ML20148D622

Forwards Revised Tables & Relief Requests Necessary to Accommodate Test Methodology Incorporating 880303-08 Telcon Comments for Valves in Question in Order to Expedite Addl Interim Relief.Fee Paid

ML20148D622
Person / Time
Site:	Farley
Issue date:	03/17/1988
From:	Mcdonald R ALABAMA POWER CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8803240094
Download: ML20148D622 (21)

Text

_ _ _ _ _ _ _ _ _ _ - _ - _ _ _ -

e' a

• Alibama Power Company 600 North 18th Street Post Office Box 2641

' Birmingham, Alabama 352910400 Telephone 205 250-1835 L

nio ce Pr $4 dent Alabama Power the SOuttem dectic system Docket No. 50-348 10CFR50.55a(g)(6)(i)

March 17, 1988 U. S. Nuclear Regulatory Comission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:  !

Joseph M. Farley Nuclear Plant - Unit 1 Second Ten Year Interval Inservice Testing Program for ASME Code Class 1, 2 and 3 Pumps and Valves Alabama Power Conpany pre' acusly submitted the subject Inservice Testing .-

(IST) Program to the NTc by letters dated September 30 and November 20, 1987. By letter dated December 10, 1987 the NRC granted interim relief for the relief requests subnitted with the program. However, the NRC stated that interim relief for 23 7alves in the high and low head safety injection systems was granted only until the next refueling outage scheduled to start in March 1988. In an effort to expedite additional interim relief, Alabama Power Company has now developed an alternative test methodology as prescribed by the NRC. This methodology incorporates the connents of the conference calls held with the NRC between March 3 and 8, 1988 for the valves in question.

In lieu of the system test previously utilized, valve disassembly on a sampling basis will be employed at the eighth refueling outage to verify valve forward flow operability. This alternative is described in the enclosure, which contains the revised valve tables and relief requests i necessary to accomodate this test method. This enclosure constitutes Revision 1 of the IST Program. j i

p50 apksk 6 9

8803240094 880317 PDR ADOCK 05000348 p DCD

U. S. Nuclear Regulatory Comission March 17, 1988 Page 2 Valve disassembly on a sampling basis will be performed on one valve from each of the following five groups of valves as described in the referenced relief requests:

WESTINGHOUSE SCHEDULAR OPERABILITY TPNS NUMBER NUMBER _RELIEl' RDQUEST RELIEF REQUEST ole 11V021A, B & C 8973A, B & C Q1E11-RV-7 Q1E11-RV-4 Q1E11V051A, B & C 8998A, B & C Q1E11-RV-3 Q1E11-RV-5 Q1E21V062A, B & C 8997A, B & C Q1E21-RV-4 Q1E21-RV-10 Q1E21V066A, B & C 8995A, B & C Q1E21-RV-6 Q1E21-RV-10 Q1E21V078A, B & C 8990A, B & C Q1E21-RV-6 Q1E21-RV-10 01E21V079A, B & C 8992A, B & C Q1E21-RV-6 Q1E21-RV-10 01E21V077A, B & C 8993A, B & C ole 21-RV-11 Q1E21-RV-14 For the record, the NRC also stated in the referenced discussions that a valve which is disassembled for the purpose of operability testing has not, as the Code specifies, "undergone maintenance that could affect its performance." Therefore, operability testing following reassembly to "demonstrate that the performance parameters, which could be affected by the ... maintenance are within acceptable limits," is not required by Section XI, IWV-3200.

It should be noted that the alternative test methodology described above addresses 21 of the 23 valves identified in the NRC letter of December 10, 1987. We remaining two valves, ole 21V076A & B (8988A & B) are passive and serve a safety related function only as primary pressure isolation valves.

h erefore, these valves are not required to open to perform their safety function and verification of individual forward flow capability is not required. On this basis the reliefs requested do not address these valves.

Finally, relief requests Q1E11-RV-2, Q1E11-RV-6, QlE21-RV-12 and Q1E21-RV-13 included in the enclosure contain editorial changes only.

