A06401, Forwards Responses to Questions on Pumps & Valves Inservice Testing Program,Per 870602 & 03 Meetings
| ML20235N664 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/10/1987 |
| From: | Mroczka E NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| A06401, A6401, NUDOCS 8707200168 | |
| Download: ML20235N664 (172) | |
Text
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y ,a NORTHEAST UTILITIES o neroi Omc . . seicen street. s ,iin connecticut 1 .im v ss o.wis ucm.c cw ' P.O. BOX 270
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H ARTFORD. CONNECTICUT 06141-0270 k k J U$$[,72."7,'C,,', (203) 665-5000 July 10,1987 Docket No. 50-423 A06401 Re: 10CFR50.55a(g)
U.S. Nuclear Regulatory Commission l Attn: Document Control Desk
- Washington, D.C. 20555
References:
(1) 3. F. Opeka letter to B. 3. Youngblood, Inservice Testing Program for Pumps and Valves, dated October 1,1985.
(2) 3. F. Opeka letter to V. S. Noonan, inservice Testing (IST)
- j. Program for Pumps and Valves, dated June 25,1986.
(3) E. L. Doolittle letter to E. 3. Mroczka, Pumps and Valves Inservice Testing Program, dated March 9,1987.
Gentlemen:
Millstone Nuclear Power Station, Unit No. 3 Responses to the Staff's Questions on the Pumps and Valves Inservice Testing (IST) Program In Reference (1), Northeast Nuclear Energy Company (NNECO) submitted Revision 'O' of the Millstone Unit No. 3 program for IST of pumps and valves. In Reference (2), NNECO transmitted Revision 1 of the IST program for pumps and valves which included the updated surveillance intervals to reflect plant Technical Specifications. In Reference (3), the Staff provided their questions and comments on the IST program for pumps and valves. A meeting was held between the Staff, their contractor EG&G, and NNECO representatives at the Millstone site on June 2, and 3,1987, to discuss our responses to their questions (Reference 3). The Staff indicated that their concerns were satisfactorily resolved and it was agreed that NNECO will transmit a letter to the NRC providing a written response on each question (Reference (3)) by July 10, 1987. Attachment I provides those l responses. In addition, a copy of the responses has been forwarded to the NRC's contractor, Mr. C. Ransom, EG&G, Idaho.
If there are any questions regarding this submittal, please contact our licensing representative directly.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY ffY E. 3.'7Foczka /
/
Seniof Vice President cc: W. T. Russell, Region I Administrator Q R. L. Ferguson, NRC Project Manager, Millstone Unit No. 3
- 3. T. Shediosky, Resident inspector, Millstone Unit No. 3 g{\
8707200168 070710 PDR ADOCK 05000423 P
l Docket No. 50-423 A06401 j j
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Millstone Unit No. 3 Responses to Questions and Comments on the IST Program for Pumps and Valves 1
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Millstone 3 Inservice Testing Program p General Questions and Comments 1
A1. Section 4.3.7- of the Millstone Unit Ne. 3 IST program does not agree with Section XI, Paragraph IWV-3416. The code requires valves to be exercised within 30 days prior to return of the system to operable status; why can't this code requirement be met?
Response
The Millstone Unit No. 3 (MP3) IST Manual Section 4.3.7 has been updated to add
" prior." (See attached.)
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4.3.3 Valves or their control systems which are replaced, repaired, or have undergone maintenance which could affect their operation shall be tested to the extent necessary to demonstrate that the performance parameters which could have been affected are within acceptable limits.
4.3.4 Valves with remote position indicators shall be observed at least once every two years to verify that valve operation is accurately indicated.
4.3.5 Power-operated valves shall be checked for stroke time each time they are full-stroke exercised to meet the requirements of this program.
4.3.6 When practical, valves with fail-safe actuators shall be tested for proper actuation upon loss of power each time the valve is exercised to meet the require-ments of this program. If the valve can only be part l stroked during operation, the fail-safe mechanism shall be tested when the valve is full stroke tested during a cold shutdown.
4.3.7 Valves in systems that have been declared inoperable, or are not required to be operable, do not need to be exercised in accordance with the normal schedule.
These valves, however, must be exercised within 30 days prior to returning the system to service and the test schedule resumed as required by Paragraph IWV-3416 of the Code.
4.3.8 Valves which operate at a frequency which meets or exceeds the required test frequency need not be additionally exercised to meet the requirements of this program, provided that the required observations are made, analyzed, and the resultant data recorded at the specified intervals.
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i . 9 Millstone 3 Inservice Testing Program-General Questions and Comments A2. Are all valves that are Appendix J, Type C, leak-rate tested included in the Millstone Unit No. 3 IST program and categorized "A" or "AC?" '
. Response Yes, all Appendix 3 Type C valves are categorized "A" or "AC." In addition any changes in the Appendix 3 program will be reflected as IST program changes.
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1 Millstone 3 Inservice Testing Program General Questions and Comments i
j A3. The N.RC has concluded - that the applicable leak test procedures and requirements for containment isolation valves are determined' by 10CFR50, Appendix 3. Relief from paragraphs IWV-3421 through 3425 for containment isolation valves presents no safety problem since the intent of the IWV-3421 -through 3425 is -met. by Appendix 3 requirements, however, the licensee shall comply with Paragraphs IWV-3426 and 3427,
Response
NNECO will comply with the Staff's position on leak testing containment isolation valves. Please refer to Relief Request R-21 (attached).
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1 LRelief' Request: -R <
Valves: 'All'10CFR50 Appendix J Tested Containment Isolation Valves that serve"only a-containment isolation functio'n.
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. Ca t' ego ry : A.and.AC-Code Class: 2 Function: Containment:lsolation Test Requirements: IWV-3421;through.IWV-3425 Basis for Relief: Leak test procedures and requirements for.
containm'ent isolation valves are determined by' 10CFR50 Appendix J. Relief from paragraphs
O IWV-3421 through 3425 (1983 Edition through-Summer 1983 Addenda) presents no safety problem since the intent of these paragraphs is met by' Appendix J requirements.
Alternate Testing: All 10CFR50 Appendix J tested valves that serve only a containment isolation function shall be tested'in-accordance with the requirements'of Appendix J.
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6 Millstone 3 Inservice Testing Program General Questions and Comments A4. The code permits valves to be exercised during cold shutdowns where it is not practical to exercise them during plant operation and these valves are specifically identified by the licensee and are full-stroke exercised during cold shutdowns. The NRC Staff requires that the licensee provide a technical justification for each valve that cannot be exercised quarterly during power operations that clearly explains the difficulties or hazards encountered during that testing. The NRC Staff will then verify that it is not practical to exercise those valves and that the testing should be performed during cold shutdowns.
Response
Valves that cannot be full stroked during plant operations, but are to be full-stroke exercised during cold shutdowns are provided with their relief requests in Section 7.0 (deferred tests) in the MP3 IST Manual.
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7 Millstone 3 Inservice Testing Program General Questions and Comments l
AS. What are the bases used,to assign .the limiting values of full-stroke time for the power-operated valves in the Millstone Unit No. 3 IST program?
Provide the limiting values of full-stroke time for those valves that have NSR(1)in the maximum stroke time column of Table 5.r. s
Response
The Active Valve Response Times Document (NM-027-ALL) provides the criteria for selection of power-operated active valves and maximum allowable full-stroke times for those active valves.
For. all no-stroke time required (NSR) designated valves the baseline valve operating time value data is doubled to provide a maximum limiting stroke time.
Upon exceeding this value the corrective action will be taken in accordance with
'IWV 3417B. (Please refer to Relief Request 27.)
We will review the limiting values of valve stroke time for all non-NSR -
designated valves. Section 5.4 of the IST Manual will be revised to address the actions to be taken upon exceeding the stroke time limits established during this review.
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All power operated valves listed in the valve lists.
