ML17157C390
| ML17157C390 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 05/31/1993 |
| From: | PENNSYLVANIA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17157C389 | List: |
| References | |
| GL-89-04, GL-89-4, ISI-T-200.0, NUDOCS 9307020026 | |
| Download: ML17157C390 (275) | |
Text
ISI-T-200.0 SUSQUEHANNA STEAM ELECTRIC STATION UNIT 2 INSERVICE INSPECTION PROGRAM PI.AN PUMP AND VALVE OPERATIONAL TESTING
'i':,;::::;.':-,"'.:Pr'ep'ar'etI':b'j:>.':::::.:'.':.':;'.': '.,;.',,,pprov'ed:bj,;~>'<5:::'::::::::: Date'.!':
Compliance with NRC Signatures on File Generic Letter 89-04 Responses to NRC Signatures on File Comments Rev. 5 2T-1 05j98 9307020026 930623 PDR ADOCK 05000387 G PDR
it O'
1
SUSQUEHANNA STEAM ELECTRIC STATION UNIT 2 PUMP AND VALVE INSERVICE INSPECTION TESTING PROGRAM
- ,:j>>::,":;.:',"; :'::Reiisioii':::::."-;::'::':::'":.;:::;:::-'::,,",3::>Dated::'::::.':i::;:;';;::~;;.".,"
TITLE:
Page 2T-1 05/93 DESCRIPTION:
Page 2D-1 05/93 Page 2D-2 05/93 LEGENDS:
Page 2LV-1 12/91 Page 2LV-2 05/93 Page 2LP-1 12/91 VALVETABLES:
Page 2VT-1 12/91 Page 2VT-2 12/91 Page 2VT-3 12/91 Page 2VT-4 12/91 Page 2VT-5 12/91 Page 2VT-6 05/93 Page 2VT-7 05/93 Page 2VT-8 12/91 Page 2VT-9 12/91 Page 2VT-10 12/91 Page 2VT-11 12/91 Page 2VT-12 12/91 Page 2VT-13 12/91 Page 2VT-14 12/91 LEP-1 05/93
~ %'
I,
ISI-T-200.0 Page 2VT-43 12/91 Page 2VT-44 05/93 Page 2VT-45 05/93 Page 2VT-46 12/91 Page 2VT-47 05/93 Page 2VT-48 05/93 Page 2VT-49 12/91 Page 2VT-50 12/91 Page 2VT-51 12/91 Page 2VT-52 12/91 Page 2VT-53 12/91 Page 2VT-54 12/91 Page 2VT-55 12/91 Page 2VT-56 12/91 Page 2VT-57 12/91 Page 2VT-58 12/91 Page 2VT-59 05/93 Page 2VT-60 05/93 Page 2VT-61 05/93 Page 2VT-62 05/93 Page 2VT-63 05/93 Page 2VT-64 05/93 Page 2VT-65 05/93 Page 2VT-66 05/93 Page 2VT-67 05/93 Page 2VT-68 05/93 Page 2VT-69 05/93 Page 2VT-70 5 05/93 LEP-3 05/93
ISI-T-200.0
- ,:;','.'::.',::.::":;: Revisioii";.";:j",.':;;":;,:"::,':::i:;:::.'"i':: ';j.",:9ate'I,'::,;';:';:'!;:,j:
Page 2VT 05/93 PUMP TABLES:
Page 2PT-1 12/91 Page 2PT-2 12/91 Page 2PT-3 12/91 Page 2PT-4 12/91 RELIEF REQUESTS:
Page 2RRT-1 12/91 Page 2RR1-1 05/93 Page 2RR2-1 12/91 Page 2RR2-2 12/91 Page 2RR3-1 05/93 Page 2RR4-1 05/93 Page 2RR5-1 05/93 Page 2RR6-1 05/93 Page 2RR7-1 12/91 Page 2RRS-1 4 12/91 Page 2RR9-1 12/91 Page 2RR10-1 05/93 Page 2RR10-2 05/93 Page 2RR11-1 05/93 Page 2RR12-1 12/91 Page 2RR13-1 05/93 Page 2RR14-1 12/91 Page 2RR15-1 12/91 Page 2RR16-1 05/93 Page 2RR17-1 12/91 Page 2RR17-2 12/91 LEP-4 05/93
ISI-T-200.0 Page 2RR17-3 12/91 Page 2RR18-1 12/91 Page 2RR19-1 12/91 Page 2RR20-1 12/91 Page 2RR20-2 05/93 Page 2RR21-1 12/91 Page 2RR22-1 12/91 Page 2RR23-1 05/93 Page 2RR24-1 12/91 Page 2RR24-2 12/91 Page 2RR25-1 12/91 Page 2RR26-1 05/93 Page 2RR27-1 12/91 Page 2RR28-1 12/91 Page 2RR29-1 05/93 Page 2RR30-1 05/93 Page 2RR31-1 12/91 Page 2RR32-1 12/91 Page 2RR33-1 5 05/93 Page 2RR34-1 12/91 Page 2RR35-1 12/91 Page 2RR36-1 12/91 Page 2RR37-1 05/93 Page 2RR38-1 5 05/93 Page 2RR39-1 05/93 Page 2RR40-1 12/91 Page 2RR41-1 12/91 Page 2RR42-1 12/91 LEP-5 05/93
~ v ISI-T-200.0
- .'
- .:;:,";.:;:..;'::: Rem)vari':, i:;:~:: i 9ated::,::i.;'i.:.;'i!:::::;;.':;:.
Page 2RR43-1 ::;:::;:.','::::.:'I:: 12/91 Page 2RR44-1 12/91 Page 2RR45-1 05/93 Page 2RR46-1 12/91 Page 2RR47-1 12/91 Page 2RR48-1 05/93 Page 2RR49-1 05/93 Page 2RR50-1 12/91 Page 2RR51-1 12/91 Page 2RR52-1 12/91 Page 2RR53-1 05/93 Page 2RR54-1 05/93 Page 2RR55-1 4 12/91 Page 2RR55-2 12/91 Page 2RR56-1 12/91 Page 2RR57-1 12/91 Page 2RR58-1 12/91 Page 2RR58-2 12/91 Page 2RR58-3 12/91 Page 2RR584 12/91 Page 2RR58-5 12/91 Page 2RR59-1 05/93 Page 2RR60-1 05/93 Page 2RR60-2 05/93 Page 2RR61-1 05/93 Page 2RR61-2 05/03 Page 2RR62-1 05/93 Page 2RR63-1 05/93 LEP-6 05/93
ISI-T-200.0 Page 2RR64-1 12/91 Page 2RR64-2 05/93 Page 2RR65-1 12/91 Page 2RR65-2 5 05/93 Page 2RR66-1 05/93 Page 2RR66-2 05/93 Page 2RR67-1 05/93 Page 2RR68-1 05/93 LEP-7, 05/93
ISI-T-200.0 SUSQUEHANNA STEAM ELECTRIC STATION UNIT 2 PUMP AND VALVEINSERVICE INSPECTION TESTING PROGRAM The pump and valve ISI testing program at the Susquehanna SES Unit 2 will be conducted in accordance with the 1980 Edition of Section XI of the ASME Boiler and Pressure Vessel Code incorporating through the Winter 1981 Addenda. Specific exceptions from these requirements are included here as Relief Requests. The inservice portion of the program commences at the receipt of the Operating License. Requirements for specific components commence concurrent with Technical Specification operability requirements.
For valves so equipped, remote position indicators will be utilized to demonstrate valve operability. Proper functioning of these position indicators will be demonstrated at least once every 24 months. Safety valve and relief valve pressure setpoint testing willbe conducted using test procedures which incorporate the testing methods of Section 4.09 of ANSI/ASME PTC 25.3-1976. PTC 25.3 Section 0, Section 1, Section 2, Section 3 paragraphs 3.06, 3.07, 3.10, and Section 4 paragraphs 4.01, 4.02 (4.023 only) and 4.09 pertain to the safety/relief valve pressure setpoint testing required by IWV-3512, in varying degrees, and will be complied with, accordingly. PTC 25.3 Section 3 paragraphs 3.01, 3.02, 3.03, 3.05, 3.08, 3.09, Section 4 paragraphs 4.02 (4.021 - 4.022 and 4.024 - 4.029), 4.03, 4.04, 4.05, 4.06, 4.07, 4.08, Section 5 and Section 6 all pertain to more complex safety/relief valve capacity testing, (normally performed by valve manufacturers) rather than pressure setpoints tests, and will be disregarded due to their inapplicability to pressure setpoint testing.
The provisions of Paragraph IWV-3511 shall begin at the receipt of the operating license.
Thermal relief devices are excluded from the program. With the exception of valves providing a high pressure to low pressure boundary (pressure isolation function), valve leakage rate testing and acceptance criteria will be based on 10CFR50 Appendix J requirements as discussed in FSAR Subsection 6.2.6 and Susquehanna SES Technical Specification 3/4.6.1.2. Pressure isolation function testing is discussed below.
Excess flow check valves are installed on instrument lines penetrating containment in accordance with Regulatory Guide 1.11. As such, the lines are sized and/or orificed such that off-site doses will be substantially below 10CFR100 limits in the event of a rupture. Therefore, individual leak rate testing of these valves is not required for conformance with 10CFR50, Appendix J requirements. Functional testing of valves to verify closure can be accomplished by the process of venting the instrument side of the valve while the process side is under pressure. Such testing is required by Technical Specification 4.6.3.4 at least once per 18 months. Testing on a more frequent basis is not feasible for several reasons. Instruments serviced by these valves frequently have interlock or actuation functions that would be interfered with should testing be performed during plant operation. Also, process liquid will be contaminated to some degree, requiring Rev. 5 2D-1 05/93
/P k
~1
ISI-T-200.0 special measures to collect flow from the vented instrument side. Functional testing with verification that flow is checked will be performed at least once per 18 months per Technical Specification 4.6.3 via SI-299-220 through 234. A listing of excess flow check valves can be found in Technical Specification Table 3.6.3-1. Relief Request 33 pertains to excess flow check valve testing.
Check valves whose safety function is to open will be full-stroke tested. Since disc position is always observable, verification of the safety analysis design flowrate through the valve is
'ot considered an adequate demonstration of the full-stroke requirement. This convention is in agreement with NRC Generic Letter 89-04, Position 1.
Limit stroke times for power operated valves are provided and controlled in a general plant procedure in accordance with the NRC guidance provided by "Minutes of the Public Meetings on Generic Letter 89-04" (NRC Response to Question 38).
Where devices monitoring appropriate parameters exist, permanently installed instrumentation will be used during pump performance testing. Both permanent plant instrumentation and measuring and test equipment will be maintained by the Instrumentation and Controls Section in accordance with their administrative procedures.
For those requirements of the Code which are impractical to test, Relief Requests have been included in this program. These Relief Requests provide the impractical test requirement, basis for relief and the proposed alternative testing. Also included as Relief Request are our Cold Shutdown Test Justifications and are so indicated.
Rev. 5 2D-2 05/93
ISI-T-200.0 LE F R VALVETABL Valve Number: Unique system designated valve identification HV - hand switch-operated valve SV - solenoid-operated valve PSV - pressure safety/relief valve XV- excess flow check valve FV - flow control valve PSE - rupture disks 5SME Class: ASME.Code Classes 1, 2, and 3 S - non-code valve which performs a safety-related function P&ID Coordinates: Location of valve on P&ID drawing Section XI Valve Category: A - valves with specified maximum leakage rate B- valves with no specified maximum leakage rate C - self-actuating (check, relief valves)
D- actuated by energy source capable of only one operation (rupture disks, explosive valves)
Active: Valves required to change position to accomplish specified safety function Passive: Valves not required to change position to accomplish specified safety function Size: Nominal valve size in inches Valve Type: C - Check valve B - Butterfly valve G - Gate valve GL - Globe valve RV - Pressure relief valve XFC - Excess Flow Check valve RD - Rupture Disk BA - Ball valve X - Shear (explosive valve)
SC - Stop Check valve Rev. 4 2LV-1 12/91
ISI-T-200.0 Actuator Type: M - Motor A- Air S - Solenoid H- Hand (manual)
- None (self-actuated)
E/H - Electro-hydraulic Remote Position Indicator: X - valve is equipped with an RPI (RPI) - - valve is not equipped with an RPI Normal Position: C- closed 0 - open Test Requirements: Q - quarterly exercise test MT - stroke time measurement concurrent with quarterly exercise test LT.- leakage rate test once per 24 months CV - quarterly check valve exercise test SRV - safety/relief valve liftsetpoint test in accordance with ASME PTC 25.3-1976, Section 4.09 (testing schedule per Table IWV-3510-1)
DT category D test requirement Relief Request: Yes/No and number(s) of applicable relief request(s)
Testing Alternative: CS - Testing shall commence no later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after the plant enters Cold Shutdown (Operational Condition 4) from Power Operation. Valves in this category are subject to testing if they have not been tested in the previous 92 days. Testing shall continue until all subject valves are tested or the plant begins startup. Testing at subsequent cold shutdowns willcommence with those valves having the longest interval (if greater than 92 days) since previous tests. This definition applies to all relief requests with cold shutdown alternative testing. Relief Request 68 pertains to the definition of this code.
RR - every 18 or 24 months as specified in relief request See relief request - specific guidance in individual relief request Remarks: Notes on any special methods of testing. If identified as a pressure isolation valve, additional leak rate testing will be performed (water as test medium) at 1000 +10 psig with an acceptance criterion of 1 gpm. Valve testing configurations will be similar to that utilized for containment local leak rate testing.
Rev. 5 2LV-2 05/93
ISI-T-200.0 RP T BL Pump Number: Unique designated pump identification number Pump Name: Commonly recognized pump name ASME Class: ASME Code Classes 1, 2, and 3 S - non-code pump which performs a'safety-related function Parameters Measured: Required test measurements in accordance with Section XI, Subsection IWP X - Parameter will be required to be measured Specific code exemptions listed Test Frequency: Scheduled test implementation frequency Relief Request Number: Reference to individual relief requests from code requirements Remarks: Notes on methods of testing.
Rev. 4 2LP-1 12/91
ISI-T-200.0 Rev. 4 2VT-1 12/91
SERVICE WATER M-2109 Sheet 2 O O 6
O 8 B~
0 5
'ZJ 0
'6 0 Xg l4 S4 0 S F Rclicf Valve 0 g o 5 Request Testing
)
e Number g V) X O Rcq*'d Altcmativc Remarks A B C D HV-20943A2 3 C-8 X B 0 Q,MT No HV-20943B2 3 E-8 X B 0 Q,MT No
SERVICE WATER M-2110 O O O 0 00 C4 Rclicf Valve S 8S O Rcqucst TcstIng Q 5 Number g~ Rcq'd Alternative A B C D HV-21024A1 3 B-5 X X 10 B C Q,MT No HV-21024A2 3 A-5 X 10 B X C QMT No HV-21024B1 3 C-5 X 10 B X C Q,MT No HV-21024B2 3 C-5 X 10 B X C QMT
EMERGENCY SERVICE WATER M-2111 SIleet I o
8$ Rclicf Valve O g Request Testulg Number R~'d Alternative Rcmarke A B C D HV-21143A 3 B-2 X B A X Q,MT No HV-21143B 3 h4 X B A X Q,MT No H V-21144A 3 GC X X B M X Q,MT Ycs 59 HV-21144B 3 E-7 B M X Q,MT Ycs 59 2-11-132 3 F4 X X CV 59 Open test 64 only 2-11-133 3 G-4 X X CV 59 RR Open test 64 only 2-11-134 3 E-7 X X CV 59 Open test 64 only 2-11-135 3 E-7 X CV 59 RR Open test 64 only 2-11-165A 3 FP X 0 CV 24 Sec Rclicf Closure test Request only
0 EMERGENCY SERVICE WATER M-2111 Sheet I (Continued)
C O
8 P C4 Valve 89s.g O
~5 Rclicf .
Tcsttng Request Number E ~ Rcq'd Altcrnatwc Rcm arly A B C D 2-1 I-165B 3 D4 X 0 CV Ycs 24 Scc Rclicf Closure test Rcqu est only Ch I&
Ct C)
C)
RHR SERVICE WATER M-2112
'::C':?
'O?:?; M
):?8&"
Cc,:@4':
?'.::,:.
'? ' W?: ~?
N x?.c ::Q
', ?~~~.',
'.,p ':c.?x k',;~+)
'."y,', 'C
- Relief/-,",,
-.',"'=;"':$Valv'e:,i;:.;" "::::; .'";Requ'est':: ..':":; Te'stin j;:;":.'> : 4?7
- .';;";-'
- -::.;:::'Nu'mbe't'"";i'"',-';:-'; t/I:.; g iR'e'q'd:"i:":"? !':Alt'e'mative'.,', :::;".:.Rem'arks':,'::
- ,,
- gp:,", ,. g? .,';;:;% g(:%:.; ',:.
? C/
'"?' g, 2-12401 3 C-2 20 C CV No 2-12403 3 G-2 X 20 C CV No HV-21210A 3 C-5 X 20 B C QMT No HV-21210B 3 G-5 X X 20 B X C'MT No PSV-21212A 3 B7 X X RV C SRV No PS V-21212B 3 F-7 RV C SRV No HV-21215A 3 C-7 X 20 B X C QMT No HV-21215B 3 G-7 X X 20 B X C Q,MT No HV-212F073A 3 A-5 C Q,MT No HV-212F073B 3 E-5 C Q,MT No HV-212F074A S A-5 X X GL =A 0 Q MT Yes 38 See Relief Rapid Request acting vlv.
P A
V
'C 5
r, C
4
RHR SERVICE WATER M-2112 (Continued) m~x;m r,~ ";:.q
. R'elief;,;:.
- ';"'-",:.Valve'i:";-.',".:.'.":: -"Req'ue<<si,:
.';,'-Tes'tin j':;;:;,
';:"::Numbel,.::, ,'Req',d :;; ;:"; A1teiiiative,,';."., ,""-Reiiiarks,:.
<<j""'8:>F')":(
'A'::,::g,"3!i".':,:,',Cj".'~":-:;::"D,'
a:p;K%~,. x HV-212F074B S E-5 X I GL A 0 Q,MT Yes 38 See Relief Rapid Request acting vlv.
HV-212F075A 2 A-5 X 6 G M X C Q,MT No HV-212F075B 2 E-5 6 G M X C Q,MT No M
O g O O
O
J 4
REACTOR BUILDING CLOSED COOLING WATER M-2113 j 8 O
H O
0 8 C4 l4 O 8S Rclicf Vaivc O g~' ducat Testing Number R~'d Altcraativc Rcmarka A B C D HV-21313 2 C-I X 4 G 0 Q,MT, LT HV-21314 2 C-3 X 4 G X 0 Q,MT, CS LT H V-21345 2 C-I 4 G 0 Q,MT, LT HV-21346 2 C-3 4 G Q,MT, LT
CONTAINMENTINSTRUMENT GAS M-2126 Sheet I O. -; 4 0' Rclicf, Q
Valve" Request Testing .
-,"." Number Rej'd,;g - Altcrnatiyc Reins rks 2-26-018 2 AW 0 CV RR Closure test only.
2-26429 2 C-5 0 CV RR Closure test only.
2-26-O72 CV,LT Ycs Closure test only, verify operation during leak test.
2-26474 2 E-8 X CV,LT Ycs Closure test only, verify operation during leak test.
2-26-152 2 C-8 X X CV,LT Ycs Verify operation during leak test.
2-26-154 A-8 X CV,LT Ycs RR Verify operation during leak test.
2-26-164 X CV,LT Ycs RR Closure test only, verify operation during leak test.
PS V-22643 B-6 RV SRV No SV-22643 3 B4 X X GL S Q,MT 38 Scc Relief Rapid acting 58 Rcqu est. valve.
CONTAINMENTINSTRUMENT GAS M-2126 Shcct I (Continued) 4' 4'
~ rl. P v~ Rclicf
. Valve: "" ;S O "'g>r>w
~
Request Testing "5
g'~,:~ R~'d Altcrnatiyc, Number,
':~%~~i'p 8, -
Remarks
'A B',' . 0 SV-22644 2 A4 X GL S 0 Q,MT 38 Scc Rclicf Rapid acting h7 58 Request. valve.
