the feIIeuing i

setpelats.

j

); 'n v4c.* (ws a

)

L,over-veisege i 1 3 2 v A c* 0 W 5 4 S- )

n.

mer-. ems. t ser ve

  • Csus A.

), larve* Cws s.

mer-fre ns, a s7 Hm, -o,+ 2. 7.

  • F%=1 setp.mts +o be ca.dirmal by hil Musmm,ffs.

i neN edent, l

S/4 9-31 A'V Y i

I h

~

,

Retrieved from "https://kanterella.com/w/index.php?title=ML20117J491&oldid=4283415"