Component' Identification: ASHE Code Classi 1,-2, 3' E IWV 2200 Valve Category: A, B y1 Valve Functioni e, 3 Ai(',4dentified in' valves -listw . j
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Test Requirements: Paragraph -IWV-3417 "(a) If, for power operated valves, an increase in stroke time of 25% or more from the previous test for 3'
valves with full-stroke times' greater than 10~ seconds or 50% or more for valves with full-stroke times less than or equal to 10'secondsisobterhed,testfrequency i shall be increased to once each month ~until !
corrective action is taken, at which time i the original test frequency shall bc )
e i l resumed. In any case, any abnormality or ,
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erratic action shall be reported.
I Code Relier. Relief is requested from comparing present i stroke times to stroke times from the J
previous test, i
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Basis for Relief: Use of the " previous test" stroke time does y not adequately identify slow degradation of valve performance. For example, repeated l increases in stroke time of 15 to 24 i percent would not require that the valve be considered in " Alert", with attendant additional investigation and testing. The proposed alternative acceptance criteria would identify such valves and require that t they be formally evaluated for acceptability or declared inoperable. In instances where the evaluation does not result in a determination of inoperability additional or increased frequency testing may be specified to aid in evaluating valve performance. This criteria provides increased assurance that degrading valves are promptly identified and that such degradation is promptly evaluated for its impact on valve operability.
. Proposed Alternative: Test results shall be compared to the reference values of stroke time for each valve.
- a. Valves with reference stroke times
- greater than 10 seconds shall exhibit no more than a 125% change in stroke time when compared to the reference value.
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-b. Valves with. reference stroke: times less than 10 seconds shall{ exhibit no more than a 50% or 1 second'(which ever is greater). change in stroke time when compared to the reference value.
- c. Valves with referer.ce stroke times of less than 2 seconds shall not exhibit a stroke time in excess of 2 seconds.
Valves with measured stroke times which do not meet the above acceptance criteria
' shall be immediately retested (or' declared inoperable).
If retested and the second set of data also does not meet the acceptance criteria the data shall be analyzed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> to verify that the new stroke time represents acceptable valve operation, or the. valve shall be' declared inoperable. When'the evaluation indicates the deviation may be caused by degradation of the valve or its operator additional testing may be specified to confirm or trend the degradation. If trended test results indicate the valve will exceed the limiting value of stroke time prior to the next test or that valve operation fa unreliable the valve shall be declared inoperable. The evaluation shall be documented in the record of the tests.
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acceptance criteria, the cause of the- ;
initial deviation shall be analyzed and the results documented in the record of tests.
Valves for which measured stroke times exceed limiting values for stroke times shall be immediately declared inoperable Valves which are declared inoperable shall!
be readjusted, repaired, or replaced prior to returning the valve to service. A test demonstrating satisfactory valve performance shall be performed prior to returning the valve to service.
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l Millstone 3 Inservice Testing Program General Questions and Comments i
A6. When flow through a check valve is used to indicate a full-stroke exercise of the valve disk, the NRC Staff position is that verification of the maximum flow rate identified in any of the plant's safety analyses through the valve would be an adequate demonstration of the full-stroke requirement. Any flow rate less than this will be considered partial- l stroke exercising unless it can be shown (by some means such as measurement of the differential pressure across the valve), that the check valve's disk ' position at the lower flow rate would permit maximum required flow through the valve. Does the Millstone Unit No. 3 IST program conform to this Staff position?
Response
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, We interpret this to mean the minimum acceptable flow required by the plant's j i
l safety analyses for that accident scenario requiring the largest flow rate is to be !
met for this valve to perforrn its intended function.
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Millstone 3 Inservice Testing Program General Questions and Comments I A7. The relief request and cold shutdown justification bases should indicate the negative consequences that make testing at the code required ;
frequency impractical such as endangering personnel, damaging equipment '
or resulting is a plant shutdown.
R_esponse l
This item is addressed for each individual relief request where specific questions are asked addressing this lack of information.
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W Reactor Coolant System Bl. How are valves 3RCS-V31, 32, 71,107, and 146 verified to full stroke during cold shutdown testing?
Response
1.
Valves 3RCS*V31 and V32 will be deleted from the IST program as they do not perform a safety-related function. (Refer to the response to Question B.2.)
- 2. Valves 3RCS*V71, V107,146, and RCS*V30 (SIL Cold Leg Injection from Accumulators Lines) have been reevaluated and will be deleted from Relief Request CSR-1. These valves will be added to Relief Request R - 24, which has been revised to partia!!y disassemble, inspect and manually exercise on a staggered sampling basis during each refueling outage. '
Relief Request R-3 has been revised to include valves 3SIL*15,17,19, and 21 for disassembly.
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Valves: -3RCS*V30, V71, V107, V146 Categori: AC
_ Code Class: 1 Function: Pressure isolation between the reactor coolant system and the safety injection accumulator tanks.
Test Requirements: Exercise (full stroke) quarterly.
Basis for Relief: These valves cannot be full stroke or part stroke-1 exercised during operation since no flow path exists-to accomplish such a test. The valves cannot be
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full stroke or part stroke exercised during a cold shutdown because this would result in a-complete or l
partial discharge of the tanks into the reactor
, vessel which. could ' resulti int low'tiidifsFature l
overpressurization'of the:RCS.
Alternate Testing: These valves will be partially disassembled, inspected-and manually exercised on a staggered sampling basis each refueling outage. During each disassembly, l
the valve internals will be inspected for structural j
soundness (no loose or corroded parts). In the event that a disassembled valve's full-stroke capability is questionable, additional valves will be disassembled until one hundred percent (100%) of the valves identified in this group have been disassembled and inspected.
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-Valves: 3SIL*V15, V17, V19, V21 Category: AC Code Class: 1 Function: -Pressure isolation between the reactor coolant' system and the safety injection accumulator tanks.
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~ Test Requirements: Exercise (full stroke) quarterly.
Basis for Relief: These valves cannot be full stroke or part stroke exercised during operation since no flow path exists to accomplish such a test. .The valves cannot be full stroke or part stroke exercised during a gold shutdown because this would result in a complete or partial discharge of the tanks into the reactor result in low tem vessel which could ~~ ameyy;.gynm,.perature ..
~ overpressurization" of: the; RCS.
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Reactor Coolant System B2. What is the safety-related function of valves 3RCS-V31,32,147, and 148?
If these valves perform a safety-related function in the closed position, how are they individually verified to close? Do these valves perform a pressure isolation function?
M' Response These valves do not perform a safety-related function. Therefore, these valves will be deleted from the MP3 IST Manual. (See attached). The valves that provide a safety-related function (i.e., containment isolation) are 3CHS*MV8105 and 3CHS*V58. Relief Request CSR-2 which covers valves 3RCS*V31, V32, V147, and V148 has been deleted.
,4 85 B2-1
to Relief Request: CSR-2 DELETED Valves:
Category:
Code Class:
Function:
Test Requirements:
Basis for Relief:
Alternate Testing:
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- - - - - - - - - 0 - 5
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i
'21
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l i
Reactor Coolant Pump Seals ;
C1. Provide a more deta' lled technical justification for not full-stroke exercising valves 3CHS-V393, 433, 466, and 500 during cold shutdowns (Relief Request R-17 does not address the consequences of exercising these valves).
' Response 1
Valves 3CHS*V393, 433, 466, and 500 are included in the IST program and full-stroke exercised at the refueling outage. Relief . Request R-17.. provides justification for not full-stroke exercising these valves during cold shutdowns.
1 i
~1 1
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i i
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23 l
Reliev Request: R-17 Valves: 3CHS*V393, V433, V466, V500, V532, V533 Category: A Code Class: 2 Function: Seal Water Return Containment Isolation Valve Test Requirements Exercise closed (full stroke) quarterly.
Basis for Relief: Plant operating procedures require #1 seal return flow be maintained whenever (RCS) pressure exceeds 100 psig. Isolating these valves during plant operation, startup, or cold shutdowns in which the RCS is pressurized could damage the RCP seals.
Alternate Testing: These valves will be full stroke exercised during l refueling when the RCS is depressurized to less than 100 psig.
NOTE: Full-stroke exercising of the seal return valves will be performed during cold shutdown when the RCS is depressurized (i.e., for cold shutdowns which depressurize the RCS to less than 100 psig).
NOTE: Full stroke exercising of the r. cal supply valves will be done on cold shutdowns in which the RCS is drained down to a level which uncovers the RCP seals (i.e.,
refueling or cold shutdowns which drair the RCS).