PS V-22648 3 C-5 RV SRV No C)
SV-22648 3 C4 X X GL S X Q,MT 38 Scc Rclicf Rapid acting 58 Rcqu est. valve.
SV-22649 2 C4 X GL S X Q,MT 38 Scc Rclicf Rapid acting 58 Rcqucst. valve.
SV-22651 2 E-7 X X GL S 0 Q,MT, 3 Rapid acting LT 38 valve.
58 SV-22654A 2 A-8 X GL S X 0 Q,MT, 4 Rapid acting LT 38 valve.
58
CONTAINMENTINSTRUMENT GAS M-2126 Shcct I (Continued)
O O
l4 Rclicf Valve 89 O Rcqucst Testing Number it ~g Rcq'd,- Altcrnativc Rema res A B C 9 SV-22654B 2 C-7 X X GL X 0 Q,MT, 4 Rapid acting LT 38 valve.
58 SV-22661 2 F-7 X X GL X 0 Q,MT, 38 Scc Rclicf Rapid acting LT 58 Rcqucst. valve.
SV-22671 2 G-7 X GL Q,MT, 38 Scc Rclicf Rapid acting LT 58 Rcqucst. valve.
IJ tJ n O
( O CO
CONTAINMENTINSTRUMENT GAS M-2126 Shcct 2 O O
'E 8 O 00 ~e 0 'S S De 0$
Rclicf Valve A O Request Testing Number 4 E~
~ l- ~ Rcq'd Alternative Rema rlts cc ~
A B C - D HV-22603 D-9 X GL' X 0 Q,MT, No LT SV-22605 D-9 X GL S 0 Q,MT, 38 Sce Rclicf Rapid acting LT 58 Request. valve.
MSIV LEAKAGE CONTROL SYSTEM M-2139 In 0 O C4 O Rclicf Valve O Request Testing Number 6~
V g
O Rcq'd tcmatiye C
Rema rki P4 e-a F A B C D HV-239F001B 1 D-3 X 2 G X Q,MT,LT Ycs Rcduccd Pressure Leak Test.
HV-239F001F 1 G-3 X 2 G Q,MT,LT Ycs Rcduccd Prcssure Leak Test.
HV-239F001K 1 G-3 X X 2 G X Q,MT,LT Ycs Rcduccd Prcssure Leak Test.
HV-239FOOI P 1 H-3 X 2 G X Q,MT,LT Ycs Reduced Pressure Leak Test.
H V-239F002B E-3 X X 2 G Q,MT CS HV-239F002F 2 G-3 2 G X Q,MT HV-239F002K 2 G-3 2 G X Q,MT HV-239F002P 2 H-3 X 2 G X Q,MT CA IJ CO C)
<<9
MSIV LEAKAGE CONTROL SYSTEM M-2139 (Continued) f O O
'CS
~O 0
O le P Valve 0 8S fff Relief Number c E-O ff O ,
Request Rcq'd
~
k Tcating Alternative Remarks A B C D' V-239F003B 2 E-5 X M X C QMT No H V-239F003F 2 G-3 X G M X C Q,MT No H V-239F003K 2 G-3 G M X C Q,MT No HV-239F003P 2 H3 X G M X C QMT No HV-239F006 2 D-8 X G M X C QMT HV-239F007 2 E-8 X G M X C Q,MT CS HV-239F008 2 D-8 X G M X C QMT H V-239F009 2 D-8 X G M X C Q,MT
NUCLEAR BOILER M-2141 Sheet I C
O 8 ~I O 0 De De
-,8S g
Rclicf Valve. O Rcqu cat Testing Number 6~
c48 Rcq'd Alternative Remarks A B.C-'
PS V-24137A HA X X RV C SRV Sce Rclicf Rcqucst.
PS V-24137B HQ X X RV C SRV Sce Rclicf Rcqucst.
PS V-24137C H-4 X RV C SRV Sce Relief Rcqucst.
PS V-24137D HQ X RV C SRV Sce Relief Rcqucst.
PS V-24137E H-4 X RV C SRV Sce Rclicf Rcqu est.
PS V-24137F X RV C SRV Sce Rclicf Rcqucst.
PS V-24137G H-4 X RV C SRV Ycs Scc Rclicf Request.
PS V-24137H H-4 X X RV C SRV Sce Rclicf r Request.
PS V-24137J H4 X. X RV C SRV Scc Rclicf Rcqucst.
NUCLEAR BOILER M-2141 Sheet 1 (Continued) e O
P O O 0 le 8' Rclicf 0 O O Valve a O Request Testing Number 4 E~
ss Rcq'd Alternative Remarks A B C D PS V-24137K X X RV C SRV Scc Rclicf IJ Rcqu est.
Ch PS V-24137L X RV C SRV Sec Rclicf Rcqucst.
PS V-24137M X RV C SRV Sce Rclicf Rcqucst.
PS V-24137N RV C SRV Scc Rclicf Rcqu est.
PSV-24137P X RV C SRV Scc Rclicf Request.
PS V-24137R X RV C SRV Sce Rclicf Request.
PSV-24137S X RV C S+ Scc Rclicf Rcqu est.
PSV-241F013A 1 C4 X X RV C SRV No I7I I
IJ IJ es 4
NUCLEAR BOILER M-2141 Sheet I (Continued)
O-eR O
C4 $4 O Relief Vt Valve O 0 Request Testing Number E~
V Rcq'd Alternative Rcmarirs A B C, D PS V-241F013B I X X RV C SRV No PSV-24 1 F013C I RV C SRV No PS V-24 1 F013 D I X X RV C SRV No PS V-241F013E I RV C SRV No PSV-241 F013 F I X RV C SRV No PSV-241F013G I X RV A C SRV Q Ycs 10 ADS Valve.
PS V-'241 F013H I RV C SRV No PSV-241F013J I RV A C SRV Q Ycs 10 RR ADS Valve.
PS V-241F013K I X X RV A SRV,Q 10 ADS Valve.
(
PS V-241F013L I CA X RV A C SRVQ Ycs 10 RR ADS Valve.
NUCLEAR BOILER M-2141 Shcct 1 (Continued)
It, Valvc- ' ;'O 'II" l;i nt Relief Request ',.'esting Number , n'"
ctI n
V Rcq'd 'Altctnative Remarks nt' A B C;,, D PSV-241F013M CA X X X RV A SRV,Q Ycs 10 ADS IJ Valve.
00 PS V-241F013N 1 CA RV A SRV,Q Ycs IO RR ADS Valve.
PS V-241F013P 1 C4 X X RV SRV No PS V-241F013R 1 C4 X RV SRV No PSV-241F013S 1 C-4 X X RV SRV No HV-241F016 1 E4 X G M X 0 Q,MT, No LT H V-241F019 E-6 G M X 0 Q,MT, No LT HV-241F020 2 E-7 X GL M X 0 QgT No
NUCLEAR BOILER M-2141 Sheet I (Continued) o oR lg Relief F
Valve O Rcqucst Testing Number 5 E~
"' 8 Rcq'd gtcrnativc Remarks F o o
A B C D HV-241F022A I C-5 X X 26 GL A 0 Q,MT, Scc Rclicf Rcduecd LT Request. prcssure leak test in rcvcf5c direction.
HV-241F022B I C-5 X 26 GL A 0 Q,MT, Yes Scc Rclicf Rcduccd LT Request. PfC55UIC leak test in Icvcrsc direction.
H V-241F022C I C-5 X 26 GL A 0 Q,MT, Scc Relief Rcduccd LT Rcqu cat. prc55ufc leak test in fCVCfsC direction.
NUCLEAR BOILER M-2141 Sheet 1 (Continued)
C/ gA S,
?
(
h r .'Relief:
x Valve '-Rcqucsi
,,, Testing .
Number Rcq'd: 'Altcrnativc
.1 C A B C -;-D.
HV-241F022D 26 GL 0 Q,MT, Scc Rclicf Rcduccd IJ LT Rcqucst. pressure leak test in lJ o reverse direction.
241 F024A A-5 X 1 C CV Closure test only.
241F024B 3 A-5 X 1 C 0 CV Closure test only.
241F024C A-5 X I C 0 CV Closure test only.
241F024D A-5 X I C 0 CV Closure test only.
HV-241F02&A 26 GL A X 0 Q,MT, Scc Rclicf Reduced LT Rcqucst. pressure leak test.
I IJ o IJ CO C)
I O
NUCLEAR BOILER M-2141 Sheet I (Continued) 0 O O ". =;
Valve O
O E~
o O x
~
8.'elief Request
~
.. Testing Number cl Rcq'd Alternative Remarks c4 ~
A- -" B.' C; -.D.
HV-241F028B 1 C-7 X X 26 GL A 0 Q,MT, Sce Rclicf Rcduccd LT Rcqu est. prcssure leak teat.
HV-241F028C 1 C-7 X 26 GL A 0 Q,MT, Scc Rclicf Rcduccd LT Rcqucst. prcssure leak test.
HV-241F028D 1 C-7 X 26 GL A X 0 Q,MT, Sce Rclicf Rcduccd LT Rcqu cat. prcssure leak test.
241F029A 2 A-7 X 0 CV Closure test only.
241 F029B 2 A-7 X 0 CV Ycs Closure test only.
241 F029C 2 A-7 X X 0 dv Closure test only.
241 F029D 2 A-7 0 CV Ycs RR Closure test only.
NUCLEAR BOILER M-2141 Sheet 1 (Continued)
C O O- 6 oN 6
~o 0 g
$ 4 o F Relief Valve O Rcqucst Teatmg Number E~ 8 Rcq'd , Qtoernatiye Remarks
. A 8 C D PS V-241F037A 3 X RV C SRV Scc Rclicf IJ Request.
IJ PSV-241F037B RV C SRV Scc Rclicf IJ 3 Request.
PS V-241 F037C 3 X RV C SRV Ycs Sec Rclicf Rcqu cat.
PS V-241 F037D 3 X X RV C SRV Scc Relief Rcqucst.
PS V-241F037E 3 X RV C SRV Scc Rclicf Rcqucst.
PSV-241F037F 3 X RV C SRV Scc Rclicf Request.
PS V-241 F037G 3 X RV SRV Ycs Scc Relief f
Rcqu cat.
PSV-241F037H 3 X' RV C SRV Ycs Scc Relief Request.
NUCLEAR BOILER M-2141 Shcct 1 (Continued)
C O O
\+
~ O De $ 4 O
oI Rclicf Valve 'o Rcqucst Testing g
Number g~ O Req'd Alternative A B, C 9 PSV-241F037J 3 G4 X X 6 RV SRV Scc Rclicf Rcqucst.
PS V-241 F037K 3 G4 6 RV SRV Scc Rclicf Request.
PS V-241F037L 3 GR 6 RV SRV Scc Rclicf Rcqu est.
PS V-241 F037M 3 G4 X 6 RV SRV Scc Rclicf Rcqucst.
PS V-241F037N 3 G4 X 6 RV SRV Scc Rclicf Rcqucst.
PS V-241F037P G-4 X 6 RV SRV Scc Rclicf Request.
PS V-241 F037R 3 G4 X X 6 RV SRV Scc Rclicf Rcqucst.
PSV-241F037S 3 GP X 6 RV SRV Scc Rclicf Request.
NUCLEAR BOILER M-2141 Sheet 2 O
'aO n
O I nI Relief BS O
IN Valve Rcqucst Testing Number Cll 0 g~
c4 8 Rcq'd Alternative A B -C,D 241%17 2 F-3 X GL H LT No 241%18 2 F-3 X GL H LT No H V-24107B E-3 X 24 0 CV No Open check only.
H V-'24182A C-2 X Q,MT, No LT HV-24182B 2 E-2 X Q,MT, No LT 241 F010A 1 C4 X X X 24 0 CV,LT Sce Rclicf Closure Request. check only.
241F010B 1 E4 X 24 0 CV,LT Scc Relief Rcqu est.
H V-241F032A 2 C-2 X 24 SC M 0 Q,MT, 12 CS Closure test LT only.
HV-241F032B 2 E-2 X 24 SC X 0 Q,CV, 12 CS Closure test MT,LT only.
REACTOR RECIRCULATION M-2143 S!lect I h
.y Y Y(l'
- C ,'
\+ ..
YL (h
Rclicf'- j Y
~-""" Valve h Rcq'nest ,Testing Y
~
"'- ~h Number 'cq'd'- Alternative 'cmarits
. Ch,
'Y, h'0 h hh A ',-B;, ."'C. 9 HV-243 F019 1 B4 X 3/4 GL A X Q,MT, 38 Scc Rclicf Rapid acting LT Rcqucst. valve.
HV-243 F020 1 B4 X X 1 GL A X Q,MT, 38 Sce Rclicf Rapid acting IJ LT Request. valve.
HV-243 F031A I F-8 X 28 G M X 0 QMT 16 CS HV-243F031B I F-8 28 G M X O Q,MT 16 CS HV-243F032A 1 F-8 4 G M X O Q,MT No HV-243F032B I F-8 X X 4 G M X 0 Q,MT No
REACTOR RECIRCULATION M-2143 SIlcct 2 v,i,X, O
O. ~ (,rh'h'R l4 Rciicf Valve.,'.,: trt o '-'olucst
-,",... Testing
-Numbcr-.=,'.'. 8,t O" ? Rcq'd I ; AltcrnatiYc , i-Rcrnarirs
'A . B"..C,.D '".'43F013A X 1 C 0 CV,LT Ycs 15 RR Closure test only.
243F013B 1 C 0 CV,LT Ycs 15 RR Closure test only.
XV-243 F017A 2 F-2 1 XFC X 0 CV,LT Ycs 14 RR Closure test only.
XV-243 F017B 2 H-3 X X I XFC X 0 CV,LT Ycs 14 RR Closure test only.
REACTOR WATER CLEANUP M-2144 Sheet 1
?
Cj
- Lc?C,, C
,Retie'f
',;,',!'I;":iValise';i?'.',":!
'. ?)? ,o;;;Q:;I c;"';;,'I;R'eqiies't",:,
"!;:'Y,"
.'" ;4k I.;i':C!
".R'eq! d""",.'":.
TeStl1lg.":c"',:.'::;':;:...-::;:.;'?A'ltetn'atiye'.:':::,
Rema
'Y'8
- 'Y. ':
..'.Numbe'r',,:-.:':.;":,:','.,'cA';.'-.,'::;::;.:'.:;-;:;B,'",",";:::,'::;."",:,C'.";::;;:;,':$
D ;:;,Y::
- "Y.
HV-244F001 1 C-2 X X 6 G M X 0 Q,MT, No LT HV-244F004 1 C-2 X 6 G M X 0 Q,MT, No LT O
tel g
t L
~ P
CONTROL ROD DRIVE M-2147 Sheet 1
" fh.
",'i;Testmg "i..
",,'-':'Altemative .:,,-,'. -';:.,"Re'tttaiks.".;;,"
':" A':::::: '..B,::;:.":',"..C;.i:; ',':"":9,:;:
XV-247F010A 2 A-4 X GL 0 Q,MT Yes 61 See Relief Request.
XV-247F010B 2 A-5 GL 0 Q,MT Yes 61 See Relief Request.
XV-247F011A 2 F-5 X GL A 0 Q,MT Yes 61 See Relief Request.
XV-247F011B 2 F-6 X GL 0 Q,MT Yes 61 See Relief Request.
~ There are a total of 185 sets of these valves, one for each of the 185 CRD Hydraulic Control Units.
M O
IJI g
~
hl O
O IJI O
C
'I U
t
~ I C,
CONTROL ROD DRIVE M-2147 Sheet 2
)
J A r
3;
'alve, Number S;.-.Q Rclicf Request Rcq'd
'.~;. -.
Testing "',
tItltcrnative Rcntarka, A'
A -
B":;.,';:-'C *.:D',
247114>> 2 AS X 3/4 CV ~ 17 Scc Rclicf Open test Rcqucst. only.
247115* 2 D-8 X C CV 17 Scc Rclicf Closure test Rcqu est. only.
XV-247260 2 DW GL A C e 17 Scc Rclicf Open test Request. only.
XV-24727* 2 AW X X GL A C e 17 Scc Rclicf Open test Rcqu est. only.
2471380 2 D4 X 0 CV 17 Scc Relief Closure test Request. only.
'here are a total of IBS sets of these valves, one for each of the IBS CRD Hydraulic Control Units.
STANDBY LIQUID CONTROL M-2148 Relief Valve 8S O Roqu cat 'esting g
Number Rcq'd
- Alternative Remarks A B C,D 248F004A D-7 X X X DT No Explosive Valve.
248F004B D-7 X DT No Explosive Valve.
HV-248F006 D-8 X SC M X Q,MT, 18 RR Closure test LT,CV with motor operator, open test during reactor vcsscl injection test.
248 F007 E-8 CV,LT 19 RR Closure test during leak test, open test during reactor vessel injection lest.
PSV-248F029A D-5 RV SRV No PS V-248 F029B F-5 X X RV SRV No 248F033A D.6 X CV No
STANDBY LIQUID CONTROL M-2148 (Continued) tg 8'4 O 0 Relief Valve O gO S Request Testing Number cl E~ Rcq'd Alternative Remarks
+(
A B 'C D.
248F033B 2 FW I'A C CV No
REACTOR CORE ISOLATION COOLING M-2149
.:',::;;Relief::.,';:.-:
,:;::Re'q)'ue?st'; ':":.:";.-'"-,.,T)esttn'g:,;:,."-',,",$
,",'!;!,',:,'Nu'mbe'r, "".-':), ; Req;d::;:::.'. :,Alterna)tive'; ",,;.";:: i;; Remarks.,:::;:.".,".'5.'..
?
249420 E-5 X X GL H LT No HV-249F007 1 C-3 X X M X 0 Q,MT, 20 See Relief Leak test in LT Request. reverse direction.
HV-249F008 2 C-3 X X M X 0 Q,MT, No LT HV-249F013 2 E-5 X M X Q,MT, No LT FV-249F019 2 F-3 X GL M X 0 Q,MT, 20 See Relief Leak test in LT 38 Request. reverse direction.
Rapid acting valve.
249F021 F-7 X CV,LT Yes 21 Closure test only.
65 249F028 G-5 X CV,LT Yes 21 Closure test only.
HV-249F031 2 H-2 X G M X Q,MT, Yes 20 See Relief Leak test in, LT Request. reverse direction.
(-,i l
t
REACTOR CORE ISOLATION COOLING M-2149 (Continued)
Rclicf Valve Request Testing Number Req'd Alternative Remarks A B C D 249 F040 2 G-5 X 10 C CV,LT 21 RR Closure test only.
H V-249F059 G-3 10 0 Q,MT, 20 Sce Rclicf Leak test in LT Rcqucst. reverse direction.
HV-249F060 2 G3 X GL 0 Q,MT, No Leak test in LT rcvcrsc direction.
HV-249F062 X 0 Q,MT, No LT 249 F063 2 FA X C CV 22 Open test only.
64 249 F064 2 F4 X C CV RR Open test only.
HV-249F084 2 F-3 0 Q,MT, Ycs Scc Rclicf Leak test in r
LT Rcqu est. reverse direction.
3
REACTOR CORE ISOLATION COOLING M-2149 (Continued) 8 0 h=
vt / is 0
,O' / /I Pe Relief Valve Q g'.'. Rctlu cat Testing
", Number y'-/'~ ',+
II Rctl'd:-'-
Alternative'cc Remarks
/* *
'h B..C';::, D /
IJ HV-249F088 C-3 X X I GL A X Q,MT, 38 Rclicf Leak test in LT. RcIIucst. revcrsc direction.
Rapid acting D
valve.
RESIDUAL HEAT REMOVAL M-2151 Sheet I
- 4"V/4 X " NA;X;(".
,y..', C;$ ;,C, " +;Very'4 C?? ~
"??'?
- . O
- ::,.... ;.Relief;;::; '.",q+(.'~
")i.';:":,Vaiv'el::::":::?~?",',"", v ':;.R'equ'"e'st'-.
"::,:R'e'a'.ll,"=:: ':,':..."¹p'.:','Alte'r'nativ?e':";:;.'.":
- ~'.v.
- %.y.&A, ~::,:;:Rem'a'iks",:.'V-2518$
4:...':::.'i':
.'e<<"
4A 2 F-8 X 24 G M X 0 Q,MT, Yes 20 See Relief Leak test in LT Request. reverse direct ton.