Relief request Q1E21-RV-15 has been deleted since the necessary relief for valves 01E21V077A & B has been combined into a similar relief request (01E21-RV-14) for valve ole 21V077C.

U. S. Nuclear Regulatory Comibsion March 17, 1988 Page 3 It is respectfully requested that the reliefs described herein be granted by March 25, 1988 on an interim basis until the Unit i ninth refueling outage or until final approval of the reliefs are granted, whichever is earlier. Granting of these interim reliefs will ensure that an approved IST Program is available for utilization during the upcoming outage. A subsequent submittal will be made by Alabama Power Company by March 31, 1988 requesting final approval of these reliefs.

Pursuant to 10CrR170.21, the required application fee of $150.00 is enclosed. If there are any questions please advise.

Respectfully submitted, f

AIMM PNER gmMW ,

I f D' l

l g.-

i R. P. Mcdonald l RPM / SIB:csl-V4 Enclosure cc: Mr. L. B. Long Dr. J. N. Grace Mr. E. A. Reeves Mr. W. H. Bradford l

l l

l i

!!NCI46URE IST PROGRAM REVISION 1

SUMMARY

OF CHANGES RE OVE PAGE INSERT PAGE DESCRIPTION OF CHANGE III-1-2-1 III-1-2-1 Revised relief request references for valves QV021A, B & C.

III-1-2-2 III-1-2-2 Revised relief request references for valves QV021A, B & C.

III-1-2-8 III-1-2-8 Deleted reference to valves QV021A, B

& C and their Code class. .

III-1-2-9 III-1-2-9 Revised the "Basis for Relief" and i

"Alternate Testing" statements.

III-1-2-10 III-1-2-10 Revised the "Basis for Relief" and i "Alternate Testing" statements.

III-1-2-11 III-1-2-11 Revised the "Basis for Relief" and "Alternate Testing" statements.

I III-1-2-12 III-1-2-12 Editorial change to renumber existing relief request Q1E11-RV-6. ,

l l

III-1-2-13 III-1-2-13 New relief request added for valves j QV021A, B & C.

l III-1-2-14 -

Deleted page, i

III-1-7-4 III-1-7-4 Revised relief request reference for valves QV077A & B.

III-1-7-19 III-1-7-19 Revised the "Basis for Relief" and j "Alternate Testing" statements.

l III-1-7-21 III-1-7-21 Revised the "Basis for Relief" and "Alternate Testing" statements.

III-1-7-25 III-1-7-25 Revised the "Basis for Relief" and  ;

"Alternate Testing" statements.

!!NCIOSURE IST PROGRAM REVISION 1

SUMMARY

OF CHANGES REMOVE PAGE INSERT PAGE DESCRIPTION OF CHANGE III-1-7-26 III-1-7-26 Revised the "Basis for Relief" and "Alternate Testing" statements.

III-1-7-27 III-1-7-27 Editorial change to renumber existing relief request Q1E21-RV-12.

III-1-7-28 III-1-7-28 Editorial change to renumber existing relief request QlE21-RV-13.

III-1-7-29 III-1-7-29 Revised the "Basis for Relief" and "Alternate Testing" statements.

III-1-7-30 -

Deleted page.

III-1-7-31 -

Deleted page.

III-1-7-32 -

Deleted page. Relief request for valves ov077A & B was combined with relief request valves OV077C (Q1E21-RV-14).

STB:csl-V4 4

P

,,_...-_-,_,.,w-._--- -

%.,-,,.y __- - , - . - - _ y _

, . . _ . _ _ . . - -. - _ - .._. - - _ - -_ . . - - -. - - __. .-. . _. - . .- . . - . -- _ _ _ _ . .x . . _ , -

IMP Unit No. 1

• Valve Test List f80P-1-M-042 ,.