Cl-2
.____._._______J
- Ly Reactor Coolant Pump Seals
' C2. Provide a more detailed technical justification for not' full-stroke exercising valves 3CHS-V394, 434, 467, and 301' during cold shutdowns (Relief Request R-2 does not address the consequences of exercising these valves during cold shutdowns).
Response
Relief Request R-2 provides a more detailed technical justification for not full-stroke exercising these valves during cold shutdowns.
l C2-1
, d-Relief Request: R-2 Valves: 3CHS*V58, V394, V434', V467, V501
-Category: AC Code Class: 2 Function: Containment Isolation Valve f.
Test Requirement's: Exercise closed (full stroke) quarterly.
Basis for Relief: The function of these valves is to provide containment isolation upon cessation of normal charging or seal flow. The seal supply valves cannot be tested at power or cold shutdowns unless the RCS is depressurized, otherwise damage to the RCP seals may occur. Cold shutdowns which depressurize the RCS do not have a motive. force to verify the valves are closed. During cold shutdown there is no flow path available to pressurize the downstream side of the normal charging valve to demonstrate that the valve is closed when normal charging flow is secured, since it is isolated from the RCS by two check valves in series.
Alternate Testing: These valves are subject to local leak rate testing every two years as required by 10CFR50, Appendix J.
This test verifies their adequacy for containment isolation and requires that the valves be shut to successfully complete the test.
c2-2
L4 l Chemical and Volume Control System j 1
l DI. Provide a more detailed technical justification for not full-stroke l exercising valves 3CHS-V5 and 802 quarterly during power operations.
Response J.
l l
Refer to the revised Relief Request CSR-5. j i
i Dl-1
M Pelief Request: CSR-5 Valves: 3CHS*V5, V56, V57, V802 Category: A and B Code Class: 2 Function: Containment Isolation Valves Test Requirements: Exercise (full stroke) quarterly Basis for Relief: The charging and letdown subsystems of the CVCS is to establish a programmed water level in the pressurizer to maintain proper reactor coolant inventory and proper chemical control of the Reactor Coolant System. Full stroking exercising these valves on a quarterly basis during power operation could cause a loss of pressurizer level control and possibly a reactor trip. The plant is designed with a limited number of letdown isolation thermal cycles. As letdown is disrupted, the charging water to the RCS is no longer heated up and causes a thermal cycle on the hot path to the RCS.
Alternate Testing These valver will be full stroke tested during cold shutdowns.
D1-2
za .
Chemical and Volume Control System
- D2. - Provide a more detailed technical ' justification for not . full-stroke exercising valves 3CHS-V40 and 41 quarterly during power operations.
. Response Refer to the revised Relief Request CSR-6.
l i
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4 D2-1 i
.---_-.--------.---------_____a
Q . t.
k I
i Relief Request: [CSR-6 Valves: 23CHS*V40, V41 0 . Ca tego'ry: B
' Code Class: '2
. Function: -Isolation of the Volume Control Tank from the suction
. side of the, charging pumps.
- Test Requirements': Exercise'(full stroke) quarterly.
Basis for Rel'ief: Stroke-testing;of these valves during' power operation would result in a disruption of normal charging. flow and cause loss of suction pressure to an operating-charging pump. .This could give rise ~to a loss of-
.e-pressurizer level control-resulting in'a plant [ff: }:
i trip. Use of the alternate pump suction source'may.
result with injecting high' concentration of boric acid into the RCS.
' Alternate Testing: These valves will be full stroke tested during cold
~s hutdowns.
i 1
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l 1 1
L 1 U i 1
D2-1
30 ;
Chemical and Volume Control System ,
D3. Provide. a more . detailed technical justification for not full-stroke exercising valves 3CHS-V46,47 and 48 quarterly during power operations and during cold shutdowns.
- Response See the revised Relief Request R-18 for additional justification.
i 1
D3-1 1
M
'R '
Relief Request:
' Valves: 3CHS*V46,.V47, V48'
> Category:. .C
!ie : Code Class: 2 Function: To prevent backflow through the associated charging:
pump when secured and at least one other charging-pump'is operating..
-Test Requirements: Exercise open (full stroke) quarterly.
1 Basis'for Relief: The charging pumps do not generate sufficient flow (design flow) to full stroke.the valves during normal chiWin~g"operst'iiiis~^ThesE" valves"Eannot:be exercised;during'shstdowns'sinceEinjection flow could : re sultyin :: low;..tempe rature ~ove rat es s uriza tion
- ?TgT[fRCS t >
Alternate Testing: These valves will be quarterly part stroked jand full stroked exercised by subjecting them to full design flow during refueling outages.
1 l
D3-2
31- !
.a Chemical and Volume Control System D 4. - Provide a more detailed technical justification for not full-stroke exercising valves 3CHS-V56 and 57 quarterly during power operations.
Response !
Cold shutdown Relief Request CSR-7 has been deleted. These valves have been added to Relief Request CSR-5 which provides a rnore detailed justification for not full-stroke exercising. These valves are included on the attached Relief Request CSR-5. I i
4 1
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. D4-1 k[
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33 Q.
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R111ef Request: CSR-7 DELETED ([ ,
f-62.,'..
Velves:
Cetegory:
Code Class:
Function:
Test Requirements:
Basis for Relief:
Alternate Testing:
I i
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3\f Relief Request: CSR-5 Valves: 3CHS*V5, V56, V57, V802 I
I Category: A and B j Code Class: 2 Function: Containment Isolation Valves /
Charging Flow Controller Isolation Test Requirements: Exercise (full stroke) quarterly Basis for_ Relief: The charging and letdown subsystems of the CVCS is to establish a programmed water level in the pressurizer to msintain proper reactor coolant inventory and proper chemical control of the Re. actor Coolant System. Full stroking exercising these valves on a quarterly basis during power operation could cause a loss of pressurizer level control and possibly a reactor trip. The plant is designed with a limited number of letdown isolation thermal cycles. As letdown is disrupted, the charging water to the RCS is no longer heated up and causes a thermal cycle on the hot path to the RCS.
Alternate Testing These valves will be full stroke tested during cold shutdowns.
k
(
P4-3
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39 4
' Chemical and Volume Control System D5. Provide a more detailed technical justification for not full-stroke exercising valve 3CHS-V58 quarterly during power operations and during cold shutdowns.
Response
Refer to the revised Relief Request R-2.
l l
DS-1
. . 39
, Relief Request: R-2 Valves: 3CHS*V58, V394, V434, V467, V501 Catego ry: AC Code Class: 2 Function: Containment Isolation Valve Test Requirements: Exercise closed (full stroke) quarterly.
Basis for Relief: The function of these valves is to provide containment isolation upon cessation of normal charging or seal flow. The seal supply valves cannot be tested at power or cold shutdowns unless the RCS is depressurized, otherwise damage to the RCP seals may occur. Cold shutdowns which depressurize the RCS do not have a motive force to verify the valves are closed. During cold shutdown there is no flow path available to pressurize the downstream side of the normal charging valve to demonstrate that the valve is closed when normal charging flow is secured, since it is isolated from the RCS by two check valves in series.
Alternate Testing: These valves are subject to local leak rate testing every two years as required by 10CFR50, Appendix J.
This test verifies their adequacy for containment isolation and requiras that the valves be shut to successfully complete the test.
D5-2
l l
.,- , Ho' i
Chemical and Volurne Control System D6. Provide a more detailed technical justification for not full-stroke exercising valves 3CHS-V333, 710, 711, and 712 quarterly during power.
operations.
- Response Relief Request CSR-8 has been revised to include a more detailed technical justification for not full-stroke exercising these values quarterly during power operations.
l 4
l D6-1
.M j.
r Relief Request: CSR-8 Valves: 3CHS*V333, V710, V711, V712 Category: C and B Code Class: 3-
-Function: Provide a gravity boration path Test Requirements: Exercise (full stroke) quarterly Basis for Relief: In order to line up the charging system to permit exercising of these valves during power' operation, it would be necessary to interrupt normal charging and letdown flow. Additionally, testing of these valves at power would result in uncontrolled.
boration of the Reactor Coolant system with the reactor critical. A rapid boration would introduce a large amount'of negative reactivity to the RCS causing a plant shutdown.