HV-251F004C 2 F-8 G M X 0 Q,MT, Yes 20 See Relief Leak test in LT Request. reverse direction.
HV-251F006A 2 H-8 X 20 G M X Q,MT No HV-251F006C 2 G-7 X 20 G M X C Q,MT No HV-251F007A 2 F-7 X X G M X 0 Q,MT, Yes 20 See Relief Leak test in LT Request. reverse direction.
HV-251F015A I D-7 X 24 G M X Q,MT, Yes 26 CS Pressure LT 67 isolation valve.
HV-251F016A 2 B5 12 GL: M X Q,MT, No LT HV-251F017A 2 D-3 X GL M X 0 Q,MT No HV-251F021A 2 B7 X 12 G M X C Q,MT No M
O O
O
RESIDUAL HEAT REMOVAL M-2151 Sheet 1 (Continued)
;:;:;:;,:Nu'mb'er",',."':,',",'.,.';'Relief ";:Rendu'e?st',".
- Req',d,':;:
',,:::,:" ":Tes'tiri'j'.;:':::i!:.':,"
- ,',:;::Alte'I'attv'e',::,':>. ';;.Re'ma'rks;:,:":;:
":'A':,!:,';:."::-,""B,'.":,;'::'C;'::-:.;.:.';'..:.::.',:.";.;:;::;.
HV-251F022 1 B-8 X X 6 Q,MT, Yes 20 CS Leak test in LT 26 reverse 67 direction.
HV-251F023 I B7 X X 6 G M Q,MT, Yes 26 CS LT 67 HV-251F024A 2 E-7 X 18 GL M X C QMT No HV-251F027A 2 E-7 GL M C Q,MT No HV-251F028A 2 E-5 X X 18 G M Q,MT, No LT 251F031A 2 H-2 20 C CV No 251F031C 2 G-3 X 20 C CV No 251F046A 2 F-2 X C CV Yes 64 See Relief Open test Request. only.
251F046C 2 F-3 X C CV Yes 64 See Relief Open test Request. only.
CD C)
CO
F I
l
RESIDUAL HEAT REMOVAL M-2151 Sheet 1 (Continued)
- c'N WA~ .:M',
'",;:,'R'erie f:;.;:.i
- Request .,.
- ,Req'd" ',:;" '."'Alte'mat tv'e";:-:"; ::';;::Remarks.:':
HV-251F048A G-1 X GL M X 0 Q,MT No HV-251FOSOA D-8 X X 24 C CV LT Yes 26 CS Pressure 67 isolation valve.
251F090A X X 0 CV Yes 24 See Relief Closure test Request. only.
HV-251F122A E-8 X X GL A Q,MT, Yes 26 CS Pressure LT 38 isolation 67 valve.
Rapid acting valve.
RESIDUAL HEAT REMOVAL M-2151 Sbc@t 2 0
n 0 0 Valve 0 0
n iS De O
Rclicf Rcqu est '," Testing
~0 Nurnbcf ~ Rcq'd- . Altcfnativc Remarks CO v n A B C 'D HV-251 F003A 2 F-5 X X 20 G M 0 Q,MT No HV-251FOI I A 2 H4 X H C LT No Disabled HV-251F047A 2 C-8 X 20 X 0 Q,MT No PS V-25 I FOSSA A-5 X RV C LT No SV-251 F079A 2 X GL C Q MT Vcs 38 Scc Rclicf Rapid Rcqucst. acting vavc.
HV-251F103A 2 D3 X X I GL X C LT No Leak test in fCVCfSC direction.
PS V-25106A F-3 X I RV C LT No
~
IJ P7 IJ cO ED 4 O
RESIDUAL HEAT REMOVAL M-2151 Sheet 3
- .;.C'.
.;:g
'C C1 c.a
- Cd 0 .:;':,
- '
- ReItef." ~;
','l'Q:,": ';Request:. ". '.,Testiiij",,:
,"',:::.;';,VaIv'e.".';,".",.':,"..;:,":¹iiiibcer:.':
.'.":, :.4::C.: :;.,Re'q',d;,';;; :":,::"Altcemactiveem'aiks.:.
~':s
, C'.;:,:.';::;;. ',
) .a
%C HV-251F004B 2. F-3,, X M X 0 Q,MT, Yes 20 See Relief Leak test in LT Request. reverse direction.
HV-251F004D 2 F-1 X X 24 G 0 Q,MT, Yes 20 See Relief Leak test in LT Request. reverse direction.
HV-251F006B 2 G-3 X .X 20 G C Q,MT No HV-251F006D 2 H-2 20 G M X C QMT No HV-251F007B 2 F-3 X X 6 G M X 0 Q,MT, Yes 20 See Relief Leak test in LT Request. reverse direction.
HV-251F008 1 E-3 X X 20 G M X Q,MT, Yes 23 CS Pressure LT 67 isolation valve.
HV-251 F009 1 D-1 X X 20 G M X Q,MT, 23 CS Pressure LT 67 isolation valve.
RESIDUAL HEAT REMOVAL M-2151 Sheet 3 (Continued) ch? '
,',R'elie'f;:.":..'::.R'e'qu'e's't i:,::..";":-Te'stinj-;i.":'.
.',:".";.:."":.;."::::;.:.,Valv'e:.'.";",:,:',.'-',.',:;;:;::;:,;;;:.:,;.:::;Nu'mb'er::.".
":,':, :'::::: ':;:R'e'q'd
,:.;..; Alt'e'inative,'.-".,', ,",: Remar'It's',:.;.
HV-251F015B 1 C-3 X X X Q,MT, Yes 26 CS Pressure LT 67 isolation valve.
HV-251 F016B 2 A-5 X 12 GL Q,MT, No LT HV-251F017B 2 C-7 X 24 GL 0 Q,MT No HV-251F021B 2 A-3 12 G C Q,MT No HV-251 F024B 2 F-3 X 18 GL C Q,MT No HV-251F027B 2 E-3 X 6 GL C Q,MT No HV-251F028B 2 C-6 X 18 G X Q,MT, No LT 251F031B G-8 X X 20 C C CV No 251F031D H-8 20 C C CV No
V I
fi l
1
RESIDUAL HEAT REMOVAL M-2151 Sheet 3 (Continued)
V
,:;.;.(::;:;:y,',.
':,' 4;.'.".;.
,Relief:::-'::
,'z@lr",'..';:...'.Valv'e",'-.".'..,:',',',"-".";:
- .'::;:;Rvequ'e'st.;:
- ',;"'Testmg'i,':@
';Req'd';:::.-,";.'",'y'.((:;"'.
".,".:Alternative.;': ".;":'::Reiiia(rks,':,:,"::
251F046B F-7 4 C C CV See Relief Open test Request. only.
251 F046D F-8 X 4 C C CV See Relief Open test Request. only.
HV-251 F048B F-9 24 GL M X 0 Q,MT No HV-251F050B C-2 X X 24 C C CV,LT 26 CS Pressure 67 isolation valve.
251F090B B-6 2 C 0 CV See Relief . Closure test Request. only.
HV-251F122B C-2 1 GL A X Q,MT, 26 Pressure LT 38 isolation 67 valve.
Rapid acting valve.
RESIDUAL HEAT REMOVAL M-2151 Sheet 3 (Continued)
O ol eR
~I 0
Valve c5 Q S =
O 8'elief ", -: Testing n Rcqu est Number 5 Pp D 0 Rcj'd Alternative Remarks A B C D PS V-25 1 F 126 D-2 X X X I RV C LT No tJ C
RESIDUAL HEAT REMOVAL M-2151 Sheet 4 C
O O 0 n O O 00 . c O 0 C4 89
$ 4 Relief Valve Cl' O O O Request Testing Number ,II e V) r O
n g~ Rcq'd Alternative Remarks A B, C, D HV-251F003B F4 20 X 0 Q,MT No HV-251FOI I B 2 H-3 X 4 G H C LT No Disabled HV-~&I F047B C-2 X 20 G M X 0 Q,MT No PS V-251F055B 2 8 RV C LT No SV-251 F079B G-5 X 1 GL C Q,MT Ycs 38 Scc Rapid Rclicl'cqu est. acting valve.
HV-25 F103B 1 2 C-7 I GL X C LT Leak test in fevcfse direction.
PS V-25106B F-7 X I RV C LT No'o PS V-251F097 G-2 X X 4 RV LT, SRV
CORE SPRAY M-2152
- Relief,.:;:;
- . iP:,:":;Valve";.',:;,.;.:. :;:-:Re'q'u'est'-".':
.:::.,;:":.".',;:.":;:Testin'g.'"'-'::;:
Number :::-'..:. Req,'6 ',:;i:'!:., !;-.-'P.:::.;.',:.::,:;:'A'Item>>ativ'e'", :;:::;:-;:Retnarks.:'.:.'4
".::.'"':-:,':.:",'.'::;,':B',".;."::;".,:.i;C;.';".;::.,""..';::D~
HV-252FO01A 2 H-3 16 M 0 Q,MT, Yes 20 See Relief Leak test LT Request. in reverse direction.
HV-252FO01B 2 H-1 X 16 G M 0 Q,MT, Yes 20 See Relief Leak test LT Request. in reverse direction.
252F003A E-5 X 12 CV No 252F003B E-8 X X 12 CV No 252F003C E-6 12 CV No 252F003D E-9 12 CV No HV-252F004A 2 D4 X X 12 G M 0 Q,MT No HV-252F004B 2 B4 X 12 X 0 Q,MT No HV-252FOOSA 1 D-3 12 G M Q,MT, 45 CS Pressure LT 67 isolation valve.
I I
I I
CORE SPRAY M-2152 (Continued)
,j:?p??'., ?:0, r
, Zv v( <<(A
.:;:;:<":",",,;.'VaIv'e'.
.".'-.',"?Yg
.'a?':~"
%;:4MZ;c>W
.C
","Relief:,:;;,;
,'etlUest~g "-'Testlflg""'.
',:,:,'",;."::",i: N<<umb'er" ",: Ri'j!d:";.:::":: ,Alt'em'ative
- -:: Retnaiks'- :'-:
0...:,:,?$ %'C hn&
HV-252FOOSB 1 B-3 X 12 G M X Q,MT, Yes 45 Pressure LT 67 isolation valve.
HV-252F006A 1 D-3 X X 12 C X CV,LT Yes 45 Pressure 67 isolation valve.
HV-252F006B 1 B3 12 C X CV,LT Yes 45 Pressure 67 isolation valve.
PS V-252F012A 2 D-7 X X 1'A RV SRV No PS V-252F012B 2 B-7 1'A RV SRV No HV-122F015A 2 E-3 10 GL M X Q,MT, No Leak test LT in reverse direction.
HV-252F015B 2 E-3 X X 10 GL M X Q,MT, No Leak test LT in reverse direction.
C/0 O
~ g
(
a> C) cO CO
%JI
4 4
'I t P'
CORE SPRAY M-2152 (Continued)
C O 0
,C+i
~q O O nI 4 l4 Rclicf O O Valve O Q Rcqu est Testing 6 ~
Number O Rcq'd Alternative Remarks lC A B C D 252 F029A X 0 CV 24 Sce Rclicf Request.
Ch 252 F029B X X 0 CV 24 Scc Rclicf Rcqu est.
252F030A X 0 CV 24 Sce Rclicf Rcqucst.
252 F030B A-5 X 0 CV 24 Scc Rclicf Rcqucst.
HV-252F031A 2 F-3 X G M X 0 Q,MT, Ycs 20 Scc Rclicf Leak test LT Rcqucst. in rcvcrsc direction.
HV-252F031B 2 F-3 X G M 0 Q,MT, Yes 20 Scc Rclicf Leak test LT Rcqu est. m reverse r direction.
PS V-252 F032A 2 G-4 RV SRV No PSV-252F032B 2 H-6 RV SRV No
0 CORE SPRAY M-2152 (Continued) i Relief.::;:.i
"-': "'Valve"" ::;R'e'ques't,':, .;;";:,;",:,.TestIng:;-:;";';:;.
-""',;:;.;:"::,<'".",,'.::Number";.'.,',.",,"
i;Req:,d;,< ";"Alte'rn'ative';:; ':;:: Remaiks,'-,';".':
".":!A!':':::iB;;;,:,':;:":..C,':::..;:::,:,::.:;::;:D':
252F036A E-5 X X CV Yes See Relief Open test Request. only.
252F036B E-8 X CV Yes See Relief Open test Request. only.
252F036C E-6 CV Yes See Relief Open test Request. only.
252F036D E-9 X CV See Relief Open test Request. only.
HV-252F037A 1 D-3 X GL A X Q,MT, Yes 45 CS Pressure LT 38 isolation 67 valve.
Rapid acting valve.
CORE SPRAY M-2152 (Continued)
?'C,'.
? '?X.~
t@":.
':"C;<';
- ?:.: . .;: ., ",Relief:::,!';:.:
';"-;:,;-",'"::VaIv'e",:i:-,:. g?,"y,',",M
- ReqUest~
- ::..:.:::::.:,:Tisttn'g;:.:;::;-:;:;,
- ~';?':.,;;. 'Req.'d: ",',: ::::::Alte'riia'ttve,". ,'": Rem'a'ik's',,:,:
~"',;:":!8;:.:.?
N.;,YA
,,"A".',',",::.":"':.';8,":::..'ji C 4;.".;.
HV-252F037B 1 C-3 X Q,MT, Yes 45 CS Pressure LT 38 isolation 67 valve.
Rapid acting valve.
O g tel
(
CA
'I 4 P,
I
FUEL POOL COOLING 4, CLEANUP M-2153 Sheet 1 O C O O n
gO ct Rclicf =
Valve Number 8~CI Request Rcq'd k'esting Altcrnativc Remarks A B C,. 9 2-53%7IA 3 B4 X C CV 13 Scc Rclicf Open test 65 Rcqu cat. only.
2-53471 B 3 B-5 X X C CV Ycs 13 Scc Rclicf Open test IJ 65 Rcqu est. only.
L C/l CJ CJ n CO CO CO
HIGH PRESSURE COOLANT INJECTION M-2155 j',-' s el
~
0 O
~I O 0 C4 C4 O Relic f Valve 0 - Request '; Testing, ~
Number Rcq'd Altcrnativc , Remarks X
A .B.,,. C D 2-55%12 2 E-5 X 2 C 0 CV 24 Sce Rclicf Request.
2-55%38 2 E-5 I GL H LT No H V-255F001 2 D-8 X 10 G Q,MT No Vl 20 Scc Rclicf Leak test in Cl H V-255F002 B-3 10 G M .Q,MT, LT Rcqu est. reverse direction.
HV-255F003 B-3 10 G X 0 Q,MT, No LT H V-255F004 B-8 X X 16 G 0 Q,MT No 255 F005 2 EW X 14 C CV No Open test only.
HV-255F006 2 E-5 14 G X Q,MT Ycs 29 H V-255F007 2 E-6 14 G X 0 Q,MT No H V-255F008 2 D5 X X 10 GL X Q,MT No
HIGH PRESSURE COOLANT I%ECTION M-2155 (Continued) j
'E O
n 0
I O
O O
6 E
O Ic O O" o S cd Relief Valve Q o 6 cd O Rcqu est Testing Number O ctl Rcq'd Alternative Remarks Ch 0 K A B C D HV-255F012 F-3 X G M X Q,MT, Ycs 20 Scc Relief Leak test in LT Rcqu est. fcvcrsc direction.
Verify stroke during pump test.
255 F019 C-8 X 16 CV 32 RR Closure test only.
HV-255F042 H2 X 16 G M X Q,MT, 20 Scc Rclicf Leak test in LT Rcqucst. fcvcfsc direction.
255 F045 2 H-3 16 CV 31 Scc Rclicf Open test 65 Request. only.
255 F046 E-7 X X X CVgLT Ycs 28 Sce Rclicf Open test 65 Rcqucst. only.
HIGH PRESSURE COOLANT IN/ECTION M-2155 (Continued)
Sw h"
'S g'. ".. s
.0 Rclicf Valve A Request Testing Number 4 Req'd Alternative A B,.: C ,'D 255 F049 2 G-5 20 C CV,LT 2S Sec Relief Open test Rcqu est. only during pump test.
H V-255F066 G-3 X 20 G 0 Q,MT, 20 Scc Rclicf Leak test in LT Rcqucst. reverse direction.
HV-255F075 2 F-5 3 G 0 Q,MT, No LT 255F076 2 F4 X 3 C CV 34 Open test 64 only.
255 F077 2 F4 X X 3 C CV 34 RR Open test 64 only.
HV-255F079 F-3 X 3 G 0 20 Scc Rclicf Leak test in Rcqu est. reverse direction.
C/)
S+
IJ 8
4 C)
HIGH PRESSURE COOLANT INJECTION M-2I55 (Continued) eR g
Relief Valve Request Tcatutg Number II Rcq'd - Alternative. Remarks X
A B C 9 HV-255F100 B-3 X X I GL A X Q,MT, 38 Scc Rclicf Rapid CO LT Rcclucst. acting valve.
IA CA CJ CD CD CD
HPCI TURBINE - PUMP M-2156 Sheet 1 O
8
~o O O 8' Rclicf Valve o II Request Testing E~
o Rcq'd. Alternative Remarks Number A 8 C.'D FV-25612 B-7 X 10 GL E/ X C Q,MT 53 Sce Rclicf Test during H Rcqu est. HPCI pump test.
X C CV 65 Scc Rclicf Test during 256F04S Rcqu est. HPCI pump test, open test only.
G-5 C CV No Test during 256 F052 HPCI pump test, close test only.
G-5 C CV 65 Scc Rclicf Test during 256 F057 Rcqucst. HPCI pump test, open test only.
GL M X C QMT No Test during H V-256F059 E-3 X HPCI pump test.
B-5 X 16 RD C DT No No testing PSE-256D003 required.
V)
IJ CO CO
HPCI TURBINE - PUMP M-2156 Sheet 1 (Continued) 0 O g l4 S 8S Relief
'alve O
- 5. O Request Testing Number g~ II Rcq'd Alternative A 8' D PSE-256D004 S h-5 X X 16 DT No No testing IJ required.
IJI
CONTAINMENTATMOSPHERE CONTROL M-2157 Sheet I S
O J
ReliefRcqucst Yalve A ~i '=-Testing .,
'utnbcr
', : Rcq'd . , "Rcntarka '
n Alternative c
A ...= B ",C.>>,<<" D HV-25703 E-3 X X 18 B X Q,MT, 37 Closure test LT only. Leak test in reverse lJ C direction.
Ch HV-25704 E-2 X 18 B X Q,MT, 37 Closure test LT only.
PS V-25704A I 2 X 24 RV C SRV No PS V-25704A2 2 F-4 X 24 RV C SRV No PSV-25704B I 2 F-4 X 24 RV A X C SRV No PS V-25704B2 2 F4 24 RV C SRV No PSV-25704CI 2 F4 X 24 RV X C SRV No PS V-25704C2 2 F-4 X 24 RV X C SRV No PSV-25704DI 2 F4 X 24 RV C SRV No PS V-25704D2 2 F-4 X 24 RV X C SRV No PS V-25704E I 24 RV X C SRV No M
t> n tJ
( CO C)
CO D
CONTAINMENTATMOSPHERE CONTROL M-2157 Sheet 1 (Continued)
"j 0 Dc Relief 8S O Request Testing Yalyc Number E~ Rcq'd: , Alternative Remarks g C A B 'C . D PS V-25704E2 2 X 24 RV X SRV No HV-25705 D-3 2 GL X Q,MT, 37 CS Closure test LT only.
HV-25711 A-3 2 GL Q,MT, 37 CS Closure test LT only.
HV-25713 24 B X Q,MT, 37 CS Closuretcst LT only. Leak test in reverse direction.
HV-25714 24 B A Q,MT, 37 CS Closure test LT only.
HV-25721 C-8 6 B Q,MT, Closure test LTr only.
CONTAINMENTATMOSPHERE CONTROL M-2157 Sheet I (Continued)
O sl O 8 l4 00 Dv I
O 9 Relief O
Valve 0 O E~g Rcqucst Testing Number Rcq'd Altcfnattve A B C D HV-25722 C-5 X 24 B A X Q,MT, Ycs 37 CS Closure test LT only, Leak test in fcvcfsc direction.