System: LhSI/ Retr Q1[1]

Re l l el' Valve Act. Req. or Valve Glay Dwg No. Size Act. Position or Te.glit_and f req. C. S. Desc ript ion Number 1}l I Coo rd . I pa_L fin.I lyps Typs peo rg iaii $arety Pass. f.L LI }l Im Lgy LI _Just. and Isotes QV001A 1 D-175041 A 12 CA M0 C Al O/C A Y CS CS C - LC Q1[11- RC Loop IC to 1-8701A C-3 CS-1 RHR Pump 1A.

D-351118 C-3 QV0018 1 D-175041 A 12 CA M0 C At 0/C A Y CS CS C -

LC Q1E11- RC Loop 1A to 1-8702A E-3 CS-1 CHR Pump 18.

D-351118 E-3 QVOO9A 2 D-175041 8 8 CA M0 C Al O A Y Q Q O - - -

RHR HX 1A to 1-8706A B-8 Cha rging D-351118 Pump Suction.

B-8 QV009B 2 D-175041 B 8 CA MO C Al O A Y Q Q O - - -

RHR HX 18 to 1-87068 C-8 Cha rging Pump D-351118 Suction.

D-8 QV015A 2 D-175041 C 3x4 SR S C N/A O/C A -

T - - - - -

RHR Pump 1-8708A C-4 Suction.

D-351118 G-4 QV015B 2 0-175041 C 3x4 SR S C N/A O/C A -

T - - - - -

Ri:R Pump 1-8708B [-4 Suction.

D-351118 E-4 QV016A 1 D-175041 A 12 CA M0 C Al O A Y CS CS O -

LA Q1E11- RC Loop IC to 1-87010 C-2 CS-1 RHR Pump 1A.

D-351118 C-2 QV016H 1 D-175041 A 1? CA MO C Al O A Y CS CS O -

LA Q1E11- RC Loop 1A to 1-8702B E-2 CS-1 RHR Pump *B.

D-351118 E-2 QV021A 1 D-175038/2 AC 6 CK S C N/A O A -

R -

ff -

LA Q1E11- RHR Pump Disc.

1-8973A E-1 RV-4 to SIS Injection D-351115/2 Q1E11- CL.

E-1 RV-7 QV0218 1 D-175038/2 AC 6 CK S C N/A 0 A -

R -

FF -

LA Q1E11- RHR Pump Disc.

1-89738 T-1 RV-4 to SIS Injection D-351115/2 QlE11- CL.

f-1 RV-7 03611 Ill-1-2-1 REV. 1 l

- . _ . , . . - , . . . _ _ , _ , , , _ _ _ . . - _ . _ ~ ~ , , . . . - . _ . _ . . . . - - _, m _ , _ _ _ . . - _ - - . - _ . . . , .

(NP Unit No. 1 Valve test List FNP-1-M-042

• System: LHSI/RHR Q1E11 He 1 ic f' Yalve Act. Req. or Valve Class Dwg. No. Size Act. Position or Teils and R eg, C. S. Description Number 111 [fo(Md fai fin.) Lype type No m faei Safety Pass, P1 M 11 pl3 [ky L[ JL and Notes QVO21C 1 D-175038/2 AC 6 CK S C N/A O A -

R -

IF -

LA Q1011- RHR Pump Disc.

1-8973C G-1 RV-4 to SIS Injection D-35111$/2 01011- CL.

G-1 RV-7 QVO23A 2 D-175038/2 0 10 CA MO O Al O/C A Y Q Q C 1-8888B G-3 RHR HX A to RCS CL isolation.

D-3*>1115/2 C-3 QVO238 2 D-175038/2 0 10 CA MO O Al O/C A Y Q Q C 1-8888A i-3 RHR HX B to RCS CL isolation.

D-351115/2 F-3 QVO24A 2 D-115038/2 B 10 GA MO O Al O/C A Y C 1-8681A l-4 Q Q - - -

RHR to RCS ItL Cross Connect.

D-351115/2 I-4 QVO248 2 D-115038/2 0 10 GA MO O Al O/C A Y Q Q C -

1-8881H G-4 RHR to RCS ItL Cross Connect.