Alternate Testing: These valves will be full stroke tested during cold shutdowns when the reactor is shutdown.
D6-2
)
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Chemical and Volume Control System _
D7. Provide the P&lD that shows valves 3CHS-V487,489 and 489. ,
Response
This P&lD was provided at the June 2,1987, meeting. _
I l
l l
D7-1
l .. . .
Chemical and Volume Control System D8. Provide a more detalled technical justification for not full-stroke
, exercising valves 3CHS-V532 and 533 quarterly during power operations and during cold shutdowns.
t-
Response
It has been redetermined that the aforementioned valves can only be full stroked i during a refueling outage for reasons stated on the revised Relief Request R-17.
l D8-1
- > . c o
. .- A/7 Ie '
Reliev Request: R-17 h - Valves: 3CHS*V393, V433, V466, V500, V532, V533
, Category: A1 L
Code Class: 2'
!l Function: Seal Water Return Containment Isolation Valve 2
- Test Requirements Exercise closed (full stroke) quarterly.
Basis for Relief: Plant operating procedures require #1 seal return flow be maintained whenever (RCS) pressure exceeds 100 psig. Isolating these valves during plant operation, startup, or cold shutdowns in which the
, RCS is pressurized could damage the RCP seals.
Alternate Testing: These valves will be full stroke exercised during refueling'when the RCS is depressurized to less than 100 psig.
NOTE: Full-stroke exercising of the seal return valves will be performed during cold shutdown-when the RCS is depressurized (i.e., for cold shutdowns which depressurize the RCS ,
to less than 100 psig). "
'l NOTE: Full stroke exercising of the seal supply valves will be done on cold shutdowns in j which the RCS is drained down to a level l which uncovers the RCP seals (i.e., I refueling or cold shutdowns which drain the RCS). !
D8-2 l
)
qs Chemical and Volume Control System D9. Review the safety functions of valve 3CHS-V42 (P&lD 25212-26904 Sh. I location 3-9) to determine if it should be included in the IST program and tested to the code requirements.
Response
l This valve does not perform a safety function and does not meet IWV1100 and will not be included into the MP3 IST Manual. Valves 3CHS*V40 and V41 provide isolation (3CHS*LCVil2D and C) these are included in the IST Manual.
l 1
09-1
Qq w0- ,;
Chemical and Volume Control System DIO. Do valves 3CCE-V9 and .21 (P&ID ' 25212-26905 locations E-2 and C-2) have a. required fall-safe position? If so, they are active valves and should be included in the IST program and tested to the code requirements.
Response
Valves 3CCE-19 and 21 will be included in the IST program and will be full-stroke exercised quarterly.
l l
l D10-1 t _ _ _ _ . _ _ _
- oog:.e
I ei I ~
ms C ui E cv P oe S DR S
m FT pe ES mt I E us5 LU P y0 EQ S9 RE g 6 R n g2 i n-gi2 rl 1 a o2 h o5 .
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O 8 8 2 5 1 9 2 5 C - - - -
m - - -
e n F G C E D G F D t i s w y a S r D D EG RN I I UT S STTI STTI STTI S STTI SfTI STTI QS F FNFP FMFP FNFP F FMI P FP f FP FMFP EE RT D
f, OI 3 : Q Q I Q I Q I Q Q I Q I Q I ER B B B B B B TG TE I N P NI UT S
TEM NTA I R R OEG NO PCO EOT I R TI A s s s s s s EVP OTC - e e e - e e e NR MI Y Y Y Y Y Y OE TS ESDI RON SN PI LI I
I M
E RE TD I O - C O C - C 0 C I M F F F F F F A
F d d e e r s r s N N o o o o O/O l / l /
I LI d C d d d d C d d d
_ TAT e/- /e e /e e/- / e e / e
. I MC s nn ns s n ns s nn ns s n ns
_ SRN oee e o oe eo oee eo oe eo OOU l pp pl l p pl l pp pl l p pl PNF COO OC CO OC COO OC CO OC N
O I
T r r r r r r A - i i i - i i i U A A A A A A T
C A
E .
P K. .
K .
Y H A. L A. H A L. A.
T C G G G C G G G YS GS TA EAL 3 3 3 3 3 3 3 3 ZCC C 8 B B C B B B I 2 2 2 2 2 2 2 2 SEE DD OO CC l 3 5 1 3 ER I 3 9 i 1 1 2 2 VE V VA V VA V VB V VB LB - - 0 - A - 6 - - 0 B - 6 AM E E3 E7 E2 E E3 E7 E2 VU C C3 C C3 C - C - C - C -
N C CV C - CV C CV C - CV
- - 0 V - 0 - - O - V - 0 3 3A 3T 3A 3 3A 3T 3A
)
3Oh l ,!
l' I'
SI Chemical and Volume Control System Dil. Would failure of valve 3CHS-V269 closed during quarterly stroke testing render an entire safety system inoperable?
Response
No. Failure of valve 3CHS*V269 closed during a quarterly stroke test will not render the safety system inoperable.
Dil-1
j; 1:_
5' L Chemical and Volume Control System l
D12. Review the safety-related function of valves 3CHS-Y294, 296 and 320 (P&lD 25212-26904 Sh. 3 locations 3-5, 3-6 and F-4) to determine if they should be included in the IST program.
Response
Yes. These valves should be included into the IST Manual. Valves 3CHS*V294, 296 and valves 319 will be full stroked open quarterly. 3CHS*V320 can only be full stroked at cold shutdown. (See the attached Relief Request CSR-23.)
D12-1
SI 0 n 0 n
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.e NQ P P EE r r NN a MR e- e -
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FT ES d m I E 3 ne4 LU 5 2 at 0 EQ - -
s9 RE R 2 R l y6 R S - S aS2 C R C c -
il 2 mo1 er2 h t5 . ) ) ) ) ) ) ) )
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F sl w yoa SV r D D EG RN I I UT STI T ST S S S STI S S STI S QS FNPL FL F F F FNP F F FMP F EE RT _
D TO 3 SI S Q Q Q ER C I
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B Q I Q Q S I S TG TE B C B C I N P NI UT S
TEM INTA R R _
OEG NO _
PCO EOT I R TI A s s s s EVP OTC e - - - - e e - e -
NR MI I Y Y Y OE ESD Y TS RON SN PI LI L
I M
E IRr I D LO - - - - - - - - - -
I M
_ A
_ F N N d d d O/O r/n r/n r/n / / / /
_ I LI d d od ad od ad od ad d d d d TAT /e /e e e d e e e e /e e e e e
_ I MC ns ns ns ns ns ns ns ns ns s n s n s n s n SRN eo eo OOU pl pl eoeo pl pl eoeo eoeo eo oe oe oe oe pl pl pl pl pl l p l p l p l p PNF OC OC OCOC OCOC OCOC OC CO CO CO CO N
O I r r r T o o o A t - - - - t - t -
U o o o T M M M C
A S . .
? K. K.
Y A K. K K. K. .
K H H H H L. H H L H T C C C C C C C C G C TS GS TA EAL 2 2 2 2 2 3 3 3 2 2 ZCC A C C C C B C C B C I 3 A 2 2 2 2 2 2 2 2 SEE 3 DD OO CC 2 3 4 9 4 6 9 0 7 8 6 6 6 6 9 ER 5 5 9 1 2 2 2 2 2 2 2 3 3 VE V5 V V V V V0 V V V4 V LB - 0 - - - - - 1 - - - 0 AM S1 S SB SC SA S1 S S S1 S VU t i8 H1 H0 H0 H0 H8 H H H8 H N C - C8 C8 C8 C8 C - C C C - C
- V - 3 - 4 - 4 4 - V - - - V -
3M 38 38 38 38 3M 3 3 3H 3 3yu
! i
b Relief Request: CSR-23 Valves: 3CHS*V320 Category: C Code Class: 2 l
Function: Provide a gravity boration path 7
Tpst Requirements: Exercise (full stroke) quarterly Basis for Relief: Testing of this valve from the closed to open position during power operation would result in boration of the Reactor Coolant System possibly causing a plant shutdown.