HV-25723 D-7 24 B A X Q,MT, 37 CS Closure test LT only.
HV-25724 18 B A X Q,MT, 37 CS Closure test LT only.
HV-25725 E-5 18 B A X Q,MT, Ycs 37 CS Closure test LT only. Leak test in fcvcfsc direction.
SV-25734A G-2 X X GL S X Q,L'd, Ycs 38, Sce Relief Rapid MT 58 Rcqucst. acting valve.
CONTAINMENTATMOSPHERE CONTROL M-2157 Sheet 1 (Continued)
C"
- " tA
- :g.
- "O .'.
- Relief,';,
- .
.';-.:; Valve"'";;" ','gTe'sttri::-';"",
- Re'q'nest
- ,'
- ,::,Numb e'r:.':,';,.:,:,'-'.', '.:,'Re'q'd'-,-'.:. "';.;:"'Alt'eiiiative',;;:
C',W . ~
"g"," :,"':-:""',Reiiiaiks:;,',":,:'V-25734B 2 E-6 X 1 GL S X Q,LT, 38, See Relief Rapid MT 58 Request. acting valve.
SV-25736A 2 G-3 X 1 GL S X 0 Q,LT, 38, See Relief Rapid MT 58 Request. acting valve.
SV-25736B 2 E-6 X X 1 GL S X Q,LT, 38, See Relief Rapid MT 58 Request. acting valve.
SV-25737 2 G-6 X 1 GL S X Q,LT, Yes 38, See Relief Rapid MT 58 Request. acting valve.
SV-25738 2 G-6 X X 1 GL S X Q,LT, Yes 38, See Relief Rapid MT 58 Request. acting valve.
'C
.~
I ~
I.,j I
1
CONTAINMENTATMOSPHERE CONTROL M-2157 Sheet 1 (Continued)
C ,:r:
': 0 &tv'.
,.C% "..:
. '..C
- Relief:,.;:.':
"'-'<'""'"-"Val+e"""':-""
,";Request;":,
.;::;;.; Number"..'.',".;:,; (p g" i';RE!d,".,":;;, ,'A'Iternattv'e-';.'; ,:;,i:,"Re'mari s.",'
@.,XC;8
- ,;., 8;.,
- C;:6;:;
".'.?',.
- .c.gg?a ')C;:.',
'.wi'A""':i;.".c.B+i!:,:";, C~ ..;.'.:Q i';. 4' YMZ.,M%'.
SV-25740A 2 B4 X X GL S X 0 Q,LT, Yes 38, See Relief Rapid MT 58 Request. acting valve.
SV-25740B 2 B5 X GL S Q,LT, Yes 38, See Relief Rapid MT 58 Request. acting valve.
SV-25742A 2 B3 GL S 0 Q,LT, 38, See Relief Rapid MT 58 Request. acting valve.
SV-25742B 2 B-6 X GL S X Q,LT, Yes 38, See Relief Rapid MT 58 Request. acting valve.
SV-25750A 2 C4 X GL S X 0 Q,LT, Yes 38, See Relief Rapid MT 58 Request. acting valve.
"~v r
~,
Ci
CONTAINMENTATMOSPHERE CONTROL M-2157 Sheet 1 (Continued) 9? ?X 'y:NANT(..:+:? %';
':?y'.',,".,.y"
%?.".c",.'
?:? .;" ?
.C
':.'??:C yM
',',",h Cl,.'.
- ?
- C%
?gg %:.
'.Cl:..? .: ",% lgP,'.;.'t .!ReIief:.;"."':,.,",'.;:Re'qu'e'st'::;
"'-ll":-'? '",;i;::.:Testing':.",:i~i','
<; fy?
".'Req!d ".~".g Alternativ'e,';:,: ;'.';:::'",.':,Rem'arks.;;::.';;
r? .,;:
.".'A"'i::.'::"'::";:B';'.~":;;':::Ci:::,::,:i.:':.-::,,'D.';.
SV-25750B 2 B-5 X GL S X Q,LT, Yes 38, See Relief Rapid MT 58 Request. acting valve.
SV-25752A 2 C-3 X X GL S X 0 Q,LT, Yes 38, See Relief Rapid MT 58 Request. acting valve.
SV-25752B 2 B-6 X GL S Q,LT, 38, See Relief Rapid MT 58 Request. acting valve.
HV-25766 2 H-5 G M Q,MT, Yes 20 See Relief Leak test in LT Request. reverse direction.
SV-25767 2 C-5 X GL S Q,LT, 38, See Relief Rapid MT 58 Request. acting valve.
HV-25768 2 H-4 X G M X Q,MT, No LT
~r.
CONTAINMENTATMOSPHERE CONTROL M-2157 Sheet 1 (Continued)
"Relief'.",-".
",-.',;;;;,':.'";:;:,Valve,:-',;;.""".'.,';".".', "-':',:Te'sjin'gv'::-
- ',Reqwu'est'.'Reqw'vd:::.':-
-,,';:;,:;::Number'"-";;; ':'Avl'teinative ;.'::::Rema'iks..:::.::::,
'.WV W ', '<<v.:.'W.'.'.r '
SV-25774A C-3 X 1 GL S X 0 Q,LT, 38, See Relief Rapid MT 58 Request. acting valve.
SV-25774B D-6 X 1 GL S X Q,LT, 38, See Relief Rapid MT 58 Request. acting valve.
SV-25776A C4 X X 1 GL S X, 0 Q,LT, 38, See Relief Rapid MT 58 Request. acting valve.
SV-25776B D-5 X X 1 GL S X Q,LT, Yes 38, See Relief Rapid MT 58 Request. acting valve.
SV-25780A F-3 X 1 GL S X 0 Q,LT, Yes 38, See Relief Rapid MT 58 Request. acting valve.
CONTAINMENTATMOSPHERE CONTROL M-2157 Sheet 1 (Continued)
- ! Relief ~'
Request".:Reij'd-""';",
i-'::::.-".:Remarks:.:'::;:,"
SV-25780B 2 F-6 X GL S X Q,LT, Yes 38, See Relief Rapid MT 58 Request. acting valve.
SV-25782A 2 F-2 X X GL S X 0 Q,LT, Yes 38, See Relief Rapid MT 58 Request. acting valve.
SV-25782B F-6 X GL S Q,LT, Yes 38, See Relief Rapid MT 58 Request. acting valve.
SV-25789 2 C4 X GL S Q,LT, Yes 38, See Relief Rapid MT 58 Request. acting valve.
t T~
4
CONTAINMENTATMOSPHERE CONTROL M-2157 Sheet 5
% .O t
p
- ~'? j'
": .'".,'5?
'\ ', 9
".0':::":.'.
0,:...;;;
4'?;;";
car;i.'.. ;:n .,'.,";;:;:
- R'
- . '
- 'Relic'f.,'
- :"-:.;;:
.';,Rej!d:::,:,::;,'C.'::,',':
.;:;;:Request:".,-:. ~~ "'Testmg '-".
I F , ; al:".:,~;.'.; '-';:;:
Aiteriiative',,,': ;::",:"-::::Remaikr;,"","
,".i":-'-'.'. B:-ll:",';;C(i.":,'.:;-'.9
-'X .
SV-257104 E-3 1 GL S Q,LT, Yes 38, See Relief Rapid MT 58 Request. acting valve.
SV-257105 E-3 1 GL S X Q,MT, Yes 38, See Relief Rapid LT 58 Request. acting valve.
SV-257106 F-3 X 1 GL S X Q,LT, 38, See Relief Rapid MT 58 Request. acting valve.
SV-257107 X 1 GL S X Q,LT, Yes 38, See Relief Rapid MT 58 Request. acting valve.
4 ~
I
CONTAINMENTATMOSPHERE CONTROL M-2157 Sheet 6
- .C .,
",.: g:,
Relief@~
'"",:Valv'e".,".'",'l ;"::.:R'equest"; ;:;;:::'gestUlg;:;.,';
" '=:';,; ¹'mh'ei.'..;::;::;; 'Req!d',~N ":"Alternative',".':, :;.-.': '; Rem'aiks:-,'",
~p+vg'.
SV-257100A 2 B-3 X 1 GL X 0 Q,LT, 38, See Relief Rapid MT 58 Request. acting valve.
SV-257101A 2 B-3 X X 1 GL X 0 Q,LT, 38, See Relief Rapid MT 58 Request. acting valve.
SV-257102A 2 C-3 X 1 GL X 0 Q,LT, 38, Relief Rapid MT 58 Request. acting valve.
SV-257103A 2 C-3 X 1 GL X 0 Q,LT, Yes 38, See Relief Rapid MT 58 Request. acting valve.
0 N
8 ge l"
CONTAINMENTATMOSPHERE CONTROL M-2157 Sheet 7 C'>':.,":.;.
. )/%'::
V( ',: ';,
V hV CJ
- 0:".
,""'",".""':":"',Valve",:.;,,'.' ~"'
I
, ':: )): ',.a """."Testtng ":
'.ReqUest-R'e'q':d,:;:;:
g/ 'Q ". X ':Aitemativ'e'. :- Rema'iks'",.'-'.
,'::rP,'. x
- 'A";::,'-::i::.;:B;:;:;".,:.C;:::..;.::::, ':,:::,::,",9.';:; NM <"
SV-257100B B-3 X X 1 GL S X 0 Q,LT, 38, See Relief Rapid MT 58 Request. acting valve.
SV-257101B B-3 1 GL S X 0 Q,LT, 38, See Relief Rapid MT 58 Request. acting valve.
SV-257102B C-3 1 GL S X 0 Q,LT, Yes 38, See Relief Rapid MT 58 Request. acting L valve.
SV-257103B C-3 X X 1 GL S X 0 Q,LT, 38, See Relief Rapid MT 58 Request. acting valve.
g~ t 1 h 1'
~ I
LIQUID RADWASTE COLLECTION M-2161 Sheet I Relief::i'.:.'":,'e'qiies't:i Rej',d,'-':.
HV-26108A1 2 B-3 X X G A X Q,MT, No LT HV-26108A2 2 B-5 X X G A X Q,MT, No LT HV-26116A1 2 G-3 X G A X Q,MT, No LT HV-26116A2 2 H-3 X X G A Q,MT, No LT
REACTOR BUILDINGCHILLED WATER M-2187 Sheet 2
':;:::;:Relte'f,;:,:"':,::
V':,".-.:::,:;Vali):":,';,::-"'.
i",:Retlues't':;Req',d',".;:.
.:.:;.;Testmg;,'.": .;;;:;;: r.r..'....
- ,
- ,'
- ;;,.;.Numb'e'x,:.":':,',', "..Arltrexiia'tKe';::: "":,:.-',Rem'axks",:;
. x ZCC xcP;;:;: Y:.
'::'A'.:"::::,'::::.::::.B:::::::=':-::::.:C:::: "'4:D!::,:-'!."
HV-28781AI 2 H-2 X G A X 0 Q,MT, No LT HV-28781A2 2 G-2 X G A X 0 Q,MT, No LT HV-28781B I 2 D-2 X G A X 0 Q,MT, No LT HV-28781B2 2 C-2 X G A X 0 Q,MT, No LT HV-28782A1 2 D-2 X X B A X 0 Q,MT, No LT HV-28782A2 2 C-2 B A X 0 Q,MT, No LT HV-28782B I 2 H-2 X X B A X 0 Q,MT, No LT HV-28782B2 2 G-2 X B A X 0 Q,MT, No LT HV-28791AI 2 B-2 X X G A X 0 Q,MT, Yes 39 CS LT O g
'I 1
I~
'C
REACTOR BUILDINGCHILLED WATER M-2187 Sheet 2 (Continued)
\'
M C.:.
4
- CC.': "
,. 41'.w
'," g'.; C7, '-;R'elief,:.,'::::,;.
- -'ll:::::,:",::VaI'v'e,'.'.'-'.;-"'..',":.',';."::
';::Nuinbet".:.:.:,'.",':
- 'g::40',:5
- ,'8 %ca
?ai",
': ~;N~j N
g;. Og.,:;: ;::. Request:.
'::Req"d:;::,":;,'
.;~<:~Testing':,:;:)~
- -',A'Itetn'atiy'e,
- ". ;:,";';Re'iiiaiks.'".':.'
'j: A':.;i',::.::i, Bi,:::.:'":.';C:."'-':,'"';:::".'I)
HV-28791A2 2 A-2 X X 3 G A X 0 Q,MT, Yes 39 CS LT 0
Ch HV-28791B I 2 F-2 X 3 G A X 0 Q,MT, Yes 39 CS LT HV-28791B2 2 E-2 X 3 G 0 Q,MT, Yes 39 CS LT HV-28792AI 2 F-2 X X 3 B A X 0 Q,MT, Yes 39 CS LT HV-28792A2 2 E-2 X 3 B A X 0 Q,MT, Yes 39 CS LT HV-28792BI 2 B-2 X 3 B A X 0 Q,MT, Yes 39 CS LT HV-28792B2 2 A-2 X X 3 B A X 0 Q,MT, Yes 39 CS LT
, II I
r I
I
TRAVERSING INCORE PROBE (TIP) (No P&ID) y C.'y
'%.' y?'8?:;:
':R'e'lief,,:,:.',"::
';:.::,:;.:,"','.Valv'e ;
Re'q'uest.;: ."y::j'?
""'i"-"'-:""~'"'¹mber; Testmg:::yy.';i.:"Alternative"';
: ",:: ."."." Reiiiarlts."',.";
';::A".-::,:':,.:::-::,: B::.::::::,'.'.":..':..,C..'::."":.'"D;.:'.;
(?'%?y?
TIP Chan A S N/A X 3/8 BA S X Q,MT, 38 See Relief Rapid Man Valve* LT Request. acting vlv.
TIP Chan A S N/A X X 3/8 X 0 DT No Squib Valve**
TIP Chan B S N/A X 3/8 BA S X Q,MT, 38 See Relief Rapid Man Valve LT Request. acting vlv.
TIP Chan B S N/A X 3/8 X 0 DT No Squib Valve TIP Chan C S N/A X X 3/8 BA S X Q,MT, Yes 38 See Relief Rapid Man Valve LT Request. acting vlv.
TIP Chan C S N/A 3/8 X 0 DT No Squib Valve TIP Chan D S N/A X X 3/8 BA S X Q,MT, Yes 38 See Relief Rapid Man Valve LT Request. acting vlv.
TIP Chan D S N/A X X 3/8 X 0 DT No Squib Valve TIP Chan E S N/A X X 3/8 BA S X Q,MT, 38 See Relief Rapid Man Valve LT Request. acting vlv.
A TRAVERSING INCORE PROBE (TIP) (No P&ID) (Continued)
,p,'? -;'Relief:,::.
4:ReqU est: ::.i.",:,';:9'e'su'ni::'.:::'."::i:
'-".,i;'"'-::,":",Numb'e'r'.",'.-",';. '::,Req.'d';-;.' ::i,"':Alte'm'a'tiye,:::.
TIP Chan E S N/A X X 3/8 X 0 DT No Squib Valve TIP Channel manual (Ball) isolation valve.
TIP Channel Squib (explosive/shear) isolation valve.
ISI-T-200.0 Rev. 4 2PT-1 12/91
PARAJVIETER MEASURED c'
9..
Pump C Number Pump Name'. I Remarks 2P202A Residual Heat Exempt X X X 52 Bypass loop, bearings in Removal-A IWP- 54 main flow path 4400 55 lubricated by pumped liquid.
2P202B Residual Heat Exempt X X 52 Bypass loop, bearings in Removal-B IWP- 54 main flow path 4400 55 lubricated by pumped liquid.
2P202C Residual Heat Exempt X X X X 4C 52 Bypass loop, bearings in Removal-C IWP- 54 main flow path 4400 55 lubricated by pumped liquid.
2P202D Residual Heat Exempt X X X 52 Bypass loop, bearings in Removal-D IWP- 54 main flow path 4400 55 lubricated by pumped liquid.
2P204 and High Prcssure X X X X X 44 Bypass loop, main and 2P209 Coolant Injection 48 booster pumps opcratc Main &, Booster 52 in tandcm-55 mcasurements taken as 63 onc pump.
IJ C)
C)
PARAMETER MEASURED (Continued)
Pump C4 Number Pump Name
~
p E ~ gm Remarks g
X =
2P206A Core Spray-A Exempt X X X 52 Bypass loop, bearings in lWP- 54 main flow path 4400 55 lubricated by pumped liquid.
2P206B 'Core Spray-B Exempt X X X X 52 Bypass loop, bearings in lWP- 54 main flow path 4400 55 lubricated by pumped liquid.
2P206C Core Spray-C X X X X aa 52 Bypass loop, bearings in Exempt lWP- 54 main flow path 4400 55 lubricated by pumped liquid.
2P206D Core Spray-D Exempt X X X 52 Bypass loop, bearings in IWP- 54 main flow path 4400 55 lubricated by pumped liquid.
2P208A Standby Liquid Exempt See Rclicf 43 Bypass loop.
Control-A IWP- Request 43. 49 4400 52 M
lJ C)
PARAMETER MEASURED (Continued)
Pump :O Number Pump Namc- ll ]I Remarks 2P208B Standby Liquid Exempt Scc Rclicf X X X 43 Bypass loop.
Control-B IWP- Rcqucst 43. 49 4400 52 2PS06A RHR Service Exempt X X X 52 Bearings in main flow
. Water-A (Unit I) IWP- 54 path lubricated by 4400 pumped liquid. Inlet pressure dcrivcd from spray pond lcvcl.
2PS06B RHR Scrvicc Exempt X X 52 Bearings in main flow Water-B (Unit I) IWP- 54 path lubricated by 4400 pumped liquid. Inlet prcssure dcrivcd from spray pond level.
Scc Rclicf Rcqucst 48.
Sce Rclicf Rcqucst 54.
Scc Rclicf Rcqucst 49.
ISI-T-200.0 Rev. 4 2RRT-1 12/91
ISI-T-200.0 RELIEF RE UEST NUMBER 1 COLD SHUTDOWN TEST JUSTIFICATION System: Reactor Building Closed Cooling Water PEcID: M-2113 Valves: HV-21313 HV-21314 HV-21345 HV-21346 Category:
Class:
Function: Containment Isolation Impractical Test Requirement: Exercise valves once per 92 days.
Basis for Relief: These valves are in the coolin g water su pply and return lines for the reactor recirculation pump bearing and seal coolers. Cycling of these valves during power operation would interrupt this cooling water flow, possibly causing pump bearing damage or seal failure.
Alternative Testing: Exercise valves during Cold Shutdowns (no more frequently than once per 92 days).
Rev. 5 2RR1-1 05/93
ISI-T-200.0 RELIEF RE ER 2 System: Containment Instrument Gas P&ID: M-2126 Valves: 2-26-070 2-26-072 2-26-074 2-26-152 2-26-154 2-26-164 Category: A,C Class:
Function: Containment Isolation Impractical Test Requirement: Exercise valves once per 92 days.
'asis for Relief: These check valves serve the containment isolation function inside containment and are not equipped with remote position indicators.
Downstream of the valves (inside containment) there are no pressure measurement devices or other means of remotely verif'ying valve position.
The only practical method of closure testing involves pressurizing the downstream side and measuring pressures with temporary instrumentation.
With the inerted containment, such testing can only be performed during a major outage which requires containment purging. This testing, which requires significant effort in the installation and removal of temporary equipment in the high radiation area of the containment drywell, is already performed during Category A leak rate testing.
Two valves, 2-26-152 and 2-26-154, serve a safety function on opening as well as their containment isolation function. The open test cannot be performed as there would be no positive indication (flow measurements) of function. Operation of the equipment serviced by these valves (ADS function of the safety/relief valves) will not verify their proper opening since the accumulators at the SRV operators provide capacity for several lifts.
Rev. 4 2RR2-1 12/91
ISI-T-200.0 RELIEF RE T ER 2 (Cont'd.)
Performing continued lifts in an attempt to verify check valve opening will increase the potential for SRV leakage or failure to reseat, will impact proper maintenance of reactor pressure control, and has the potential for degradation of the ADS function.