D-351115/2 G-4 QVO?5A 2 D-175038/2 A 14 GA MO C Al O/C A -

Q Q O -

LJ Q1E11- Ctat. Sump to 1-8811A J-4 RV-1 RHR Pump 1A.

D-351115/2 J-4 OVH?SH 2 D-175038/? A 14 GA MO C Al O/C A Q 1-88118 Q O -

LJ Q1[11- Ctat. Sump to h-4 RV-1 RHR Pump 18.

D-351115/2 18 - 4 QVO26A 2 D-175038/2 A 14 CA MO C Al O A Y 1-8812A Q Q O -

LJ - Ctat. Sump to J-5 RHR Pump 1A.

D-351115/2 J-5 QVO26B 2 D-175038/2 A 14 GA MO C Al O A Y 1-8812B Q Q O -

LJ - Ctat. Sump to 14 - 5 RHR Pump 18.

D-351815/2 H-5 QVO27A 2 D-175038/2 B 14 GA MO O Al C A Y Q Q C 1-8809A F-10 RWSi to RHR Pump 1A.

D-351115/2 F-10 03618 Ill-1-2-2 REV. 1

. . -l FNP-1-M-042 RELIEF REQUEST Q1E11-RV-2 System: LHSI/RHR Valve: QV042A,QV0428 l

Category: AC Class:

2 Function: LHSI/RHR to RCS cold leg injection line check valves.

ASME Section XI Quarterly Test Requirements: Verify forward-flow operability ,;

quarterly or at cold shutdown (IWV-3521). ,.

I-Basis for Relief: Verification of forward-flow operability.

of these normally closed check valves can only be performed by injecting RER water into the RCS. During normal operation the low-pre.e.ure LHSI/RHR pumps cannot overcome the higher RCS operating pressure. Verification of full design flow rate operability cannot be done at cold shutdown due to back pressure from the reactor coolant system. Verification of full-flow operability can only be done at refueling with the RCS depressurized, the reactor vessel head removed, upper internals in place, and the refueling cavity at refueling level.

Alternate Testing: Valves will be forward-flow verified when the SI/LOSP test is being performed.

0361I III-1-2-8 REV. 1

FNP-1 -M-042 RELIEF REQUEST Q1E11-RV-3 System: LHSI/RHR Valve: QV051 A, QV05103 QV051C Category: C Class: 1 Function: HHSI/LHSI to RCS cold leg injection line check valves ASME Section XI Quarterly Test Requirements: Verify forward flow operability quarterly or at cold shutdown (IWV-3521)

Basis for Relief: Disassembly of these valves can only be done with the RCS depressurized and the reactor vessel level at mid-plane.

Alternate Testing: Valves will be disassembled on a staggered basis at refueling. l E

i

(

i l III-1-2-9 REY. 1 y - -- n,- - - - - - --, r----,.,y-y . , , - -., -----~~,-,.-.-,,---,-we ,--,e-.,,,-.-

..  ; )

RELIEF REQUEST i Q1 Ell-RV-4  :

System: LHSI/RHR Valve: QV021 A, QV0218, QV021C Category: AC Class: 1 ASME Section XI Quarterly Test Requirements: Verify forward flow operability (IWV-3522)

Basis for Relief: These 6-inch Yelan swing check valves are located in the low-head safety injection flow paths to the reactor coolant system cold legs. Individual line flow rate cannot be used to verify individual valve operability due to lack of instrumentation.

Alternate Testing: One of these valves will be disassembled and manually full stroke tested at each refueling on a staggered test basis. If stroke testing reveals that the valve is inoperable, the remaining valves will be disassembled.

III-1 10 REY. 1

FNP-1-M-042 RELIEF REQUEST Q1E11-RV-5 System: LHSI/RHR Valve: QV051 A, QV0518, QV051C Category: C 4

Class: 1 ASME Section XI Quarterly Test Requirements Verify forward flow operability (IWV-3522)

Basis for Relief: These 6-inch Velan swing check valves are located in the shared low-head and high-head safety injection '

Ifnes to the reactor coolant system cold legs.