Alternate Testing: This valve will be full stroke tested during cold shutdown.
i l
l l
D12-3 l ._. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ -
s5 . ..
l Fuel Pool Cooling System El. Review the safety function of valves 3SFC-V3 and 6 (P&ID 25212-26911 ,=_
locations G-9 and G-10) to determine if they should be included in the IST program and tested to the code requirements.
Response
Yes. These valves have been evaluated as active valves per IWV2100 and will be ----
added to the IST Manual. (See attached.)
u a
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s . . _
0 -
e e e e l S v v v v _
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no CA t t t t ei ms I sx- sx. sz- sx-C ei ei ei ei ui E td) td) td) td) cv P ne ne ne ne oe~ .S kev kev k ev k ev DR a pl a pl a pl epa a pl epa epa epa LAv LAv LAv LAv S
m FT
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TO 3 SI Q Q I I I I ER B B B B TG TE I N P NI UT S
TEM NTA I R R OEG NO PCO EOT I R TI A EVP OTC - - - - - -
NR MI I OE ESD TS RON SN PI LI L
I M
E RE UD LO - - - - - -
I M A
F N N O/O / / / / / /
I LI d d ddd ddd ddd ddd TAT e e eee eee eee eee I MC sn sn k s s k ss k s s k s s coo SRN oe oe coo coo coo OOU l p l p ol l oll oll oll PNF CO CO LCC LCC LCc LCc N
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AM C C C C C C VU F F F F F F N S S S S S S 3 3 3 3 3 3 Y"
57 Fuel Pool Cooling System ;
F1. Would failure of valve 3SIL-V5 or 11 closed during quarterly stroke testing render the low pressure safety injection system unavailable to perform its safety function?
Response
Yes. Failure of these valves closed would render SIL unavailable to perform its intended safety function. These valves will be full-stroke tested during cold shutdown. (Refer to Relief Request CSR-24.)
l i
l 1
l l
F1-1
58 Relief Request: CSR-24' Valves: 3SIL*V5, V11 Category: A Code Class: 2 1
Function: RHR Cold Leg Containment Isolation Valve l
l Test Requirements: Exercise (full stroke) quarterly Basis for Relief: These valves are required to be open with power removed from the operators during modes 1, 2 and 3 per Tech. Spec. 3/4.5.2 to ensure operability of this ECCS subsystem.
Alternate Testing: These valves will be full stroke tested during cold shutdown.
F1-2
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OEG NO PCO EOT I R TI A s s s s EVP OTC e - - e - - e - - e -
NR MI I Y Y Y Y OE ESD TS RON SN LI PI -
L I
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RE UD LO - - - - - - - - - - -
I M A
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I LI d d d d d d d d d d d TAT /e e e /e e e /e e e _ /e e I MC ns sn s ns s n sn ns s n sn . as sn SRN eo oe o eo oe oe eo oe oe eo oe OOU pl l p l pl l p l p pl l p l pl l p PNF OC CO C OC CO CO OC CO C OC CO N
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V N6A 5A V9 6
V 7
V 8B V2 9
V rV 1 B l 5 V9 1
V L8 6 LB - 1 - 5 0 - - - 1 - - 5 - 0 -
AM L8 LA C8 L8 LA LB L8 LB L8 LC VI N
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I 8 S -
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- 8 38 3I" l
60 i
L i l
l Fuel Pool Cooling System 1
F2. How are valves 3SIL-V6, 7,12,' and 13 partial-stroke exercised quarterly during power operations?
Response
Per Procedures SP3610B.2 and 3, the RHR pumps are on recirculation when these !
valves are part-stroked by' utilizing the SlH test header. Partial stroking of )
these valves during power operation causes a hydraulic shock to the test line J headers which could cause equipment damage. We will revise the IST program j manual to full stroke these valves at cold shutdowns and will delete the the !
partial stroking. 1 i
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k W
r ei td k e n
_ apep e ep ep ep e P LA LA LA P LA
, n .
n o S i FT a t ES ec I E 4 4 a r e2 LU 2 1 1 _ 2 uj1 EQ - - - -
w s n9 RE R R R _ R sI 6 R S S S S n e 2 C C C ry- C_ _
Pt 2 u wf2 e1 oa5 . ) ) .) ) ) ) ) ) )
a LS2 D 1 1 1 1 1 1 1 l 1 R
0 .
0 6h. 5h.
s :
m :8 0
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6h S
6 S S 3h 8h 9h 9h 1 h.
- S - S S S S m e n B( B( J J( K( K( B( B( I( J(
t i s w y a -
S r D -
D EG RN I I V V UT STI S R STTI ST ST STI S R STTI QS FNP F S FNLP FL FL FMP F S FNLP EE RT .
D TO -
3 SI Q I Q
- S I S1 SI Q I Q
TEM NTA I R R OEG NO PCO EOT I R TI A s s s s EVF e e - e e NR OTCI MI Y Y
Y Y
LI L
I M
E mE ~
iD LO - - - - -
I M A
F N
O/O I LI TAT I MC SRN N
/e ns eo d
/
d e
s n oe
/
d e
s n oe e/e ns eo d
/
d e
s n oe
/
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s n oe
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d e
s n oe
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d e
s n oe
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OOU pl l p l p pl l p l p pl l p l p pl PNF OC CO Co OC CO CO OC Co CO OC N
O I r r r r T o o o o A t - t - - t - - t U o o o o T M M M M C
A E . .
P .
K K K K. L.
Y A H A. H H A. H E A.
T C C C C C C C R G TS GS TA '2 2 EAL 2 2 C 2 2 2 2 2 C 2 ZCC B C 4 A C C B C 4 A I 2 2 / B A A 2 2 / 8 SEE 1 1 3 6 6 1 1 3 DD OO CC ER 2A 3 4A
- 5A 6 7 8B 9 O
I 8 l
iB VE V2 V V6 V9 V V V2 V V6 V9 LB - 1 - 5 0 - - - 1 - 5 - 0 AM L8 LA E8 L8 LA LB L8 LB 8 L8 VU N
I 8 S -
- V 3M I 9 S5
- V 3M I 8 S1
- 8 38 I 8 S1
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l R f eo p e p
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E ei e e e e td t t t t cv oe P n S k e k k k k DR s p a a a a ep e e e e LA L L L L n
o S i FT 1 9 9 9 9 t ES - - - - -
ec re2 IE LU S R R S
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S - S - S -
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ry- y Pt2 e1 wf2 oa5 . - ) ) ) ) ) ) ) ) ) ) )
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6h.
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t i s w y a E E S r D L L E
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TO 3 SI SI S - I OI S I OI S I OI S I OI Q I Q I ER CB C B RB C B RB C B RB C B RB B B TG TE
~ IN P NI UT S
TEM NTA I R R OEG NO PCO EOT I R TI A s s s s s s EVP OTC - e - e - e - e - e e NR MI I Y Y Y Y Y Y OE ESD TS RON SN PI LI L
I M
E RE UD LO - - - - - - - - - - -
I M A
F N N O/O / / / / / / /
I LI d d d d d d d d d 5 d
TAT e /e e /e e /e e /e e e e I MC sn ns s n ns s n ns sn ns sn sn sn SRN oe eo oe eo oe eo oe eo oe oe oe OOU l p pl l p pl l p pl l p pl l p l p l p PNF N
CO OC CO OC Co OC CO OC CO CO CO g7 O
I T
r o
r o
r o
r o
r o
r o
A - t - t - t - t - t t U o o o o o o T M M M M M M C
A E . . . .
P K . K . K . K . K. . .