Alternative Testing: Valve closure is. demonstrated by completion of leak rate testing performed once per 24 months. Commencing with the first refueling outage, verification of the opening capability of valves 2-26-152 and 2 154 will also be performed at that time with an air pressure applied through the outboard test valves (2-26-021, 2-26-03 1), opening the inboard test valves (2-26-155, 2-26-153), and observing essentially unrestricted flow. I Rev. 4 2RR2-2 12/91
ISI-T-200.0 RELIEF RE UEST. NUMBER 3 COLD SHUTDOWN TEST JUSTIFICATION System: Containment Instrument Gas M-2126 PEcID'alves:
SV-22651 Category:
Class:
Function: Containment Isolation Impractical Test Requirement: Exercise valve once per 92 days.
Basis for Relief: Closing this valve interrupts instrument gas supply to several important valves inside containment such as the Safety/Relief Valves (non-ADS function) and the MSIVs. This could compromise the ability of the SRV's to operate in the relief mode which, while not an ECCS function, is important to safety. Loss of instrument gas could also cause the MSIVs to close, resulting in a severe reactor transient.
Alternative Testing: Exercise valve during cold shutdowns (no more frequently than once per 92 days).
Rev. 5 2RR3-1 05/93
~ ~
k f
ISI-T-200.0 RELIEF RE VEST NUMBER 4 COLD SHUTDOWN TEST JUSTIFICATION System: Containment Instrument Gas PAID: M-2126 Valves: SV-22654A SV-22654B Category:
Class:
Function: Containment Isolation Impractical Test Requirement: Exercise valves once per 92 days.
Basis for Relief: Closing these valves will interrupt instrument gas supply to the ADS solenoids of the Safety/Relief Valves, compromising their ability to provide the opening motive force for the ADS valves in support of the long-term cooling ECCS function.
Alternative Testing: Exercise valves during cold shutdown (no more frequently than once per 92 days).
Rev. 5 2RR4-1 05/93
ISI-T-200.0 RELIEF RE UEST NUMBER 5 COLD SHUTDOWN TEST JUSTIFICATION System: MSIV-Leakage Control P&ID: M-2139
":': Catego~'iaaf 4'~
"'"'""':i:: :::::"'"'ij""""i(Valves":~'~jk~mimgii~'h"'"'":"""""i"N HV-239F001 B, F, K, P HV-239F002 B, F, K, P Function: Containment Isolation; System Initiation Impractical Test Requirement: Exercise valves once per 92 days.
Basis for Relief: The MSIV-LCS inboard bleed lines are directly connected to the main steam lines at the outboard MSIV. During power operations, these lines are pressurized with main steam up to the first isolation valve (HV-239F001 B,F,K,P). Double valve isolation is provided by HV-239F002 B,F,K,P. Opening any of these valves during power operations will leave only one barrier against the release of main steam to occupied plant areas through the system piping. Maintenance of double valve isolation is desired for personnel safety considerations and for prevention of inadvertent leakage paths from the main steam lines.
Alternative Testing: Exercise during cold shutdowns (no more frequently than once per 92 days).
Rev. 5 2RR5-1 05/93
ISI-T-200.0 RELIEF RE UEST NUMBER 6 COLD SHUTDOWN TEST JUSTIFICATION System: MSIV-Leakage Control P&ID: M-2139 Valves: HV-239F006
/ HV-239F007 HV-239F008 HV-239F009 Category:
Class:
Function: System Initiation Impractical Test Requirement: Exercise valve once per 92 days.
Basis for Relief: The MSIV-LCS outboard bleed and blowdown lines are directly connected to the m'ain steam system at the steam line drain. During power operations these lines are pressurized with main steam up to the first isolation valve (HV-239F006, HV-239F008). Double valve isolation is provided by HV-239F007 and HV-239F009. Opening any of these valves will leave only one barrier against the release of main steam to occupied plant areas through system piping. Maintenance of double valve isolation is desired for personnel safety considerations and for prevention of inadvertent
~
leakage paths from the main steam lines.
Alternative Testing: Exercise during cold shutdowns (no more frequently than once per 92 days).
Rev. 5 2RR6-1 05/93
A' AO P
~ e3 i
ISI-T-200.0 RELTEF RE T R7 System: Nuclear Boiler P &ID: M-2141 Valves: 241F010 A,B Category: A,C Class:
Function: Containment Isolation Impractical Test Requirement: Exercise valves closed once per 92 days.
Basis for Relief: These check valves remain open maintaining the flowpath to the vessel whenever the feedwater/condensate, HPCI or RCIC systems are providing makeup to the vessel or when Reactor Water Cleanup is returning flow to the vessel. Due to the necessity of maintaining this flowpath in virtually all modes of operation, closure testing is only practical during extended outages such as refuelings during which these systems are shutdown.
Also, plant design does not provide a practical means of demonstrating closure other than by upstream pressurization performed during leak rate testing. This testing involves significant effort for installation of temporary equipment, and requires complete purging of the inerted reactor containment.
Alternative Testing: Proper valve closure willbe verified in by completion of leak rate testing performed once per 24 months.
Rev. 4 2RR7-1 12/91
ISI-T-200.0 R
System: Nuclear Boiler P&ID: M-2141 Valves: PSV-24137 A,B,C,D,E,F,G,H,J,K,L,M,N,P,R,S PSV-241F037 A,B,C,D,E,F,G,H,J,K,L,M,N,P,R,S Category:
Class:
Function: SRV Discharge Pipe Vacuum Breaker Impractical Test Requirement: Setpoint test per PTC 25.3-1976.
Basis for Relief: The ASME performance test code does not provide the most practical method for testing these vacuum relief devices.
Alternative Testing: Commencing with the first refueling outage, the setpoint will be checked once per refueling outage by pouring water into the valve inlet and measuring the height of water column necessary to activate the valve.
Rev. 4 2RR8-1 12/91
ISI-T-200.0 R LIE System'. General P&ID: General Valves: General Category: General Class: General Function: As applicable to specific valves.
Impractical Test Requirement: Paragraphs IWV-3417(b) and IWV-3523 of Section XI require that when corrective action is required as a result of tests made during cold shutdown, the condition shall be corrected before startup.
Basis for Relief: For those valves specified therein, the Limiting Conditions for Operation presently contained within the Susquehanna Steam Electric Station Technical Specifications provide the control by which valves and/or systems are declared inoperable. They also control entry into the various operational conditions. Further controls are not necessary for "these valves. Valves which are not under the control of the Technical Specifications will be declared inoperable should they fail ISI testing.
Alternative Testing: The requirements contained within Susquehanna SES Technical Specifications will control plant operations and testing with regard to out-of-service valves. For valves which are not addressed in the Technical Specifications, any failures will cause the affected valve(s) to be declared inoperable and corrective action to be initiated as appropriate.
Rev. 4 2RR9-1 12/91
ISI-T-200.0 RELIEF RE VEST NUMBER 10 System: Nuclear Boiler I
P&ID: M-2141 Valves: PSV-241F013 G,J,K,L,M,N Category: B,C Class:
Function: ADS Valve, Code Safety/Relief Valve Impractical Test Requirement: Exercise valve once per 92 days.
Basis for Relief: The six safety relief valves assigned to the ADS system perform an essential safety function when operated by the pneumatic actuator with gas supplied through the ADS solenoid valves. Operation of these valves is not practical during power operation because this action will vent main steam to the suppression pool, inducing a transient condition and increasing the potentiality for an open failure of a safety relief valve.
Also, no stroke timing is practical as these are pneumatic assisted SRVs.
No direct position indication of the SRVs is provided. Although acoustic monitors attached to the valve discharge piping provide evidence of steam flow through each valve, which can be taken as indirect or secondary indication of valve position, no accurate stroke timing is possible. ADS valve stroke times could only be inferred very crudely from elapsed time between manual (non-ADS) actuation of each valve and acoustic monitor indication of steam flow or lack of steam flow in the valve discharge pipe line. Exercising during cold shutdown cannot be accomplished because of lack of steam flow (and attendant noise) provides no indirect or secondary indication of valve movement.
Alternative Testing: The ADS valves will be exercised once per 18 months in accordance with Technical Specification 4.5.1.d.2.b, which provides manual opening of each ADS valve with reactor dome pressure greater than or equal to 100 psig and observing either control valve or bypass valve response or corresponding change in measured steam flow. No stroke timing can be done.
Rev. 5 2RR10-1 05/93
ISI-T-200.0 Additionally, to monitor for possible degradation of each ADS SRV, actuator lift time and actuator lift distance will be measured during each safety valve/relief valve pressure set point test, done to satisfy paragraph IWV-3510 requirements.
Rev. 5 2RR10-2 05/93
1 <
ISI-T-200.0 RELIEF RE UEST NUMBER 11 System: Nuclear Boiler PAID: M-2141 Valves: HV-241F022 A,B,C,D HV-241F028 A,B,C,D Category:
Class:
Function: Containment Isolation Impractical Test Requirement: Exercise valves once per 92 days.
Basis for Relief: During full power operation, it is impractical to full stroke cycle these valves, since the interruption in steam flow would induce a reactor pressure transient with increased probability of reactor scram, main steam line isolation and SRV actuation. Trending of valve stroke times is not necessary due to Technical Specification limits on minimum as well as maximum allowable stroke times with a tolerance of only 2 seconds between the 3 second minimum and the 5 second maximum.
Alternative Testing: Full stroke testing will be performed in Operational Condition 1, 2, or 3 when power level is low enough to prevent the above mentioned transients (no more frequently than once per 92 days). No reduction from high power levels will be made specifically to accomplish this testing. No trending of valve stroke times will be done.
Rev. 5 2RR11-1 05/93
ISI-T-200.0 KR 12 System: Nuclear Boiler P&ID: M-2141 Valves: HV-241F032 A,B Category: A, C (HV-241F032B only)
Class:
Function: Containment isolation; HPCI flowpath (HV-241F032B only).
Impractical Test Requirement: Exercise valve once per 92 days.
Basis for Relief: a. These check valves remain open maintaining the fiowpath to the vessel whenever the feedwater/ condensate systems are providing makeup to the vessel. Interruption of the feedwater fiowpath by motor operator closure of these valves can only be practically accomplished during cold shutdowns.
- b. No practical means other than upstream pressurization similar to leak rate testing is available to demonstrate valve closure of HV-141F0328 as a check valve.
Alternative Testing: a. Cycle valves shut using stop-check motor operators during cold shutdowns (no more frequent than once per 92 days).
- b. Closure testing of HV-241F032B as a check valve willbe demonstrated by completion of leak rate testing to be performed once per 24 months.
Rev. 4 2RR12-1 12/91
ISI-T-200.0 RELIEF RE UEST NUMBER 13 System: Fuel Pool Cooling and Clean-Up PEcID: M-2153 Valves: 2-53-071 A,B Category:
Class:
Function: Admit flow to fuel storage pool.
Impractical Test Requirement: Exercise valves once per 92 days.
Basis for Relief: In an alternative flowpath to the fuel storage pool, exercising of these valves utilizing flow can only be accomplished utilizing ESW or RHR water. Use of ESW would introduce "raw" water from the ESSW spray pond, undesirable for chemistry and fuel integrity considerations. While use of the RHR flowpath is possible, the difficulty of operating the RHR system in an abnormal lineup for supplying the fuel pool creates a dynamic control situation that is best minimized.
Alternative Testing: Verify valve operability by a pneumatic open flow path test during periodic pressure test. A pneumatic open flow path test (SE-235-301) is performed once per Inspection Period (as specified by ASME Code Section XI paragraph IWD-2400).
Rev. 5 2RR13-1 05/93
ISI-T-200.0 KR 14 System: Reactor Recirculation P&ID: M-2143 Valves: XV-243F017 A,B Category: A,C Class:
Function: Containment Isolation Impractical Test Requirement: Exercise valves once per 92 days.
Basis for Relief: Closure testing of these excess flow check valves involves depressurization of the CRD system side of the valves and verification that the valve will close and stop excess flow. Such actions require interruption of seal water to the recirculation pumps, which creates a potential for pump seal damage; disruption of CRD Hydraulic System flow; and installation of temporary equipment.
Alternative Testing: Closure testing will be demonstrated by completion of leak rate testing to be performed once per 24 months.
Rev. 4 2RR14-1 12/91
ISI-T-200.0 RELIEF E ER 1 System: Reactor Recirculation P&ID: M-2143 Valves: 243F013 A,B Category: A,C Class:
Function: Containment Isolation Impractical Test Requirement: Exercise valves once per 92 days.
Basis for Relief: These simple check valves serve as containment isolation valves inside containment. The valves are not equipped with remote indication and there is no pressure indication downstream of the valves. For these valves, closure testing is only practical through pressurization downstream of the valve with the upstream piping vented, and verification of the absence of flow upstream. Interruption, of the CRD flow (seal purge) during Reactor Recirculation Pump operation to perform this testing could result in seal damage. This type of testing can only be performed during a period when the containment is accessible. The deinerting of the containment will only be performed during major outages and the testing will be performed during Category A leak rate testing.
Alternative Testing: Valve closure is demonstrated by completion of leak rate testing performed once per 24 months.
Rev. 4 2RR15-1 12/91
ISI-T-200.0 RELIEF RE VEST NUMBER 16 COLD SHUTDOWN TEST JUSTIFICATION System: Reactor Recirculation PAID: M-2143 Valves: HV-243F031 A,B Category:
Class:
Function: Reactor Recirculation Pump Discharge Isolation, LPCI flowpath.
Impractical Test Requirement: Exercise valves once per 92 days.
Basis for Relief: The recirculation pump discharge isolation valves are in the main flowpath of the reactor recirculation system which is necessary to maintain reactivity control of the reactor. Cycling of these valves during power operations would interrupt the driving core flow, possibly resulting in severe changes in core power level.
Alternative Testing: Technical Specification 4.4.1.1.1 provides for and controls the exercising of these valves prior to exceeding 25% power during each startup.
Rev. 5 2RR16-1 05/93
ISI-T-200.0 RELIEF KR 17 System: Control Rod Drive P&ID: M-2147
~V~lv gate~ry 247114-001 through 247114-185 C 247115-001 through 247115-185 C XV-247126-001 through XV-247126-185 B XV-247127-001 through XV-247127-185 B 247138-001 through 247138-185 C Class:
Function: Control Rod Scram Impractical Test Requirement: Exercise valves once per 92 days and measure stroke times.
(per IWV-3411 and IWV-3521)
Basis for Relief:it These valves, located on the hydraulic control units for the 185 control rod drives, perform the active safety function of rapidly inserting the control rods into the reactor core, upon receipt of a reactor scram signal from the reactor protection system. Exercising these valves quarterly during power operations could result in the rapid insertion of one or more control rods more frequently than desired. Where testing could result in the rapid insertion of control rods, thereby causing rapid reactivity transients and wear of the control rod drive mechanisms, the control rod scram test frequency identified in the Plant Technical Specifications will be utilized as the valve testing frequency.
Normal control rod motion has been shown to be an indicator that the associated cooling water header check valve (247138 -001 through -185) moves to its safety position (closed). Normal control rod motion may not occur if this check valve were to fail in the open position. An additional positive test of the closure of this valve can be provided by venting of the cooling water header during Primary Containment Integrated Leakage Testing, conducted per Technical Specification 4.6.1.2.
Normal control rod motion does not serve as an indicator that any scram discharge header check valve (247114 -001 through -185) moves to its Rev. 4 2RR17-1 12/91
ISI-T-200.0 RELIEF RE ER 17 (Cont'd.)
safety position (open), however. Since this check valve is moved to its open position only by scram exhaust flow, a positive test of the opening of 'the valve can only be provided by the periodic scram testing and control rod insertion timing specified by Technical Specification 4.1.3.2.
Verification that any charging water header check valve (247511 -001 through -185) moves to its safety position (closed), requires that the control rod drive pumps be stopped to depressurize the charging water header. This test cannot be performed during power operations because stopping the pumps would result in loss of cooling water to all control rod drive mechanisms and seal damage could result. This test cannot be performed during each cold shutdown because the control rod drive pumps supply seal water to the reactor recirculation pumps and one of the recirculation pumps might be kept running, thus continuing to need its seal water supply. The HCU accumulator pressure decay test, specified by Technical Specification 4.1.3.5.b.2, provides verification of the closure of its charging water header check valve.
The scram inlet valves (XV-247126 -001 through -185) and the scram exhaust valves (XV-247127-001 through -185) are air operated valves that full-stroke in milliseconds and are not equipped with position indication, thereby rendering measurement of their full-stroke times impractical.
Verifying that the control rod associated with each pair of these valves meets the periodic scram testing rod insertion time limits, specified by Technical Specification 4.1.3.2, is an acceptable alternate method of detecting degradation of these valves. Since these measurements of control rod insertion times are subject to the conservative limitations of Technical Specification 4.1.3.3, and because these measurements cannot be meaningfully correlated with the full-stroke times of the scram inlet and exhaust valves, trending of these scrams time measurements in any manner comparable to that of valve stroke times is both impractical and unnecessary.
These bases for relief from applicable code testing requirements for these individual control rod scram valves are intended to conform to those provided as guidance by NRC Generic Letter 89-04 (Position P7).
Rev. 4 2RR17-2 12/91
ISI-T-200.0 RELIEF RE T KR 17 (Cont'd.)
'n: Pro r functioning of the scram discharge header check valves (247114-
'-2 7126-XXX d of th xh al {XV-247127-XXX) will be verified by periodic scram testi testing o rod insertion timing, with reactor pressure >
control an d con psig, conducted per Technical Specification 4.1.3.2 and Technical Specification a) For all control rods prior to thermal power exceeding 40% of rated power, following core alternations or after a reactor shutdown that is greater than 120 days.
I b) For specifically affected individual control rods, following maintenance or modification to the control rod or control rod drive system, which could affect the scram insertion time of those specific control rods.
c) For at least 10% of the control rods, on a rotating basis, at least once per 120 days of power operation.
Proper closure of the charging water header check valves (247115-XXX) will be verified by the demonstration that each individual accumulator check valve maintains its associated accumulator pressure above the alarm f ~10 minutes with no CRD pump operating, at least once per 18 months, conducted per Technical Specification 4.1.3.5...
Proper closure of the cooling water header check valves (247138-XXX) will be verified by venting of the cooling water header during Primary Containment Integrated Leakage Testing, at least once perr 30 too 50 mmonth interval, conducted per Technical Specification 4.6.1.2.
Rev. 4 2RR17-3 12/91
ISI-T-200.0 System: Standby Liquid Control PAID: M-2148 Valves: HV-248F006
.Category: A,C Class:
Function: Containment Isolation Impractical Test Requirement: Exercise valve once per 92 days.
Basis for Relief: To verify proper opening of this stop-check valve, it is necessary to pass fluid through the valve. This action would result in an injection into t e reactor vessel and would require actuation of an explosive valve. Both actions are undesirable during power operations. Closure testing as a motor-operated stop-check valve during power operations presents the danger of having the disc stick in the closed position, blocking the only SLC injection fiowpath, with no means of detecting the failure.
Alternative Testing: The proper functioning of the Standby Liquid Control System injection fiowpath, including opening of HV-248F006, will be demonstrated once per 18 months in accordance with Technical Specification Section 4.1.5.d.
Closure testing of the valve by motor operator will be performed just prior to the injection testing once per 18 months.
Rev. 4 2RR18-1 12/91
ISI-T-200.0 RKLIKF RK KR 1 System: Standby Liquid Control P&ID: M-2148 Valves: 248F007 Category: A,C Class:
Function: Containment Isolation Impractical Test Requirement: Exercise valve once per 92 days.
Basis for Relief: To verify proper opening of this check valve, it is necessary to pass fluid through the valve. This action would result in an injection into the vessel and would require actuation of an explosive valve, both undesirable during power operations. Closure testing is only practical by pressurizing downstream of the valve (the upstream side being vented) and verifying absence of flow in the upstream side. This requires installation of temporary equipment and access to the containment which is inerted during power operation.
Alternative Testing: The proper functioning of the Standby Liquid Control System injection fiowpath, including opening of 248F007, will be demonstrated once per 18 months in accordance with Technical Specification Section 4.1.5.d.
Valve closure is demonstrated by completion of leak rate testing performed once per 24 months. See Relief Request Number 18.