Individual line flow rate cannot be used to verify individual valve operability due to lack of instrumentation.

Alternate Testing: One of these valves will be disassembled and manually full stroke tested at refueling on a staggered test basis. If stroke test reveals that ,

the valve is inoperable, the remaining valves will be disassembled.

4 111-1-2-11 REV. 1

FNP-1-M-042

. 1 i

RELIEF REQUEST .

Q1E11-RV-6 System: LHSI/RHR Valve: QVO32A, QVO32B, QV033A, QV033B Category: B Class: 2 Function: RHR HX. tube side discharge to SIS (QV032A,B) and RHR HX. bypass (QV033A,B).

ASME Section XI Quarterly Test Requirements: Measure valve stroke time.

Basis for Relief: Valves QV032A,B are the RHR heat exchanger outlet valves and QV033A,B are i

the RHR heat exchanger bypass valves.

Valves QV032A,B are normally open, fail open end valves QV033A,B are normclly closed, fail closed valves. This is the required valve alignment for the LHSI mode of operation. The RHR function of these valves is to control cooldown rate by regulating flow through the RHR heat exchangers. Both the flow control and bypass valves modulate to control the amount of heat removal by the RHR heat exchangers. Valves QVO32A,B modulate in response to a manually controlled position signal and valves QV033A,B automatically modulate to adjust bypass flow in response to the set position of valves QV032A,B. The only way to full stroke the valves is by manually adjusting the flow-control valve position control station through the full range of adjustment.

Alternate Testing: The valves will be tested quarterly by stroking each valve through its full range of travel.

0361I I I I- 1 12 REV. O

FNP-1-M-042 REl.tEF NEQUEST i Q1D1-RV-7 ,

System: LHSI/RHR Valve: QV021 A, QV021B, QV021C Category: AC Class: 1 Function: LHSI/RHR to RCS cold leg injection line check valves ASME Section XI Quarterly Test Requirements: Verify forward flow operability quarterly or at cold shutdown (IWY-3521)

Basis for Relief: Disassembly of these valves can only be done with the RCS depressurized and the reactor vessel level at mid-plane.

Alternate Testing: Valves will be disassembled on a staggered basis at refueling.

I I I-1 13 REY. 1

,1 FNP Unit No. 1 FNP-1-M-042 Valve Test List **

System: Sl/CVCS Q1E21 -

Retier Valve Act. Req. or ,

Valvo CJ_asa Dwg. No. Size Act. Position or Tests and Freg. C. S. Desc ri ption i Number J $.1 (Cold .1 QLL ( in. I hen hpe Norm faii Safety Pa s s . ,P_ l, M SJT. p.R_ isy .M Just. and Notes QVO72 2 0-175038/1 B 3 GA MO C AI O A Y CS CS O - -

Q1E21- HHSI Pump Reci r-  !

1-8884 J-6 RV-5 culation to RCS D-351115/1 Hot Legs.

J-6 .

QVO76A 1 D-175038/1 AC 6 C F. S C N/A C P - - - - -

LA -

Wa te r f rom Loop 1-8988A f-4 1 RHR HX to RCS D-351115/1 Hot Leg. See F-4 relier request Q1E21-RV-15.

QV0768 1 D-175038/1 AC 6 CK S C N/A C P - - - - -

LA -

Wa te r f rom Loop 1-89888 C-4 2 RHR HX to RCS D-351115/1 Hot Leg. See G-4 relier request Q1E21-RV-15.

QV077A 1 D-175038/1 AC 6 CK S C N/A 0 A -

R -

FF -

LA Q1E21- LHSI/RHR/HHSI to 1-8993A F-2 RV-11 RCS Hot Leg Loop D-351115/1 Q1E21- 1.