Y H A H A H A H A H A A T C G C G C G C G C G G EAI ZCC I
YS GS TA 2
C A
2 B
0 I
C A
0 2
B 0
I C
A 0 0 2
B I
C A
0 2
B 0
I C
A 0
2 B
8 2
B 8
SEE 6 1 1 1 1 1 1 1 1 DD OO CC 3 4 5 6 7 8 9 0 1 2 3 ER 1 l A 1 1 B 1 1 C 1 2D 2 2A 2B VE V V8 V V8 V V8 V V8 V V4 V4 LB - - 0 - 0 - - 0 - - 0 - - 0 - 0 Af LD L8 LA L8 LB L8 LC LD V1 P I 8 I 8 I 6 I 8 I 6 I8 I 6 L8 I 8 I 6 L8 I 8 L8 I 8 N S1 S - S5 S - S5 S - S5 S - S5 S - S -
8 V - 9 V - 9 - V V 38 3M 38 3M 38 3M
- 9 38
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l l[!Il
63-Fuel Fool Cooling System F3. The proposed alternate test frequency for valves 3SIL-V15,17,19, and 21 does not adequately demonstrate the operability of these valves. The NRC Staff has concluded that. a valve sample disassembly / inspection utilizing a manual full-stroke exercise of the valve disk is an acceptable method to verify a check valve's full-stroke capability. This program involves grouping similar valves together and testing one valve in each group during each refueling outage. The sampling. technique requires that each valve in the group be of the same design (manufacturer, size, model number, and materials of construction) and have the same service conditions. Provide a justification for not meeting this NRC Staff position.
Response
The relief request'has'been revised to reflect the NRC Staff position. (See the attached Relief Request R-3.) Additionally,3RCS&V30, V71, V107, and V146 has been added to this relief request in response to Question B.I.
I l
)
l 1
I l
I l
I F3-1
. . , . GLf Relief Request: R-3 Valves: 3SIL*V15, V17, Vl9, V21 i
Category: AC Code Class: 1 Function: Pressure isolation between the reactor coolant system and the safety injection accumulator tanks. 1 Test Requirements: Exercise (full stroke) quarterly.
Basis for Relief: These valves cannot be full stroke or part stroke exercised during operacion since no flow path exists to accomplish such a test. The valves cannot be
. fall stroke or part suoke exercised during a cold shutdown because this would result in a complete or i I
partial discharge of the tanks into the reactor vessel which could result in low temperature j i
overpressurization of the RCS.
1 Alternate Testing: These valves will be partially disassembled, inspected and manually exercised on a staggered sampling basis each refueling outage. During each disassembly, l the valve internals will be inspected for structural j soundness (no loose or corroded parts). In the event that a disassembled valve's full-stroke capability is questionable, additional valves will be disassembled until one hundred percent (100%) of the valves 1 identified in this group have been disassembled and inspected.
}
J
)
F3-2 1
E _
, .. .,-< C(
Fuel Pool Cooling System FI.
d Would failure of valve 3SIL-V25 open during quarterly stroke testing-render the low pressure safety injection system unavailable to perform its >
safety function?
Response
Yes. This has been addressed and this valve will be tested a. culd shutdown. A cold shutdown relief request has been written to address this. (See attached Relief Request CSR-25) Also,3SlH*V93, V100 in Question 1.5 have been added to this relief request also.
i 1
l 4
F4-1 )
/R - t C e t C .
SI s D n t0 s 0 n
- : : TU - e
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r P rP oF - t r
P NN e P MR P
1 1
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p fC 0
1 1
e-p OL
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t n 5 J y1 5 J no CA 3 t l 3 t ei ms I
C
- s x nr - s a ei oe9 h
ei ui cv P E W td n n p9 W td oe S I
k e I n et k e DR r e p ps n r s p
- P e ep LA 0 ee
- tP e
- P LA ep n
o S _
x 5 5 i FT -
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r c I E R R ue3 LU S S sj1 EQ C C s n9 eI 6 r
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t i _
s y
v _
s S r D _ _
D EG - _
RN I I V -
V UT STI S STI S S T I- R STI T STI R STI T QS FMP F FMP, F FN S FMPL FMP S FMPL EE RT D
TO 3 SI Q I Q Q I Q Q
- S I Q I
- S I ER B B C B B C B TG TE -
I N P .
NI UT -
S TEM NTA I
OEG R
NO R ~ ~
PCO EOT -
I R TI A s s s s s s EVP OTC NR MI I Y e -
Y e - e Y
Y e
Y e - -
Y e
I PI M
E RE UD LO - - - - - - - C - -
I M F A
F N N /
/
O/O / / / / /
- I LI d d d d d d d dd d d TAT e e /e e /e e e ee e e
/h/
I MC s n s n ns s n ns s s n s s s s n eo -- o SRN oe oe eo oe oe oo o oe OOU l p l p pl l p pl l l p l l l l p PNF CO CO OC CO OC _C CO CC C CO N
O I
T A
r o
r o
r o - r o r r
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Relief Request: CSR-25 i
Valves: 3SIL*V25/3SIH*V93, V100 1
' Category: A Code Class: 2 Function: SIL/SIH Hot Injection Isolation Test Requirements: Exercise (full stroke) quarterly i
Basis for Relief- These valves are required to be closed with power.
operation removed from the operators during modes ~1, 2 and 3 per Tech. Spec. 3/4.5.2 to ensure operability.
of this ECCS subsystem.
Alternate Testing: These valves will be full stroke tested during cold shutdown.
i I F4-4
. 59 Fuel Pool Cooling System F5. How are valves 3SIL-V26,27,28, and 29 partial-stroke exercised quarterly during power operations?
Response
3SIL*V26, V28 are partial stroked per SP3610B.2 (page 12) using the SlH leak detection er.
Full-stroke testing of these valves during cold shutdown could result in RHR cooling flow bypassing the reactor core. Relief Request CSR-10 will be deleted and these valves will be full-stroke tested at refueling outages. (See the attached Relief Request R-22.)
Valves RCS*V69 and V142 will be full-stroke tested at refueling outages. (See the attached Relief Request R-22.)
3SIL*V27, V29 are part stroked using the SIH leak detection header. These will be deleted from part stroke for reasons stated above. IST manual will reflect deletion of this part stroke. (See attached.)
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1.
l Relief Request: R-22 Valves: 3SIL*V26, V28; 3RCS*V69, V142 l
. Category: AC Code Class: 2 .
Function: Pressure isolation between the Reactor Coolant System and Residual Heat Removal System.
Test Requirements: Exercise (full stroke) quarterly.
Basis for Relief: 'There is no flow path available'to test these valves during power operation with a pressure source capable of overcoming Reactor Coolant System pressure. The normal pressure sources which would be used during an accident to stroke the' valves are-the Residual Heat Removal'(RHS) pumps which develop a shutoff head of only 200 pounds. These valves cannot be full stroked during cold shutdown because establishing flow through these valves could result in RHR cooling flow bypassing the reactor core.
Alternate Testing: These valves will be full stroke tested during refueling outages.
9%
%eW FS-4
73 1
Fuel Pool Cooling System i
F6.
~
- . Valve disassembly.and it.spection is an acceptable test method, however, the test frequency proposed in Relief. Request R-5 for valves 3SIL-V982 and 983 is not adequate (see question F.3 above).
. Response These valves will be disassembled. See the revised Relief Request R-5.
F6-1
. . .- . 17 9 1
Relief' Requesti . R-5 L
l Valves: 3SIL*V982/V983 1
1 Category: C j
1
_ Code Class: .2 Function: Isolation of-the-RilS system. The valves are required .
to open for containment recirculation. -i Test Requirements:.. Exercise (full stroke) quarterly.
Basis for Relief: There is no flow path available to test these valves
' during power operation, -cold shutdown, or refueling shutdowns. The' isolation valves, 3SIL*V23 and 3SIL*V22 are interlocked requiring the RilS and RSS systems be lined up for containment recirculation before they can be opened. )
i Alternate Testing: These valves will be partially disassembled, inspected l
{
and manually exercised on a staggered sampling basis for each refueling outage. During each disassembly, the valve internals will be inspected for structural -
soundness (no loose or corroded parts). In'the event that a disassembled valve's full-stroke capability is questionable, additional valves will be disassembled !
until one hundred percent (100%) of the valves )
identified in this, group have been disassembled and inspected.
I l... ,
F6-2 L _ _ - _ _ _ _
l
.. .. . 7f Fuel Pool Cooling System l
F7. Review the safety function of valves 3SIL-V32 and 33 to determine if they should .be included in' the IST program and tested to the code requirements.