Rev. 4 2RR19-1 12/91
~
0'
ISI-T-200.0 RELIEF RE T ER 20 System -" P&ID. Valve Class RCIC M-2149 HV-249 F007 RCIC M-2149 HV-249F031 RCIC M-2149 HV-249 F059 RCIC M-2149 HV-249F084 M-2151 'V-251F004A,B,C,D
. M-2151 HV-251F007A,B RHR M-2151 HV-251F022 Core Spray M-2152 HV-252F001A,B Core Spray M-2152 HV-252F031A,B HPCI M-2155 HV-255 F002 HPCI M-2155 HV-255F012
'PCI M-2155 HV-255 F042 HPCI M-2155 HV-255 F066 HPCI M-2155 HV-255F079 Containment Atmosphere M-2157 HV-25766 Control Category:
Function: Containment Isolation Impractical Test Requirement: Leak test gate valve with pressure differential in same direction as safety function.
Basis for Relief: These valves are configured such that there is no practical means of pressurizing in the direction of safety function (lack of proper isolation valves, test connections, etc.).
Rev. 4 2RR20-1 12/91
ISI-T-200.0 RELIEF RE UEST NUMBER 20 (Cont'd.)
Pressurization in the direction of safety function would require actions such as pressurizing the containment (equivalent to an ILRT) or precisely controlling the entire RCS at the valve test pressure.
10CFR50 Appendix J paragraph III.C.1 requires that the pressure be applied in the same direction as that when the valve would be required to perform its safety function, unless is can be determined that the results from the tests for a pressure applied in a different direction provide equivalent or more conservative results. The Susquehanna FSAR Section 6.2.6.3 provides confirmation that, for the subject valves, pressure applied in the opposite direction of accident pressure produces equivalent or more conservative results.
Alternative Testing: Leak test each valve in the reverse direction. Penetration will be subjected to test pressures in the correct direction during containment integrated leak rate tests.
Rev. 5 2RR20-2 05/93
0 IS I-T-200. 0 RELIEF RE UEST ER 21 System: Reactor Core Isolation Cooling PEcID: M-2149 Valves: 249F028, 249F040, 249F021 Category: A,C Class:
Function: Containment Isolation Impractical Test'Requirement: Exercise valve once per 92 days.
Basis for Relief: These check valves are not equipped with position indication and system design does not provide any practical method of verifying closure other than pressurization similar to leak rate testing. Such testing requires installation of temporary equipment which is impractical on a quarterly basis, and it would render the RCIC system inoperable during the testing period. While RCIC is not an ECCS system, it is important to safety and can provide an additional margin for prevention or mitigation of reactor transients. Normally, testing of this type is accomplished by required containment local leak rate testing in accordance with 10CFR50, Appendix J. More frequent performance represents an unnecessary burden on the licensee.
Alternative Testing: Demonstrate closure by completion of leak rate testing performed once per 24 months.
Rev. 4 2RR21-1 12/91
IS I-T-200. 0 RELIEF RE T KR 22 System: Reactor Core Isolation Cooling PAID: M-2149 Valves: 249F063, 249F064 Category:
Class:
Function: Vacuum Breaker Impractical Test Requirement: Exercise valve once per 92 days.
Basis for Relief: These vacuum breakers installed on the RCIC turbine exhaust line are not provided with position indication equipment nor is there pressure indication installed that would provide positive verification of valve operation. A practical method of testing involves supplying low pressure air upstream of the valve and verifying that fiow can be detected downstrea'm of the valve. This test method involves installation of temporary equipment and is not practical except during major outages, and it would render the RCIC system inoperable during the testing period.
While RCIC is not an ECCS system, it is important to safety and can provide an additional margin for prevention or mitigation of reactor transients. More frequent performance represents an unnecessary burden on the licensee.
Alternative Testing: Commencing with the first refueling outage, verify opening once per 24 months in conjunction with leak rate testing.
Rev. 4 2RR22-1 12/91
ISI-T-200.0 RELIEF RE VEST NUMBER 23 COLD SHUTDOWN ~ JUSTIHCATION System: Residual Heat Removal PEcID: M-2151 Sh. 2 Valves: HV-251F008, HV-251F009 Category:
Class:
Function: Containment Isolation (Shutdown Cooling)
Impractical Test Requirement: Exercise valves once per 92 days.
Basis for Relief: These normally closed isolation valves are only required to open when bringing the unit to a cold shutdown condition, providing the flowpath for the shutdown cooling mode of RHR. In accordance with guidance presented in IE Information Notice 84-74, draft R.G. 901-4, and previous NRC concerns regarding intersystem LOCAs, cycling these valves every 92 days during power operation increases the probability of exposing the downstream low pressure piping to reactor coolant pressure (since only'ne valve would have to be ruptured or failed open to expose the low pressure system to reactor coolant pressure). During reactor operations above approximately 100 psig, interlocks inhibit cycling of these valves for the express purpose of protecting low pressure piping.
Alternative Testing: Exercise valves during cold shutdown (no more frequently than once per 92 days).
Rev. 5 2RR23-1 05/93
IS I-T-200. 0 RKI.IKF RK KR 24 System P&ID Valve Number Class Category M-2151 251FO90A RHR M-2151 251FO90B Core Spray M-2152 252FO29A Core Spray M-2152 252FO29B Core Spray M-2152 252FO30A Core Spray M-2152 252FO30B HPCI M-2155 255012 M-2111 211165 A M-2111 211165B ,C Function: Prevent reverse flow out through keepfill line Impractical Test Requirement: Exercise valves to their closed positions once per 92 days (Per IWV-3521).
Basis For Relief: These check valves, located in keepfill lines for the RHR, Core Spray, and HPCI Systems provide Condensate Transfer System water flow into their respective headers, while preventing flow of process water in the reverse direction, during operation of the respective ECCS System. In the RHR and HPCI Systems, test connections exist between the two tandem check valves existing in each line; while in the Core Spray System, a single test connection exists upstream of both check valves, which are located very close together. These configurations allow individual testing of the downstream check valve in the RHR and HPCI Systems, but support only dual testing of each pair of Core Spray System check valves in combination. Using these test connections in RHR, Core Spray, and HPCI to monitor essential restriction of reverse flow involves collecting radioactively contaminated seepage while the process system is pressurized, as during flow testing. This creates the potential for spills and spread of contamination. The increase in potential for water hammer in these systems due to isolation of keepfill lines during testing, the increase in personnel radiation exposure required to perform this testing during Rev. 4 2RR24-1 12/91
ISI-T-200.0 RELIEF RK KR 24 (Cont'd.)
plant operation, and the increase in potential for contamination of personnel and equipment through this testing justify reduced frequency. The stainless steel construction of each check valve and the series configuration of each pair of check valves reduce the probability of failure to restrict reverse flow through any keepfill line.
The relatively small size of each keepfill line minimizes the impact of any such failure. The combination of these mitigating factors warrant reduction in testing frequency.
The single check valves located in the keepfill lines for the ESW System provide Service Water System flow into their respective headers, while preventing flow of process water in the reverse direction, during operation of ESW System. Test connections upstream of each check valve support testing of its reverse flow individually. Using these test connections in ESW to monitor essential restriction of reverse flow involves collecting raw service water seepage, which has the potential to chemically contaminate and degrade the operation of the plant Liquid Radwaste System. The stainless steel construction of each check valve reduces the probability of failure to restrict reverse flow through any keepfill line. The relatively small size of each keepfill line minimizes the impact of any such failure. The combination of these mitigating factors warrant reduction in testing frequency.
Alternative Testing: Demonstrate closure of each check valve in the keepfill lines of the RHR and HPCI Systems by monitoring the essential restriction of its reverse flow, through its upstream test connection, once per refueling outage while the process system is pressurized, as during flow testing.
Demonstrate closure of at least one of the two check valves in each pair in the keepfill lines of the Core Spray System by monitoring the essential restriction of their reverse flow, through their upstream test connections, once per refueling outage while the process system is pressurized, as during flow testing.
Demonstrate closure of each check valve in the keepfill lines of the ESW System by monitoring the essential restriction of their reverse flow, through their upstream test connections, once per 18 months (+3 months) while the process system is pressurized, as during flow testing.
Rev. 4 2RR24-2 12/91
e ISI-T-200.0 RELIEF RK Relief Request Deleted.
This Page IntentionalLy Left Blank.
Rev. 4 2RR25-1 12/91
'4 pr
ISI-T-200.0 RELIEF RE UEST NUMBER 26 COLD SHUTDOWN TEST JUSTIFICATION System: Residual Heat Removal PAID: M-2151 Sh. 1 and Sh. 2 Valve CategoO HV-251F015A A HV-251F015B A HV-251F022 A HV-251F023 A HV-251FOSOA A,C HV-251F050B A,C HV-251F122A A HV-251F122B A Class:
Function: Containment Isolation Impractical Test Requirement: Exercise valves once per 92 days.
Basis for Relief: These normally closed isolation valves serve as the pressure isolation between RHR system piping and reactor coolant pressure. In accordance with guidance presented in IE Information Notice 84-74, draft R.G. 901-4, and previous NRC concerns regarding intersystem LOCAs, cycling these valves every 92 days during power operation increases the probability of exposing the downstream low pressure piping to reactor coolant pressure (since only one valve would have to
~
be ruptured or stuck open to expose the low pressure system to reactor coolant pressure). Maintenance history on these valves has shown that excessive cycling at pressure will reduce the leak tightness of the valves. In addition, failure of these valves during testing to positively re-seat could cause loss of RHR system function.
Alternative Testing: Exercise valves during cold shutdowns (no more frequently than once per 92 days).
Rev. 5 2RR26-1 05/93
0 J
ISI-T-200.0 RELIEF RE ER 27 This Page IntentionaLly Left Blank.
Rev. 4 2RR27-1 12/91
ISI-T-200.0 RELIEF RE ER 2 System: High Pressure Coolant Injection P&ID: M-2155 Valves: 255F049, 255F046 Category: A,C Class:
Function: Containment Isolation Impractical Test Requirement: Exercise valve closed once per 92 days.
Basis for Relief: This valve is not equipped with position indication. Its configuration with an open discharge into the suppression pool prevents usage of reverse flow to demonstrate closure. No practical method exists to perform closure testing other than the downstream pressurization of leak rate testing. Such testing requires installation of temporary equipment and closure of valves which renders the system inoperable.
Alternative Testing: Demonstrate closure once per 24 months by completion of leak rate testing.
Rev. 4 2RR28-'1 12/91
ISI-T-200.0 RELIEF RE VEST NUMBER 29 COLD SHUTDOWN TEST JUSTIFICATION System: High Pressure Coolant Injection P8cID: M-2155 Valve: HV-255 F006 Category:
Class:
Function: Containment Isolation, HPCI Injection Impractical Test Requirement: Exercise valve once per 92 days.
Basis for Relief: This valve is in the HPCI injection flowpath. The interlocks on this valve prevent its being open unless the Steam Admission and Turbine Stop Valves are open. This is only possible during pump flow testing.
Cycling this valve during normal plant operation or HPCI testing may lead to HPCI injection into the vessel. This would affect reactor operations and introduce a thermal transient in the vessel nozzle.
Alternative Testing: Exercise valve during cold shutdowns (no more frequently than once per 92 days).
Rev. 5 2RR29-1 05/93
I l
0 a,
ISI-T-200.0 RELIEF RE UEST NUMBER 30 System: General PAID: General Valves: All valves specified as tested on a cold shutdown or refueling frequency.
Category: As applicable Class: As applicable Function: As applicable Impractical Test Requirement: Paragraph IWV-3417(a) of Section XI requires that should an unacceptable increase in stroke time be observed, the valve test frequency shall be increased to once per month until corrective action is taken.
Basis for Relief: Valves are tested on a cold shutdown or refueling frequency because there is a defined basis for exemption from quarterly testing frequency during power operation (e.g., the plant is put into an unsafe condition, system design does not permit testing). This same reasoning would, therefore, provide the basis for exemption from the monthly testing as well.
Alternative Testing: The testing frequency will remain unchanged. The requirements contained in the Susquehanna Steam -Electric Station Technical Specifications will control plant operations with regard to out-of-service valves.
Each valve exhibiting such an increase in its stroke time will have its acceptability for continued operation evaluated by a review of the tendencies and historical ranges of its stroke time measurements.
Rev. 5 2RR30-1 05/93
i ISI-T-200.0 RELIEF RE KR 1 System: High Pressure Coolant Injection P&ID: M-2155 Valves: 255 F045 Category:
Class:
Function: Backflow Prevention Impractical Test Requirement: Exercise valve once per 92 days.
Basis for Relief: To verify proper opening of this valve, it is necessary to initiate HPCI flow while taking suction from the suppression pool. Since the water quality in the suppression pool is not maintained at reactor coolant standards, it is not advisable to initiate this flow at any time during normal operations. The resulting contamination of the HPCI system from such flow testing would affect the condensate storage tank purity and ultimately affect the chemistry control of the reactor coolant system. There exists no other practical method of verifying proper valve operation.
Alternative. Testing: Verify operability by inspection during valve disassembly. The valve will be disassembled at least once every other refueling outage on an alternating basis.
Rev. 4 2RR31-1 12/91
~ i I
ISI-T-200.0 RKLIKF RK T System. High Pressure Coolant Injection P&ID: M-2155 Valves: 255F019 Category:
Class:
Function: Backflow Prevention Impractical Test Requirement: Exercise valve closed once per 92 days.
Basis for Relief: This check valve in the HPCI pump suction line is not installed in a configuration permitting positive verification of valve closure. As stated in Relief Request Number 31, alignment of the HPCI pump to the suppression pool is not desirable. Attempting to verify closure during leak rate testing of 255F045 will not provide positive verification, since there is no appropriate pressure instrumentation provided on the CST side of 255F019, and level changes in the CST would not be readily detected due to the large tank volume.
Alternative Testing: Verify operability by inspection during valve disassembly. The valve will be disassembled at least once every other refueling outage on an alternating basis.
Rev. 4 2RR32-1 12/91
ISI-T-200.0 RELIEF RE UEST NUMBER 33
'ystem: Various P&ID: M-2139 M-2143 M-2151 M-2141 M-2144 M-2152 M-2142 M-2149 M-2155 Valves: Various (listed in Susquehanna SES Technical Specification Table 3.6.3-1)
Category:
Class:
Function: Containment Isolation Impractical Test Requirement: Exercise valve once per 92 days per IWV-3520.
Basis for Relief: Excess flow check valves are installed on instrument lines penetrating containment in accordance with Regulatory Guide 1.11. As such, the lines are sized and/or orificed such that off-site doses will be substantially below 10CFR100 limits in the event of a rupture.
Therefore, individual leak rate testing of these valves is not required for conformance with 10CFR50, Appendix J requirements.
Functional testing of valves to verify closure can be accomplished by the process of venting the instrument side of the valve while the process side is under pressure. Such testing is required by Technical Specification 4.6.3.4 at least once per 18 months. Testing on a more frequency basis is not feasible for several reasons. Instruments serviced by these valves frequently have interlock or actuation functions that would be interfered with should testing be attempted during plant operation. Also, process liquid will be contaminated to some degree, requiring special measures to collect fiow from the vented instrument side.
Alternative Testing: Functional testing with verification that flow is checked will be performed at least once per 18 months per Technical Specification 4.6.3.4.
Rev. 5 2RR33-1 05/93
r~
4 t
ISI-T-200. 0 RELIEF RE T ER 34 System: High Pressure Coolant Injection PScID: M-2155 Valves: 255F076, 255F077 Category:
Class:
Function: Vacuum Breaker, Impractical Test Requirement: Exercise valve once per 92 days.
Basis for Relief: These vacuum breakers installed on the HPCI turbine exhaust line are not provided with position indication equipment nor is there pressure indication installed that would provide positive verification of valve operation. A practical method of testing involves supplying low pressure air upstream of the valves and verifying that flow can be detected downstream of the valve. This test method. involves installation of temporary equipment and is not practical except during major outages. Its implementation would also require temporary removal of the HPCI System from service.
Alternative Testing: Commencing with the first refueling outage, verify opening once per 24 months in conjunction with leak rate testing.
Rev. 4 2RR34-1. 12!91
'I L
I l
I I
ISI-T-200.0 RKLIKF RK KR System: General P8cID: General Valves: All containment isolation valves.
Category:
'lass: As applicable to specific valves.
Function: Primary Containment Isolation Impractical Test Requirement: Additional corrective actions specified for valves 6 inches and larger, that exhibit increases in leakage rate, per IWV-3427(b).
Basis for Relief: Containment leakage rate testing is governed by 10CFR50 Appendix and Susquehanna SES Technical Specification 3/4.6.1.2.
Compliance with these requirements is described in FSAR Section 6.2.6 and in FSAR Tables 6.2-19 through 6.2-22. The additional corrective actions specified by ASME code Section XI, paragraph IWV-3427(b) are not generally effective. Their usefulness does not justify the burden of complying with this requirement.
This basis for relief from all requirements imposed by IWV-3427(b) is intended to comply with that provided as guidance by NRC Generic Letter 89-04 (Position ¹10).
Alternative Testing: Primary Containment isolation valve leak testing (with the exception of identified pressure isolation function) will be performed in accordance with FSAR Section 6.2.6 and FSAR Tables 6.2-19 through 6.2-22. Evaluation of containment isolation valve leak test results will be conducted in accordance with the requirements of 10CFR50 Appendix J and Susquehanna SES Technical Specification 3/4.6.1.2.
~ge rate measurements shall be compared with previous measurements and with the permissible valve leakage rates specified by the Superintendent of Plant for Susquehanna SES.
Rev. 4 2RR35-1 12/91
ISI-T-200.0 RELIEF RE Thts Page Intentionally Left Blank.
Rev. 4 2RR36-1 12/91
ISI-T-200.0 RELIEF RE UEST NUMBER 37 COLD SHUTDOWN TEiST JUSTIFICATION System: Containment Atmosphere Control P&ID: M-2157 Slit. 1 Valves: HV-25703 HV-25713 HV-25723 HV-25704 HV-25714 HV-25724 HV-25705 HV-25721 HV-25725 HV-25711 HV-25722 Category:
Class:
Function: Containment Isolation Impractical Test Requirement: Exercise valve once per 92 days.
Basis for Relief: These normally closed containment isolation valves on the containment purge inlet and exhaust lines are not opened during power operations except during startup for inerting purposes and during shutdown procedure to de-inert. It is not good practice to cycle a normally closed containment isolation valve, as this increases the possibility of failure in the open position. Technical Specification 3.6.1.8 controls and limits the amount of time these valves can be open in a one-year
'period.
Alternative Testing: Exercise valves at cold shutdown (no more frequently than once per 92 days).
Rev. 5 2RR37-1 05/93
N l',4
'p
ISI-T-200.0 RELIEF RE UEST NUMBER '3S System: Various P8cID: Various Valves: Those designated "Rapid-Acting" in the REMARKS column.
Category: Aor B Class: 1 or 2 Function: Various (sample, containment isolation, etc.)
Impractical Test Requirement: Trend valve stroke times per IWV-3417(a).
Basis for Relief: The listed valves, designated as "rapid acting valves," have stroke times (~ 2 seconds) of such short duration that comparison of measurements with previous data for specified percentage increases is not indicative of degrading valve performance. With measurement of stroke times to the nearest second per IWV-3413(b), a very small increase in stroke time will result in an extremely large percentage change. Verification that valves meet a'specified maximum stroke time of short duration provides adequate assurance of operability.
This basis for relief from the code required corrective actions is intended to conform to the guidance provided by NRC Generic Letter 89-04 (Position ¹6).
Alternative Testing: Measured stroke time less than the limit stroke time of 2 seconds will be verified for each of these valves when exercise tested.
Rev. 5 2RR38-1 05/93
ISI-T-200.0 RELIEF RE VEST NUMBER 39 COLD SHUTDOWN ~>> JUSTIFICATION System: Reactor Building Chilled Water P8cID: M-2187 Sh. 2 Valves: HV-28791A1 HV-28792A1 HV-28791A2 HV-28792A2 HV-28791B1 HV-28792B1 HV-28791B2 HV-28792B2 Category:
Class:
Function: Containment Isolation Impractical Test Requirement: Exercise valves once per 92 days.
Basis for Relief: These containment isolation valves are located in the Reactor Building Chilled Water supply and return lines serving the Reactor Recirculation pump motor coolers. The closure of these valves during power operation will interrupt cooling water flow to the Reactor Recirculation motor coolers, which creates the possibility of overheating and damage.