F-2 RV-14 QV077B 1 0-175038/1 AC 6 CL S C N/A 0 A -

R -

FF -

LA Q1021- LilSI/RHR/HHSI to 1-89938 G-2 RV-11 RCS Hot Leg Loop D-351115/1 Q1E21- 2.

G-2 RV-14 l QV077C 1 0-175038/1 AC 6 CL S C N/A 0 A -

R -

ff -

LA Q1E21- HHSI to RCS Hot 1-8993C G-1 RV-11 Leg Loop 3.

D-351115/1 Q1E21-G-1 RV-14 QVO78A 1 0-175038/1 C 2 CK S C N/A 0 A -

R -

FF - -

Q1E21- HHSI Pump Dis-1-8990A C-3 RV-6 charge to RCS D-351115/1 Q1E21- Hot Leg.

G-h RV-10 QV0788 1 0-175038/1 C 2 CK S C N/A O A -

R -

FF - -

Q1E21- HHSI Pump Dis-1-89908 C-3 RV-6 charge to RCS D-351115/1 Q1E21- Hot Leg.

c-3 RV-iO QV078C 1 0-175038/1 C 2 CK S C N/A O A -

R -

FF - -

Q1021- HHSI Pump Dis-1-8990C G-3 RV-6 charge to RCS D-351115/1 Q1E21- Hot Leg.

G-3 RV-10 03661 111-1-7-4 REV. 1

- .. ~ , . .

_n__

e O

FNP-1-M-042 RELIEF REQUEST QlE21-RV-4 System: SI/CVCS Valve: QV062A,QV0628,QV062C Category: C Class: 1 Function: Boron injection tank to RCS cold leg line check valves ASME Section XI Quarterly Test Requirements : Verify forward flow operability quarterly or at cold shutdown (IWY-3521)

Basis for Relief: The only possible way to verify full-flow operability of these check valves is by using the CVCS charging pump flow through the boron injection tank into the RCS cold legs. However, injecting water into the RCS through the boron injection tank during power operation exposes the safety injection nozzles to thennal shock and interrupts nomal charging and letdown. Injection of CYCS charging pump flow at cold shutdown would result in a low l temperature overpressurization of the RCS.

l Verification of full design flow rate operability l cannot he done at cold shutdown due to back pressure Verification of full flow operability from the RCS.

l can only be done at refueling with the RCS

depressurized, the reactor vessel head removed, upper internals in place, and the refueling cavity at refueling level.

Disassembly of these valves can only be done with the RCS depressurized and the reactor vessel level at mid-plane.

Alternate Testing: Forward flow operability will be verified by full flow test or by disassembly on a staggered basis at l refueling.

I i

111-1-7-19 REY. 1

FNP-1-M-042 l

RELIEF REQUEST l

l Q1E21-RV-6 l

l System: SI/CVCS Valve: QV066A, QV0668, QV066C, QV078A, QV0788, QV078C, QV079A, QV07%, QV079C Category: C Class: 1 Function: Safety injection to the RCS check valves ASME Section XI Quarterly Test .

Requirements: Verify forward flow operability quarterly or at cold shutdown (IWY-3521)

Basis for Relief: Verification of forward flow operability can only be perfomed by injecting charging water into the RCS.

The charging pumps have insufficient head to overcome nomal RCS~ operating pressure for a full flow test. Partial testing using the charging pumps would inject CVCS water which has bypassed the regenerative heat exchanger and would result in themal shock to the RCS piping. Verification of full design flow rate operability cannot be done at cold shutdown due to back pressure from the RCS.

j Verification of full flow operability can only be done at refueling with the RCS depressurized, the reactor vessei head removed, upper internals in place, and the refueling cavity at refueling level.

l Disassembly of these valves can only be done with the RCS depressurized and the reactor vessel level at mid-plane.

Alternate Testing: Forward flow operability will be verified by full flow test or by disassembly on a staggered basis at refueling.