Response
These valves are passive (i.e., closed / fail closed) and do not meet IWV2100.
These valves will not be included into the IST Manual.
In reviewing this issue it was determined that 3SIL*V31, V34 are passive containment isolation valves.' These valves will be reclassified as passive Appendix 3 valves. See the attached change to the IST Manual.
1 F7-1
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77
' Fuel Pool Cooling System F8. Review the' safety function of the following' valves (located on P&lD 25212-26912 Sh. 2) to determine-if they should be included in the IST program and tested to the code requirements:
3SIL-V41 3SIL-V44 ' 3SIL-V82 3SIL-V885 3SIL-V42 3SIL-V53 3SIL-V83 3SIL-V886 3SIL-V43 3SIL-V64 3SIL-V884 3SIL-V887
Response
Valves 3SIL-41, 42, 43, and 44, 3SIL-884, 885, 886, and 887 will be included in the IST Manual and tested quarterly.
As for 3SIL*V53, V64, V82, V83 these are thermal reliefs and will not be included in the IST Manual.
I i
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6D 1
1-Gl. Do valves 3RHS-V3,7, 25, and 42 (P&lD 25212-26912 Sh. I locations G-7, G-10, E-7, and E-9) have a required fail-safe position? If so, they should be included in the IST program and be tested to the code requirements.
Response
Valves 3RHS*V3, V7 (HCV606, 607) are normally open/ fail open and 3RHS-V25, V42 are normally closed / fall closed and are considered passive per'lWV2100 and need not be included in the IST program.
'l; l
l i
I 1
l 1
E I
l J
Gl-1
i t
8)
G2. Would failure of valve 3RHS-V4 or 8 in the closed position during 3
quarterly stroke testing render the low pressure safety injection system unavailable to perform its safety function? :
)
Response
i Yes. Quarterly stroke testing will render the low-pressure safety injection system inoperable. The IST Manual will be revised to indicate full-stroke exercising of these valves at cold shutdown. (See the attached Relief Request CSR-26.)
l i
i l
.I G2-1
- oog:.e:
NQ EE t l t l t t NN a MR rn rn P M 1 eo 1 eo 1 1 1 p 1 p 1 1 t n OL no CA 5 J 5 J 5 5 ei I 3 t 3t 3 3 ms C - s x - s x - -
ui c v E Wtei dn Wtei dn W W M oe DR P
S I
k e ra p I
k e ra p I
r I
r eep eep e e PLA PLA P P S
m FT t e ES at I E 6 6 es2 H y1 LU 2 2 EQ - -
S9 RE R R l 6 R S S al 2 C C u a -
d v2 i o1 s m2 ee5 ) ) ) ) ) ) )
RR2 D. 1 1 1
) ) )
1 1 1 1 1 1 R 1 O
6h. 0 .
- 1 .
O 7h 1 h 9h 3h.
m:
i g C 4i 6b 6h 1 h 4h e n - S S - S S - S - S - S - S - S - S C( H( C( H( C( A( E(
t i E( A( D(
s w y a S r D D EG RN I I UT S V V V V ST1 S STI RT RT STI STI R R QS F FMP F FMP SL SL FNP FMP EE S S RT D
TO 3 SI Q S Q S ER C I
B C I
B
- I
- 1 Q I Q I *
TEM NTAP l
R 0EG NO PCO EOT I R TI A s s EVP OTC - e s s NR MI I
- e - - e e - -
Y Y OE ESD T Y TS RON SN PI LI L
I M
E RE UD I O - - - - - -
I M - -
A F
d d e e s s N N o o O/O /l /l / /
I LI dC d dC d / /
TAT d d d d e- /e e - /e e e /e /e d
e d
e I MC s n ns s n ns s n s n ns ns s n s n SRN eo oe OOU PNF loep pl l p eo pl oe l p oe l p eo pl eo pl oe l p oe l p CO OC CO OC CO CO OC OC CO Co N
O I r r r T o r A - t o o o
- t - - t U o o t - -
T M M o o C M M A
E . .
P K .
K L L .
f H A H A.
. L L T C E E L L E E C C C R R G C R R YS 0E TA EAL 2 2 2 2 2 2 2 2 2 ZCC C B C B C 2 C C I 0 C B B 4 4 0 0 0 A A 3 3 SEE 1 1 1 1 4 4
/ /
1 61 1 0 1 ER 0 7 V 6 8 8 I
4A S 8B 1 A 2B C V VE V V6 ? V6 V8 V8 9 9 LB - - 1 - - 1 F C V V AM SA - 0 - 0 - ) F) - B - A S7 SB S7 S7 S7 S4 VU H0 H8 H0 H8 H8 H8 H2
- 1 S4 S7 S7 N R3 R - R3 R - R - *I 3 H3
- 7 - V - 7 R - R - H - R - R -
- V - V - V - V RV - V - V 38 3M 38 3i t 3R 3R 3( 3( 3R 3R oyto
, llll
[' l(i lill :
83 i Relief Request: CSR-26 Valves: 3RHS*V4, V8 Category: B Code Class: 2 Function: RHR Discharge Cross Connects Test Requirements: Exercise (full stroke) quarterly i Basis for Relief: Full stroke exercising these valves closed during power operation would render the RHR system inoperable by isolating two of the four cold leg injection paths to the RCS from RHR.
Alternate Testing: These valves will be full stroked tested during cold shutdown.
G2-3
._. , .- 91 G3. Provide a more detailed technical justification for not full-stroke exercising valves 3RHS-V998 and 999 quarterly during power operations.
Response
Full-stroke , exercising these valves at power operation, poses unnecessary exposure to low pressure system LOCA. These valves are RCS pressure isolation valves. required to be closed per. Technical Specification 4.4.6.2 and are leaked tested within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> af ter operation. In' order to leak test these valves, a containment entry is required. _ Any leakage through these valves flashes to steam and must be _ vented to containment atmosphere (hydrogen and radioactive gaseous problem). Relief Request CSR-il provides additienal justification for not full-stroke exercising valves RHS-V998 and 999_ quat terly during power operations.
G3-1
9[-
' Relief' Request: CSR Valves: 3RHS*V994, V995, V996, V997, V998, V999 Category: A Code Class: 1:
Function: Pressure isolation Test Requirements: Exercise.(full stroke) quarterly .
u i
~ Basis for Reliefi Stroke testing of these valves at power is not possible. V994, V995, V996'and V997 are interlocked to prevent operation (opening) when the Reactor:
Coolant System pressure is.above 375 psig. Full stroke exercising V998, V999 poses unnecessary exposure to a low pressure system LOCA. These valves are RCS pressure isolation valves required to be ;
closed.per Tech. Spec.'4.4.6.2'and are leak tested within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after operation. In order to leak test these valves,.a containment entry (personnel' safety risk, the containment at MP3 is subatmospheric to j.
I 9 psia) is required, any leakage through these valves .t a
flashes to steam and must be vented to 1 W
containment atmosphere (hydrogen and radioactive ]
gaseous problem). f Alternate Testing: These valves will be full stroke tested during cold i shutdowns. f i
l' 3
J G3-2 l* ]
BC G4. Review the safety function of valves 3RHS-V24 and 41 (P&lD 25212-26912 Sh. I locations E-6 and E-II) to determine if they should be included in the IST program and tested to the code requirements.
Response
Valves 3RHS*V24, V41 have been reevaluated as active valves. These valves will be added to 1: e IST Manual and full-stroke exercised quarterly.
i l
i i
G4-1 i
f 1 p 1 p 1 1 t n 0L 5 J 5 J 5 5 no ei CA 3t 3t 3 3 m
I - s x - s x - -
a s C ei t i cv oe E
P Wtd I n Wtd I
ei n
W I
W I
S k e k e DR ra p ra p r r eep eep e e PLA PLA P P
~
S m FT t e st ES I E 6 6 es2 LU 2 2 N y1 EQ - -
S9 RE R R l 6 R S S al 2 C C ua - .
d v2 i o1 sn2 .
ee5 . ) ) ) ) ) ) ) ) ) )
RR2 D 1 1 1 1 1 1 1 1 1 1 R
O 0 .
6h.