Alternative Testing: Exercise valves during cold shutdowns (no more frequently than once per 92 days).
Rev. 5 2RR39-1 05/93
'I V ISI-T-200.0 RELIEF RE VEST NUMBER 40 This Page Intentionally Left Blank.
Rev. 4 2RR40-1 -
12/91
~ '
ISI-T-200.0 RELIEF RE T ER 41 System: General P&ID: General Valves: All Fail-Safe Valves Category: As applicable Class: As applicable Function: As applicable Impractical Test Requirement: Paragraph IWV-3415, Section XI Basis for Relief: Valves which have a "fail-safe" requirement at Susquehanna Steam Electric Station will normally be cycled once every 92 days', unless otherwise relieved. This test will accomplish the intent of the "fail-safe" test because normal valve movement is achieved by means of interrupting motive force to the valve.
Alternative Testing: No additional testing of "fail-safe" provisions will be done because normal valve testing will achieve the same results.
Rev. 4 2RR41-1 12/91
ISI-T-200.0 RELIEF RE T ER 42 System: General P8cID: General Valves: All pressure relief valves.
Category: As applicable Class: As applicable Function: System Overpressure Protection Impractical Test Requirement: Paragraph IWV-3100, all valves shall be pressure tested after installation and prior to service.
Basis for Relief: Pressure relief valves used at Susquehanna SES have been purchased in accordance with specifications which require performance testing at the manufacturer's shop. Records of these tests are part of the Quality Assurance records. In addition, a technical procedure requires inspection of the sealing mechanism as part of the preoperational/acceptance test program.
Alternative Testing: No additional testing beyond that which was performed as part of the purchase and installation will be performed. The records will remain part of either the purchase or preoperational records and not part of the ISI files.
Rev. 4 2RR42-1 12/91
0 ISI-T-200.0 RELIEF RK T System: Standby Liquid Control P&ID: M-2148 Pumps: 2P208 A,B Class:
Function: Standby Liquid Control Pumps Impractical Test Requirement: Measure inlet pressure prior to and during pump test and measure pump delta-p during pump test.
Basis for Relief: System configuration does not provide a pressure indicator on the pump suctions. It is possible to determine suction pressure by calculation from tank level (elevation difference) when the pumps are in normal alignment to the SLC Storage Tank. However, when pump testing is being performed, the tank is valved out and the suctions are aligned to a demineralized water header. While some estimation of the pressure in this alignment is available by the setting of the pressure control valve on the demineralized water header, no direct pressure indication is available. Since the SLC pumps are positive displacement type pumps, suction pressure will not affect developed discharge pressure.
Alternative Testing: Do not measure inlet pressure prior to or during pump tests. Utilize pump discharge pressure reading in lieu of Pump delta-p reading.
Rev. 4 2RR43-1 12/91
ISI-T-200.0 RELIEF RE T System: High Pressure Coolant Injection P&ID: M-2156 Pumps: 2P204, 2P209 Class:
Function; HPCI Main and Booster Pumps Impractical Test Requirement: If not tested during plant shutdown, the pump shall be tested within one week after the plant is returned to normal operation.
Basis for Relief: The required steam supply pressure for HPCI surveillance flow verification testing is specified in the Technical Specifications. This pressure may not be attained within the above prescribed time interval.
Alternative Testing: Perform HPCI flow verification test in accordance with quarterly schedule. After a shutdown which has exceeded the quarterly limit, recommence quarterly schedule in accordance with Technical Specification 4.5.1.b.3.
Rev. 4 2RR44-1 12/91
ISI-T-200.0 RELIEF RE UEST NUMBER 45 COLD SHUTDOWN TEST JUSTIFICATION System: Core Spray PA,ID: M-2152 Valves Cate~os HV-252FOOSA A HV-252FOOSB A HV-252F006A A,C HV-252F006B A,C HV-252F037A A HV-252F037B A Class:
Function: Containment Isolation Impractical Test Requirement: Exercise valves once per 92 days.
Basis for Relief: These normally closed Isolation valves serve as the pressure isolation between CS system piping and reactor vessel pressure. In accordance with guidance presented in IE Information Notice 84-74, draft R.G.
901-4, and previous NRC concerns regarding intersystem LOCAs, cycling these valves every 92 days during power operation increases the probability of exposing the downstream low pressure piping to reactor coolant pressure (since only one valve would have to be ruptured or failed open to expose the low pressure system to reactor coolant pressure). In addition, failure of these valves after testing to positively reseat could cause loss of Core Spray system function.
Alternative Testing: Exercise valves during cold shutdown (no more frequently than once per 92 days).
Rev. 5 2RR45-1 05/93
ISI-T-200.0 RELIEF RE VEST NUMBER 4 System: General P&ID: General Valves/Pumps: General Category: As applicable Class: As applicable Function: As applicable Impractical Test Requirement: Test equipment in accordance with Section XI frequency requirements.
Basis for Relief: With one loop out-of-service in a system, it is not desirable to test the redundant loop per ISI requirements as such testing may increase the chance of failure in a condition where backup equipment is not available. Also, these situations willbe governed by the Susquehanna Steam Electric Station Technical Specifications.
Alternative Testing: Testing will be suspended on equipment in operable loop when there is a redundant loop out-of-service.
Rev. 4 2RR46-1 12/91
ISI-T-200.0 REI IEF RE T ER 47 This Page Intentionally Left Blank.
Rev. 4 2RR47-1 12/91
I
~ .
ISI-T-200.0 RELIEF RE UEST NUMBER 48 System: High Pressure Coolant Injection PAID: M-2156 Pumps: 2P204, 2P209 Class:
Function: HPCI main and booster pumps Impractical Test Requirement: Paragraph IWP-3100, bearing temperature measurement.
Basis for Relief: These pumps are driven by a steam turbine which exhausts steam into the suppression pool. Extended run times necessary to achieve stabilized bearing temperatures could heat the suppression pool water to a temperature exceeding the Technical Specification limitof 105'F.
Alternative Testing: Eliminate bearing temperature measurement. Vibration measurements will .give adequate information concerning potential bearing temperature problems.
Rev. 5 2RR48-1 05/93
0 ISI-T-200.0 RELIEF RE UEST NUMBER 49 System: Standby Liquid Control P8cID: M-2148 Pumps: 2P208 A,B Class:
Function: Injection of sodium pentaborate into Rx vessel.
Impractical Test Requirement: Paragraph IWP-3100, bearing temperature measurement Basis for Relief: One characteristic of positive displacement pumps is that there is essentially no lag time between starting the pumps and reaching equilibrium conditions. The pump bearings are located in a motor gearbox and no direct measurement of gearbox oil temperature is possible. The gearbox casing is not a reproducible measurement point. I Alternative Testing: Vibration measurements will give information concerning potential bearing problems. The pump flow rate will be measured and changes in pump flow rate provide an early indication of degradation in pump performance.
Rev. 5 2RR49-1 05/93
l I
0
ISI-T-200.0 RELIEF RE ER 50 This Page Intentionally Left Blank.
Rev. 4 2RRSO-1 12/91
ISI-T-200.0 RELIEF RE T ER 1 This Page Intentionally Left Blank.
Rev. 4 2RR51-1 12/91
' (
ISI-T-200.0 RELIEF RE T R 2 System: RHR, Core Spray, ESW, RHRSW, HPCI, SBLC P&ID: Various Pumps: All in above systems Class: Various Function: Process flow for above systems Impractical Test Requirement: Section XI, Paragraph IWP-3210, Allowable Ranges of Inservice Test Quantities Basis for Relief: Ranges of acceptable instrument accuracies, as established by ASME Section XI paragraph IWP-4110 and Table IWP-4110-1 allow up to 6% error in pump pressure and fiow readings due to acceptable instrument accuracy of 6% (2% of full scale range times full scale range 3 times reference value).
In contrast, the acceptable pump pressure and flow values required to result from pump tests, as established by ASME Section XI paragraph IWP-3100 and Table IWP-3100-2, are limited to a range extending only 2% above the corresponding reference value and only 6% flow or 7% pressure below the reference value.
Alternative Testing: Actual instrument accuracies shall be applied to indicated values of pump flow and pressure. The values of pump flow and pressure, so corrected for the effects of instrument accuracy, shall be compared to the allowable ranges for the corresponding test quantities, from Table IWP-3100-2, for determination of acceptability.
Instrument accuracies for use in these corrections shall be determined, as needed, by calibration of the flow and/or pressure instruments utilized for the pump test.
Actual instrument accuracies for use in these corrections shall conform to the acceptable instrument accuracies established for flow instruments and for pressure instruments by Table IWP-4110-1.
Rev. 4 2RR52-1 12/91
ISI-T-200.0 RELIEF RE UEST NUMBER 53 System: HPCI P&ID M-2156 Valves: FV-25612 Category: B Class:
Function: Opens to admit steam to HPCI turbine, closes to isolate steam in the event of a turbine trip.
Impractical Test Requirements: Stroke time valves when exercised, once per 92 days.
Basis for Relief: The HPCI Turbine Stop Valve, FV-25612, has a design closure stroke time of 0.5 seconds. This rapid closure is accomplished by spring force. As a rapid-acting valve, closure of this valve cannot be timed accurately nor trended from test-to-test. In contrast, opening is accomplished hydraulically, by oil pressure working against spring force. Opening takes a much longer time than closing, but the length of time can vary greatly, depending on HPCI lube oil flow and pressure variations. The turbine stop valve has no independent manual control, but rather is controlled only by HPCI turbine oil pressure. Repetitious starts and stops of the HPCI turbine and its lube oil pumps to support attempts to precisely time "stop valve movement are detrimental to the machine. The turbine stop valve is a skid-mounted component of the HPCI turbine, and structurally integrated with the turbine.
Alternative Testing: Valve will be tested functionally. each time the HPCI turbine is tested (quarterly). No stroke timing or trending will be performed. In addition, response time testing for the HPCI system willbe performed in accordance with Technical Specifications once per 18 months.
Rev. 5 2RR53-1 05/93
1 J
I
ISI-T-200.0 REI IEP RE UEST NUMBER 54 System: RHR, Core Spray, ESW, RHRSW PAID: Various Pumps: All in above systems Class: Various Function: Process flow for above systems Impractical Test Requirement: Paragraph IWP-3100, bearing temperature and lubricant level or pressure measurement, during test.
Basis for Relief: The bearings for the pumps listed above are lubricated by the flowing fluid and therefore require no verification of adequate lubrication.
Similarly, the bearing temperatures cannot be accurately measured due to the flowing fluid.
Alternative Testing: None; component vibration readings willserve as indications of pump mechanical condition.
Rev. 5 2RR54-1 05/93
0' ISI-T-200.0 RELIEF RE T ER 55 System: RHR, Core Spray, HPCI Various P&ID'umps:
All in above systems Class: Various Function: Process suction pressure for above systems Impractical Test Requirement: Section XI Paragraph IWP-4120, required range of test instruments Basis for Relief:it Full scale ranges of test instruments, as established by ASME Code Section XI paragraph IWP-4120, are limited to three times the reference value or less. In contrast, the four RHR System Pumps 2P202A/B/C/D have suction pressure reference values as low as 5 PSIG, but have suction pressure 'ages, PI-2R002A/B/C/D permanently installed with full scale ranges 0-200 PSIG. Similarly, the four Core Spray System Pumps 2P206A/B/C/D have suction pressure reference values as low as 7 PSIG, but have suction pressure gages PI-2R001A/B/C/D permanently installed with full scale ranges 0-60 PSIG. Similarly, HPCI System Pump 2P204 has a suction pressure reference value of 18 PSIG, but has suction pressure gauge PI-1R606 permanently installed with a full scale range of 0-85 PSIG.
These permanent plant instruments require the full scale ranges for which they have been designed and installed to be able to cover the full spectrum of operating conditions and configurations of their respective systems. These permanent plant instruments have greater reliability than temporary or permanent test instruments would have.
The permanent plant instruments used for these tests have had the accuracy of their calibration specially enhanced at the nominal values of the test parameters; their accuracy within the range of test values is adequate for test purposes. The use of the permanent plant instruments for ISI pump testing ensures that pump suction pressures Rev. 4 2RR55-1 12/91
T MJMBKR (Continued) ISI-T-200.0 are being measured in the same way as they would if the pump were operated to fulfill its design safety function. Repeated temporary installation and removal of suction pressure gages is impractical due to high potential for damage to the gages through the transport and work processes.
Alternate Testing: Utilize permanent plant pump suction pressure instruments for ISI pump test suction pressure measurements in RHR, Core Spray, and HPCI Systems.
Rev. 4 2RR55-2 12/91
ISI-T-200.0 RELIEF RE ER 6 This Page Intentionally Left Blank.
Rev. 4 2RR56-1 12/91
ISI-T-200.0 RELIEF RE Y This Page Intentionally Left Blank.
Rev. 4 2RR57-1 12/91
's.
0
RELIEF RK UKST NUlVfBER 58 (Continued) ISI-T-200.0 RELIEF RK T KR System P&ID Valve Category Chss Function CIG M-2126 SV-22605 Containment Isolation CIG M-2126 SV-22643 Instrument Gas Storage CIG M-2126 SV-22644 Instrument Gas Storage CIG M-2126 SV-22648 Instrument Gas Storage CIG M-2126 SV-22649 Instrument Gas Storage CIG M-2126 SV-22651 Containment Isolation CIG M-2126 SV-22654A Containment Isolation CIG M-2126 SV-22654B Containment Isolation CIG M-2126 SV-22661 Containment Isolation CIG M-2126 SV-22671 A Containment Isolation CAC M-2157 SV-25734A Containment Isolation CAC M-2157 SV-25734B Containment Isolation CAC M-2157 SV-25736A Containment Isolation CAC M-2157 SV-25736B Containment Isolation CAC M-2157 SV-25737 Containment Isolation CAC M-2157 SV-25738 Containment Isolation CAC M-2157 SV-25740A Containment Isolation CAC M-2157 SV-25740B Containment Isolation CAC M-2157 SV-25742A Containment Isolation CAC M-2157 SV-25742B 2 Containment Isolation CAC M-2157 SV-25750A Containment Isolation CAC M-2157 SV-25750B Containment Isolation CAC M-2157 SV-25752A Containment Isolation CAC ~
M-2157 SV-25752B Containment Isolation CAC M-2157 SV-25767 Containment Isolation Rev. 4 2RR58-I 12/91
>1
~ i p, 'E 0
RELIEF RE T NUMBER (Cont'd.) ISI-T-200.0 System P&ID Valve Category Chss Function CAC M-2157 SV-25774A Containment Isolation CAC M-2157 SV-25774B Containment Isolation CAC M-2157 SV-25776A Containment Isolation CAC M-2157 SV-25776B Containment Isolation CAC M-2157 SV-25780A Containment Isolation CAC M-2157 SV-25780B Containment Isolation CAC M-2157 SV-25782A Containment Isolation CAC M-2157 SV-25782B Containment Isolation CAC M-2157 SV-25789 Containment Isolation CAC M-2157 SV-257100A Containment Isolation CAC M-2157 SV-257100B Containment Isolation CAC M-2157 SV-257101A Containment Isolation CAC M-2157 SV-257101B Containment Isolation CAC M-2157 SV-257102A Containment Isolation CAC M-2157 S V-257102B Containment Isolation CAC M-2157 SV-257103A Containment Isoaltion CAC M-2157 SV-257103B Containment Isolation CAC M-2157 SV-257104 Containment Isolation CAC M-2157 SV-257105 Containment Isolation CAC M-2157 SV-257106 Containment Isolation CAC M-2157 SV-257107 Containment Isolation Impractical Test Requirement: Valves with Remote Position Indicators shall be observed at least once every 2 years to verify that valve operation is accurately indicated.
Basis For Relief: The subject solenoid valves, all of which are manufactured by the Target Rock Corporation, all are constructed in a manner that precludes local verification of valve operation by direct observation. All movements and positions of valve parts are obscured by the valve structure within which they travel and Rev. 4 2RR58-2 12/91
1 I
h,p 1
I l
0
RELIEF RE T NVMBER (Cont'd.) ISI-T-200. 0 within which they are sealed. A method for indirect observation of valve movement, utilizing ferritic steel objects (steel shot) moved along the surface of each valve's indicating tube by the permanent magnet attached to the valve stem inside, was devised, used for 18 months, and subsequently abandoned because its employment necessitated partial disassembly of the solenoid valve for the test. This disassembly and reassembly, consisting of removal and reinstallation of the reed switch housing assembly, or cover, has been found to cause damage to the wiring and its connections to the reed switches.
Alternative Testing; Confirmation of coincident valve movement and remote indication is accomplished by listening to the valve with a stethoscope, for the audible signal of the valve disk arriving at a new position. Accuracy of remote indication of valve operation is essentially verified for these solenoid valves at least once every 2 years by the combination of containment isolation valve leak testing (LLRT) (or instrument gas storage leakdown testing) with accomplishment of General Operating Procedures (GO-200-002) for plant startup and heatup. These activities are completed at least once each refueling shutdown, as follows: .
Refueling C
,y
- ,
- . Shutdown'" : Verified .Verified
', Testing" -
Valve~" Startup; Valve Sy'tem Valve :;:.,Pro'cedure', ': ='osition .' -
Procedure(s)' -
Position'IG SV-22605 SE-259467 Closed OP-225401/GO-200402 Open CIG SV-22643 TP-225407 Open OP-225401/GO-200-002 Open CIG SV-22644 TP-225407 Closed OP-225-001/GO-200402 Open CIG SV-22648 TP-225409 Open OP-225401/GO-200-002 Open CIG SV-22649 TP-225-009 Closed OP-225401/GO-200-002 Open CIG SV-22651 SE-259437 Closed OP-225-001/GO-200-002 Open CIG SV-22654A SE-259446 Closed OP-225-001/GO-200-002 Open CIG SV-22654B SE-259438 Closed OP-225401/GO-200402 Open CIG SV-22661 SE-259-069 Closed OP-225401/GO-200402 Open CIG SV-22671 SE-259490 Closed OP-225401/GO-200402 Open Rev. 4 2RR58-3 12/91
l 0
RELIEF RE T ER 58 (Cont'd.) ISI-T-200.0 Refueling; Shutdown Verified Verified Testing Valve Startup Valve System Valve Procedure Position Procedure(s) Position CAC SV-25734A SE-259419 Closed OP-273401/GO-200-002 Open CAC SV-25734B SE-259420 Closed OP-273401/GO-200402 Open CAC SV-25736A SE-259-019 Closed OP-273401/GO-200402 Open CAC SV-25736B SE-259-020 Closed OP-273401/GO-200402 Open CAC SV-25737 SE-259-103 Closed OP-273401/GO-200402 Open CAC SV-25738 SE-259-103 Closed OP-273401/GO-200-002 Open CAC SV-25740A SE-259419 Closed OP-273401/GO-200-002 Open CAC SV-25740B SE-259-020 Closed OP-273401/GO-200402 Open CAC SV-25742A SE-259419 Closed OP-273401/GO-200402 Open CAC SV-25742B SE-259420 Closed OP-273401/GO-200-002 Open 0 CAC CAC CAC SV-25750A SV-25750B SV-25752A SE-259419 SE-259420 SE-259419 Closed Closed Closed OP-273401/GO-200-002 OP-273401/GO-200402 OP-273401/GO-200402 Open Open Open CAC SV-25752B SE-259420 Closed OP-273-001/GO-200402 Open CAC SV-25767 SE-259-102 Closed OP-273401/GO-200402 Open CAC SV-25774A SE-259419 Closed OP-273401/GO-200-002 Open CAC SV-25774B SE-259420 Closed OP-273401/GO-200402 Open CAC SV-25776A SE-259419 Closed OP-273401/GO-200402 Open CAC SV-25776B SE-259420 Closed OP-273401/GO-200402 Open CAC SV-25780A SE-259419 Closed OP-273401/GO-200402 Open CAC SV-25780B SE-259420 Closed OP-273401/GO-200402 Open CAC SV-25782A SE-259419 Closed OP-273401/GO-200402 Open CAC SV-25782B SE-259420 Closed OP-273401/GO-200-002 Open CAC SV-25789 SE-259-102 Closed OP-273-001/GO-200-002 Open CAC SV-257100A SE-259419 Closed OP-273-001/GO-200-002 Open Rev. 4 2RR58-4 12/91
I
(
RELIEF RE T ER (Cont'd.) ISI-T-200.0
" Refueling.