111-1-7-21 REY. 1 l

l l

t

FNP-1-M-042 RELIEF REQUEST QlE21-RV-10 System: SI/CVCS Valve: QV062A, QV0628, QV062C, QV066A, QV0668, QV066C, QV078A, QV0788, QV078C, QV079A, QV0798, QV079C Category: C Class: 1 Function: Safety injection to the RCS check valve ASME Section XI Quarterly Test Requirements: Verify forward flow operability (IWV-3522) t Basis for Relief: These 2-inch Kerotest check valves are located in the parallel high head injection flow paths to the reactor coolant system. Individual line flow rate cannot be used to verify individual valve operability due to lack of instrumentation.

Alternate Testing: One of the valves for the reactor coolant system cold legs (QV078 and QV079) and one for the hot legs (QV062 and QV066) will be disassembled and visually inspected on a staggered test basis at each refueling. If visual inspection reveals that the valve is inoperable, the remaining valves in that group (hot leg or cold leg) will be disassembled and visually inspected.

111-1-7-25 REV. 1

FNP-1-M-042 RELIEF REQUEST Q1E21-RV-11 System: SI/CYCS Valve: QV077A, QV0778, QV077C Category: AC Class: 1 Function: HHSI to RCS hot leg injection line check valves ASME Section XI Quarterly Test Requirements: Verify forward flow operability quarterly or at cold shutdown (IWY-3521)

Basis for Relief: Disassembly of these valves can only be done with the RCS depressurized and the reactor vessel at mid-plane.

Alternate Testing: Valves will be disassembled on a staggered basis at refueling.

l L

t l

l 111-1-7-26 REY. 1 l

I l

ENP-1-I4-042 RELIEF REQUEST ,

1 QlE21-RV-12 System: SI/CVCS Valve: QV115A, QV115B, QV115C Category: AC Class: 2 Functions. CVCS seal injection to RCS pumps.

A'SME Section XI Quarterly Test Requirements: Verify forward flow operability.

Basis for Relief: These valves must remain open to allow operation of the reactor coolant pumps.

and these pumps are required to be operable by Technical Specifications prior to entry into mode 3. Technical Specification 3.4.7.2.e requires a total

- flow of no more than 31 gpm through all three valves. Administrative controls require a flow of at least 6.7 gpm through each valve.

Alternate Testing: The total flow of less than 31 gpm will be monitored every 31 days per Technical Specifications. If flow drops below 6.7 gpm a plant main control board alarm l

. is actuated and flow is reestablished via annunciator response procedures.

i 1

1 III-1-7-27 REV. 0 0366I

n . -

FNP-1-M-042

, RELIEF REQUEST QlE21-RV-13 i

System: SI/CVCS Valve: QV121A, QV121B, QV121C Category: C

. Class: 2 Function: Charging pump min, flow line check valves.

ASME Section XI Quarterly Test Requirements: Verify forward flow operability.

Basis for Relief: In verifying full forward flow operability would require measuring the flow rate through each of the charging pump minimum flow lines. Neither the individual minimum flow lines nor the common header is instrumented to measure flow rate.

Alternate Testing: '

One of these valves will be disassembled and inspected at refueling on a staggered basis. If disassembly reveals that the valve is inoperable, the remaining valves will be disassembled.

1 0366I I I I 7 - 28 REV. O

.. *l FNP-1-H-042 RELIEF REQUEST QlE21-RY-14 System: SI/CVCS Valve: QV077A, QV0778, QV077C Category: AC Class: 1 Function: HHSI to RCS hot leg injection line check valves ASME Section XI Quarterly Test Requirements: Verify forward flow operability (IWY-3522)

Basis for Relief: These 6-inch Yelan swing check valves are located in the safety injection lines to the reactor coolant system hot legs. Individual line flow rate cannot be used to verify valve operability due to lack of instrumentation.

Alternate Testing: One of these valves will be disassembled and manually full stroke tested at each refueling on a staggered test basis. If stroke testing reveals that the valve is inoperable, the remaining valves will be disassembled. .

111-1-7-29 REY. 1 1

. - . _ - . - - . -,- . . . - - .- . - . - - . - . - - - -, - - . - . - - . .