Shutdown ." Verified
,Verified'alve:
Testing; .
. Startup Valve System Valve Procedure. Position. . Procedure(s) Position CAC SV-257100B SE-259420 Closed OP-273401/GO-200402 Open CAC SV-257.101A SE-259419 Closed OP-273-001/GO-200402 Open CAC SV-257101B SE-259-020 Closed OP-273401/GO-200402 Open CAC SV-257102A SE-259419 Closed OP-273-001/GO-200402 Open CAC SU-257102B SE-259420 Closed OP-273-001/GO-200-002 Open CAC SV-257103A SE-259419 Closed OP-273401/GO-200402 Open CAC SV-257103B SE-259-020 Closed OP-273401/GO-200402 Open CAC SV-257104 SE-259419 Closed OP-273401/GO-200-002 Open CAC SV-257105 SE-259-019 Closed OP-273401/GO-200402 Open CAC SV-257106 SE-259419 Closed OP-273401/GO-200-002 Open CAC SV-257107 SE-259-019 Closed 'OP-273-001/GO-200402 Open Rev. 4 2RR58-5 12/91
ISI-T-200.0 RELIEF RE UEST NUMBER 59 RELIEF REQUEST DELETED This Page Intentionally Left Blank.
Rev. 5 2RR59-1 05/93
\
0
RELIEF RE UEST NUMBER 60 (Continued) ISI-T-200.0 RELIEF RE UEST NUMBER 60
" %l;:;,YC 5 ~)Sgstem,:-.'..:.': g:':,.':gVaIi'e.NNumb'ir", ;:CIass'!
..;;.'41FO24A MSIV M-2141 MSIV M-2141 241FO24B lg'j.::'.',Cat'egos,'.,,',;'unction:
MSIV M-2141 241FO24C MSIV M-2141 241FO24D .
MSIV M-2141 241FO29A MSIV M-2141 241FO29B MSIV M-2141 241FO29C MSIV M-2141 241FO29D Prevent reverse flow out through MSIV accumulator inlet (air) line.
Impractical Test Requirement: Exercise valves to their closed positions once per 92 days (per IWP-3521).
Basis For Relief: These check valves, located in MSIV accumulator inlet(air) lines provide Containment Instrument Gas System and Instrument Air System gas flow into their respective MSIV accumulators, while
, preventing flow of gas stored in the MSIV accumulator in the reverse direction, during closure of their respective MSIV's at the onset of a LOCA. Plant configuration and exclusion of personnel from the purged drywell during operation preclude completion of closure exercise testing throughout the period of each plant operating cycle.
Any exercise testing of these check valves requires or causes closure of the associated MSIVs, rendering it impractical except during refueling outages. The design basis of these check valves for the inboard MSIVs is established by PP&L Calculations M-MSS-025 and M-MSS-028, from which testing appropriate to their safety function is derived.
E Exercise testing of these check valves requires both access to each MSIV accumulator and that the MSIV associated with each check valve tested remain closed throughout the test to prevent unplanned actuations of Engineered Safety Features. As the primary containment is not opened and entered during every cold shutdown and as plant configuration does not always support MSIV closure Rev. 5 2RR60-1 05/93
'Cs
- I 0
RELIEF RE UEST NUMBER 60 (Continued) ISI-T-200.0 while primary containment entry is in progress, exercise testing of these check valves is not practical at every cold shutdown, and can be performed safely and reliably only during each refueling outage.
A1ternative Testing: Demonstrate closure of each MSIV accumulator check valve by monitoring the essential restriction of its reverse flow of gas, through measurement of the rate of decay of pressure in its respective MSIV accumulator (downstream of the check valve under test) once per refueling outage. This MSIV accumulator pressure decay test provides verification of the closure of the inlet check valve.
Rev. 5 2RR60-2 05/93
I'r P
Y'
ISI-T-200.0 RELIEF RE UEST NUMBER 61 System: Control Rod Drive Hydraulic PAID: M-2147 Valves: XV-247FO10A, XV-247FO11A XV-247F010B, XV-247F011B Class:
Function: CRD Scram Discharge Volume venting and draining Impractical Test Requirement: Paragraph IWV-3417(a) Corrective Action, increasing test frequency to monthly whenever stroke time increases by
) )
25% (when over 10 seconds) or by 50% (when under 10 seconds) ~
Basis For Relief: These globe valves are air operated and have comparatively complex actuation logic schemes sequencing their start and stop times. P&ID M-2147 Notes ¹21 Sc 22 establish additional restraints, which are satisfied administratively, upon the stroke times and sequencing of these valves. The pneumatic actuators of these valves have their exhaust airflows metered by needle valves. Their actuation rate is extremely sensitive to the slightest changes in the positions of the needles in these needle valves, as caused by readjustment, by physical shock, or by thermal change. By readjustment of the exhaust needle valve position, these valves are maintained in compliance with the stroke time and sequencing limitations of the PAID, which, although dissimilar from those of Article IWV-3000, provide a more relevant basis for verifying the operational readiness of these particular valves.
Stroke time measurement of these AOVs is primarily a measure of the balance of their entire actuating air supply/exhaust network; it is not a reliable measure of the physical condition of the valve under test.
Position change of the common needle valves in the actuating air exhaust lines has been the primary, dominant, and only significant cause of changes in stroke times of these AOVs. Measurements of the stroke times of these AOVs are indicative mainly of needle valve position; and not of the AOV physical condition. Mechanical failure of any of these valves would cause a large and definitive increase in its stroke time, causing it to exceed its 30 second Limit Stroke Time and plant Technical Specification 4.1.3.1.4.a.1 limit.
Rev. 5 2RR61-1 05/93
I
~ ~
RELIEF RE UEST NUMBER 61 (Continued) ISI-T-200.0 These valves are located in a radiologically contaminated area of the plant. They have no remote position indication usable for testing; and they have no individual control mechanism (only two common pushbuttons): Consequently, exercise testing of the valves requires simultaneous entry of their radiologically contaminated area by four observers. Upon the common actuation of all four valves, simultaneous direct observation (accompanied by stopwatch timing) is made of the valve stems of all four AOVs during their closure strokes. This crude testing method of simultaneous direct observation of valve stem motion does not produce stroke timing results accurate, enough to justify any concern over 25% (or 50%) rates of variation in individual stroke time measurements.
Alternative Testing: Exercise testing of the four valves is to be performed quarterly, per IWV-3410 requirements, except that the IWV-3417(a) stroke time increase limitations (of 25% above 10 seconds and 50% below 10 seconds) will not be applied. No trending of valve stroke times will be done.
Rev. 5 2RR61-2 05/93
~,
f t,
1
ISI-T-200.0 RELIEF RE UEST NUMBER 62 RELI EF REQU EST DELETED This Page Intentionally Left Blank.
Rev. 5 2RR62-1 05/93
ISI-T-200.0 RELIEF RE UEST NUMBER 63 System: High Pressure Coolant Injection P&ID: M-2156
, Pumps: 2P204 and 2P209 (combination)
Class:
Impractical Test Requirement: Paragraph IWP-3500(a) requires for the duration of the test to be at least 5 minutes, with the pump run under conditions as stable as the system permits.
Basis For Relief: These pumps are driven by a steam turbine which exhausts steam into the suppression pool, heating it toward its Technical Specification limit of 105'F. This is a severe limitation on test duration.
Increasing suppression pool temperature toward its 105'F limit, while within limits, does reduce plant safety margin in the event of an accident occurring during or after a test. Frequent test repetition is not desirable due to the strong transient nature of a HPCI quick start.
Such quick starts are recommended by INPO and have been adopted as PP&L's test method. Pump speed is not directly controllable, but can only be achieved through coordinated manipulation of the pump flow controller and the test system throttling valve. Test results are extremely sensitive to variations in pump speed; from all sources.
These factors make this test uniquely time-dependent. I Furthermore, the HPCI Pump quarterly surveillance test procedure is structured to first demonstrate satisfaction of Technical Specification 4.5.1.b.3 by running the pump at its rated flow rate and discharge pressure conditions, which create essentially the same test conditions as those for inservice testing. This prior technical specification test performance has the effect of providing several minutes of pump warmup time at rated conditions before the inservice test.
Alternative Testing: The pumps shall be run for at least one minute under conditions as stable as the system permits. At the end of this time at least one measurement or observation of each of the quantities specified shall be made and recorded.
Rev. 5 2RR63-1 05/93
1 1
~ .
I I
ISI-T-200.0 RELIEF RE T ER 64 System P&ID Valve Category Class Function ESW M-2111 211132 ESG & Load Center Rooms cooling ESW M-2111 211133 ESG & Load Center Rooms cooling ESW M-2111 211134 ESG & Load Center Rooms cooling ESW M-2111 211135 ESG & Load Center Rooms cooling RCIC M-2149 249 F063 Turbine exh steam line vac brkr RCIC M-2149 249 F064 Turbine exh steam line vac brkr M-2151 251FO46 A/B/C/D RHR pump minimum flow line LPCS M-2152 252FO36 A/B/C/D CS pump minimum flow line HPCI M-2155 255FO76 Turbine exh steam line vac brkr HPCI M-2155 255 F077 Turbine exh steam line vac brkr Impractical Test Requirement: NRC Generic Letter 89-04 Position 1 requirement that, during opening exercise testing, a check valve's "full-stroke" to the open position be verified by passage of "maximum required accident condition flow" through the check valve; and ASME Code Section XI Paragraph IWV-3521 requirement that check valves be tested every 3 months.
Basis For Relief: In recognition that establishing design accident flow through these valves for testing could result in degradation or damage to major plant equipment, NRC Generic'Letter 89-04 Position 2 establishes that disassembly and inspection of these check valves may be used as a positive means of determining that a valve's disk will "full-stroke" open ..., as permitted by ASME Code Section XI Paragraph IWV-3522. Ifpossible, partial valve stroking quarterly or during cold shutdowns or after reassembly must be performed, additionally. Due to the scope of these inspections, the personnel hazards involved, and system operating restrictions, NRC Generic Letter 89-04 Position 2 establishes that valve disassembly and Rev. 4 2RR64-1 12/91
e'q I
0'
~
t 4 l I'
l
'n
RELIEF RE UEST NUMBER 64 (Cont'd.) ISI-T-200.0 inspection may be performed during reactor refueling outages. As it is burdensome to disassemble and inspect all of the subject valves each refueling outage, NRC Generic Letter 89-04 Position 2 establishes that a sample inspection plan for groups of up to four identical valves in similar applications may be employed, within
~
the NRC guidelines specified within Position 2.
Alternative Testing: Perform partial valve stroke exercise testing at quarterly testing frequency, at cold shutdown testing frequency, or at other frequency, as specified in separate Relief Requests, specific to each check valve. Establish and employ a sample disassembly and
, inspection plan for groups of up to four identical valves in similar applications. Disassemble, inspect, verify structural soundness of internal components, and manually exercise the disk through its full stroke for one different valve in each group at each successive refueling outage (or 18 month + 3 month period for common plant valves and ESW valves), until the entire group has been inspected.
As an alternative to inspection, optionally perform full valve stroke exercise testing, utilizing a non-intrusive diagnostic test system, employing externally generated magnetic flux monitoring, acoustic emission monitoring and/or ultrasonic techniques, on the same schedule; i.e., diagnostic test one different valve in each group at each successive refueling outage (or 18 month + 3 month period for common plant valves), until the entire group has been
'iagnostic-tested or inspected.
Rev. 5 2RR64-2 05/93
y~
1 4
'I k 4 IN Q g d
ISI-T-200.0 RELIEF RE UEST NUMBER 65 O,System':"'.:.::,-:P&lo.~ ~ ':.i.".:,,;:i,:.'::.";;',Vil'v,e;,:'.;:.:';:::;,':;:..:':,'",',,",;'::,:;,i;:: .':::;:::;.:':;,Cate'jo'ry",.:',::::;; Clas's':;::
RCIC M-2149 249F021 2 RCIC pump minimum flow line FPC&C M-2153 253071 A/B ,
FPC&C isolation from ESW system HPCI M-2155 255 F045 2 HPCI supp pool suction line HPCI M-2155 255F046 2 HPCI pump minimum fiow line HPCI M-2156 256F048 HPCI lube oil cooler return line HPCI M-2156 256F057 2 HPCI lube oil outlet line Impractical Test Requirement: NRC Generic Letter 89-04 Position 1 requirement that, during opening exercise testing, a check valve's "full-stroke" to the open position be verified by passage of "maximum required accident condition flow" through the check valve; and ASME Code Section XI Paragraph IWV-3521 requirement that check valves be tested every 3 months.
Basis For Relief: , In recognition that establishing design accident flow through these valves for testing could result in degradation or damage to major plant equipment, NRC Generic Letter 89-04 Position 2 establishes that disassembly and inspection of these check valves may be used as a positive means of determining that a valve's disk will "full-stroke" open ...,
as permitted by ASME Code Section XI Paragraph IWV-3522. If possible, partial valve stroking quarterly or during cold shutdowns or after reassembly must be performed, additionally. Due to the scope of these inspections, the personnel hazards involved, and system operating restrictions, NRC Generic Letter 89-04 Position 2 establishes that valve disassembly and inspection may be performed during reactor refueling outages. As it is burdensome to disassemble and inspect all of the subject valves each refueling outage, NRC Generic Letter 89-04 Position 2 establishes that a sample inspection plan for groups of up to four identical valves in similar applications may be employed, within the NRC guidelines specified Rev. 4 2RR65-1 12I91
p I
0
RELIEF RE VEST NUMBER 65 (Cont'd.) ISI-T-200.0 within Position 2. As the population of identical valves, among those listed above, is extremely small," groups of up to four identical valves in similar applications in both units will be created for sampling.
Alternative Testing: Perform partial valve stroke exercise testing at quarterly testing frequency, at cold shutdown testing frequency, or at other frequency, as specified in separate Relief Requests, specific to each check valve. Establish and employ a sample disassembly and inspection plan for groups of up to four identical valves, shared among both units, in similar applications. Disassemble, inspect, verify structural soundness of internal components, and manually exercise the disk through its full stroke for one different valve in each group at every "pair" of refueling outages, alternating between the two units, until the entire group has been inspected. The Fuel Pool Cooling and Cleanup check valves, not normally tested during refueling outages, are tested on a 72 month frequency for each valve.
As an alternative to inspection, optionally perform full valve stroke exercise testing, utilizing a non-intrusive diagnostic test system, employing externally generated magnetic flux monitoring, acoustic emission monitoring and/or ultrasonic techniques, on the same schedule; i.e., diagnostic test one different valve in each group at every "pair" of refueling outages, alternating between the two units, until the entire group has been diagnostic-tested or inspected.
Rev. 4 2RR65-2 12/91
I
'I
- 'I
't
~
I~ ~
I
- II ~ 'I
~ J ~ '\ ~
ISI-T-200.0 RELIEF RE VEST NUMBER 66 System: Containment Instrument Gas P&ID: M-2126 Valves: 226018 and 226029 Category:
Class:
Function: Provide Actuating Gas to Automatic Depressurization Feature of Main Steam Relief Valves.
Impractical Test Requirement: Exercise valves once per 92 days (per IWV-3521).
Basis For Relief: Closure of the subject valves for exercise testing interrupts instrument gas supply to the ADS solenoids of the Safety/Relief Valves, compromising their ability to provide the opening motive force for the ADS valves, in support of the long-term cooling ECCS function.
Due to the configuration of the CIG System, depressurization and venting of sufficient pipe lines to permit closure exercise testing of these valves further interrupts instrument gas supply to several important valves inside containment, such as the Safety/Relief Valves (non-ADS relief function) and the MSIV'S. This could compromise the ability of the SRV's to operate in the relief mode which, while not an ECCS function, is important to safety. Loss of instrument gas supply could also cause the MSIV's to close, resulting in a severe reactor transient if operating; or in an undesirable ESF actuation, ifshut down. Loss of instrument gas supply could also cause isolation of the drywell cooling lines, resulting in a drywell temperature excursion.
Testing of these check valves at every cold shutdown is not practical because it requires isolation of a line feeding 25 air operated primary containment isolation valves. Isolation of this line at any time other than at a refueling outage creates the danger of unplanned actuations of Engineered Safety Features. Additionally, 4 of these 25 air operated containment isolation valves isolate drywell cooling lines.
Rev. 5 2RR66-1 05/93
~
4 r su I l I
N ~
J ~ 4 E ~ y A
~ P 'I P
I JC l '
ISI-T-200.0 Unplanned isolation of dry well cooling during cold shutdown could cause a containment temperature transient that could exceed the design maximum temperature of the drywell. Only during refueling outages are provisions made for temporary additional cooling of the drywell.
Alternative Testing: Demonstrate closure of each check valve by monitoring the essential restriction of its reverse airflow, through the test connection downstream of the opposite division check valve, once per refueling outage.
Rev. 5 2RR66-2 05/93
,s, II
)c II p
=I ~
4 I
h i
I f ~
r d J M
1
~ ~
n P II
ISI-T-200.0 RELIEF RE UEST NUMBER 67
.;:I..;.:-.i::,::System'::.",:.::p:,'.'":,",,.i,:!,::,"':,'P&lO:,;,; :.'<%Vali'es:::: 4::':'"::::": '"':>'Categoiy'"::::::: Clasi
'HR M-2151 HV-251F008 RHR M-2151 HV-251F009 A M-2151 HV-251F015A/B M-2151 HV-251F022 M-2151 HV-251F023 A RHR M-2151 HV-251FOSOA/B RHR M-2151 HV-251F122A/B Core Spray M-2152 HV-252F005A/B Core Spray M-2152, HV-252F006A/B Core Spray M-2152 HV-252F037A/B Function: Pressure Isolation of reactor coolant system pressure from each attached low pressure system.'dditional F
Impractical Test Requirement: corrective actions specified for valves 6 inches and larger, that exhibit increases in leakage rate, per IWV-3427(b).
Basis For Relief: Leakage rate testing is governed by Susquehanna SES Technical Specification 3.4.3.2. Compliance with these requirements is described in Technical Specification 4.4.3.2.
The additional corrective actions specified by ASME Code Section XI, paragraph IWV-3427(b) are not generally effective. Their usefulness does not justify the burden of complying with this requirement. Their adherence could require a shutdown of the plant during an 18 month operating cycle for the accompishment of the additional leakage tests.
II Alternative Testing: Pressure isolation valve testing will be performed in accordance with Technical Specification 4.4.3.2. Evaluation of pressure isolation valve leak test results willbe conducted in accordance with the requirements of Technical Specification 3.4.3.2.,Leakage rate measurements shall be compared with previous measurements and with the permissible valve leakage rates specified by Technical Specification 3.4.3.2.
Rev. 5 2RR67-1 05/93
e
~ I
~ ~
IV
~ ~ '
I ~" ~
I~ ~
~,
e I ~
.4".
,' 4"
~ I I v I ~
~ I fd I
4 , )~ , ~
4)
) ~
-4 I ~
e I IC
ISI-T-200.0 RELIEF RE UEST NUMBER 68 System: General P&ID: General Valve: General Category: General Class: General Function: As applicable to specific valves.
Impractical Test Requirement: Paragraph IWV-3412 requires that valves that cannot be exercised during plant operation be specifically identified by the Owner and be full stroke exercised during cold shutdowns.
Basis For Relief: By omission of any exceptions, the paragraph IWV-3412 statement implies that all valves not exercised during normal plant operation must be exercised at every cold shutdown, meeting the 3 month test interval qualification. In rare cases where it may be advantageous to resume operation immediately after reaching cold shutdown, plant duration in the cold shutdown condition may not permit exercise testing of all valves designated for test. In such cases, maintaining the plant in a cold shutdown status solely to exercise test additional valves would not justify the burden of complying
'with this requirement.
Alternative Testing: Exercise testing of cold shutdown frequency valves shall commence no later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after the plant enters Cold Shutdown (Operational Condition 4) from Power Operation, except during refueling outages. Valves identified for cold shutdown test frequency are subject to testing if they have not been tested in the previous 92 days. Testing shall continue until all subject valves are tested or the plant begins startup. Testing at subsequent cold shutdowns will commence with those valves having the longest interval, greater than 92 days, since previous tests.
Rev. 5 2RR68-1 05/93