4h.
m:
g O C - S 7h S
1 h
- S 9h
- S
. 1 1 h. 4h 3h e n C( H( C( H( C( A( E(
- S E( A(
- S D(
- S t i s w -
y a S r D D EG RN I I UT S V V V V STI S STI RT RT STI ST1 R R OS F FNP F FMP SL SL FMP FMP S S EE RT D
TO 3 SI Q S I Q S I
- I
- I Q I Q I *
TEM NTA I R R OEG NO PCO EOT .
I R TI A s s s s EVP 0TC - e - e - - e e - -
NR ft I I Y Y Y Y OE ESD TS RON SN PI LI L
I M
E RE UD LO - - - - - - - -
I M A
F d d e e s s N N o o O/O /l /l / / / /
I LI dC d dC d d d d d d d TAT e - /e e - / e e e /e /e e e I MC s n ns s n ns s n s n ns ns s n s n SRN oe eo oe eo oe oe eo eo oe oe OOU l p pl l p pl l p l p pl pl l p l p PNF CO OC CO OC CO CO OC OC CO CO N
O I r r r r T o o o o A - t - t - - t t - -
U o o o o T M M M M C
A E . . . .
P K. .
K .
L L .
L L Y H A H A E E L L. E E T C G C C R R G G R R YS GS TA 2 2 EAL 2 2 2 2 2 2 2 2 C C ZCC C B C B C C 8 B 4 8 I 0 0 0 0 A A 3 3 / /
SEE 1 1 1 1 4 4 3 3 DD OO CC 0
1 1 6 1 0 1 ER 4A 0 7 V 6 8 8 VE I 5 8B 1 A 2B C V 9 9 V V6 V V6 VB V8 F C V V LB - - 1 - - 1 - 0 - 0 -) F) - B AM SA S7 SB S7 S7
- A S7 34 - 1 S7 S7 VU H0 M8 H0 H8 M8 H8 H2 S4 H3 H3 N R3 R - R3 R - R - R - R - R - R - R -
- 7 - V - 7 - V - V - V - V RV - V - V 38 3M 38 3M 3R 3R 3( 3( 3R 3R g&I"
p, . --r r' ,
'B8 j % g l p %'
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' '% ' - Recirculation Spray System c, , . .
.. Hl . - .The code -identifies valve ' disassembly as an ' acceptable method of verifyingivalve operability,' however, the testing . Interval-identified in
. Relief Request R-6 for valves 3RSS-V3,6,'9, and 12 is not acceptable by
.the NRC Staff.
Response --
c it~ '- .
' c- Relief Request R-6 has been revised to partially disassemble: one valve per
<-: refueling outage. (See tLe attached revised Relief Request R-6.)'
i i
9 4-Hi-1
.7 L-.x____-_._
89 Relief Request: R-6 Valves: 3RSL*V3, V6, V9, V12 l
Category: AC l l
I Code Class: 2 Function: Containment Isolation Test Requirements: Exercise (full stroke) quarterly.
Basis for Relief: There is no flow path available to full stroke exercise these valves without actual initiation of recirculation spray. This could result in damage to plant equipment and spread of radioactive contamination.
Alternate Testing: These valves will be partially disassembled, inspected and manually exercised on a staggered sampling basis for each refueling outage. During each disassembly, the valve internals will be inspected for structural soundness (no loose or correded parts). In the event that a disassembled valve's full-stroke capability is questionable, additional valves will be disassembled until one hundred percent (100%) of the valves identified in this group have been disassembled and inspected.
H1-2
cl0 High Pressure Safety Injection System 1
l
- 11. Relief Request R-4 is inconsistent since it provides a justification for not full- or particl-stroke exercising valve 3SlH-V5 in the basis for relief and then in the alternate testing section proposes to partial-stroke exercise this valve quarterly,
Response
Valve 3SIH-V5 will not be partial-stroke exercised quarterly. (See the attached '
Relief Request R-4.)
l
)
11-1
____-___-__--_-_--_-_-__A
NN a rA P
t f R e- .
p e-p e
p0 f
t n 0L J J 5 no CA t t tR ei I s a sa sF ms C ei ei eC1 ui E td td t 05 cv P ~ n n 1 oe S k e k e k DR a p ep a p ep ad n.
ene LA LA L aP
. ~
n .
a S 2 2 3 i FT 1 1 1 et ES - - - 2) rc
- ue3 sj1 sn9 Lt E I
EQ R
S C
R S
C 4
R R
S C
1 2 R .
9 R
~ RE h ei6 R S r 2 (
P y-t 2 he1 gf 2 i a5 . ) ) ) ) ) ) ) )
HS2 D 1 1 1 2 2 2 2 2 R
O 4h.
m g O C
3h
- S - S 4h
- S 7h S
7 5h.
- S 2h.
- S 4h.
- S 8h.
- S e n H( H( J( A( B B( E( G( B(
t i s w y a -
S r D D EG RN I I UT STTI STTI ST FTI SS STI S STI STI QS FNLP FMLP FL FMP PF FMP F FMP FMP EE RT
- D TO -
3 SI S I S I OI S I QO Q I O Q I Q l ER C B C B RB C B R B R B E TG TE P
I N MI f
I T S
TEM NTA l R R oEG NO PCO EOT I R TI A s s s s s s EVP OTC e e - e - e - e e NR MI I Y Y Y Y Y Y OE ESD TS P ON SN PI LI L
I M
E RE iE t
l - - - - - -
l IE A~
F N N O/O / / / / /
I LI d d d d d d d d d TA tT e e e /e e /e e /e /e I i C s n sr sn ns s n ns s n ns ns SRN !
oe oe oe eo oe eo oe eo eo OOl PNF l p l p l p pl l p pl l p pl pl CO Co CO OC CO OC Co OC OC N
O I r r r r r r T o o o o o o A t t - t - t - t t U o o o o o o T M M M M M M C
A E . . .
P K . K K . .
Y A. A. H A H A. H A A T G G C G C C C G G TS GS TA EAL 2 2 I 2 2 2 2 2 2 ZCC A A C B C B C B B I 4 4 A S 8 6 4 4 6 SEE 3 DD OO CC 0 l 2 3 5 6 ER 3A 4B 5 1 i 1 A 1 1 A 1 B VE V1 Vl V V6 V V3 V V1 V3 LB - 0 - 0 - - 0 - 2 - - 2 - 2 AM N8 M8 N H8 M H9 NA R8 H9 VU I 8 I 8 I 5 l 8 I 6 l 8 I 2 I 8 1 8 N S - S - S1 S - S2 S - S2 S - S -
V V - 8 V - 9 - V - 9 V - V 3M 3M 38 3M 38 3M 38 3M 3M g- -
1 o . . .
91 Relief Request: R-4 Valves: 3SIH*V5 i
Category: AC
]
Code Class: 1 Function: Containment Isolation and Pressare Isolation l
Test Requirements: Exercise (full stroke) quarterly. l1 Basis for Relief: Full stroke or part stroking exercising of this valve during power operation would unnecessarily thermally shock the HPSI inlet nozzles to the reactor coolant system (RCS) cold legs by injecting nonpreheated water causing premature failure of the component.
Full stroking cannot be performed during cold shutdown because the required flow would risk overpressurization of the RCS.
Alternate Testing: The valve will be full stroke exercised during refueling outages when the reactor closure head is removed.
11-3
43 HJh Pressure Safety Injection System
- 12. How are valves 3SIH-V13 and 17 partial-stroke exercised quarterly during power operations?
Response
These valves are part stroked using the SlH leak test connection system (cross-tie from SIL) per SP3608.B Section 7-13 and 7-14. Valves 3SIH-V13 and 17 will not be partial-stroke exercised quarterly during power operations due to possibility of hydraulic shock and equipment damage. (See the attached Relief Request R-9.)
i l
12-1 l
L .-
NN a P 9 R e-p e- e f p p0 t n 0L J J 5 no CA t t tR ei I s a sa sF ms ui C ei ei eC1 E td td t05 cv P n n 1 oe S k e k e k .
DR a p a p ad n ep ep ene LA LA L aP n
o S 2 2 3 i FT 1 1 1 et ES - - -
_ rc ue3 I E LU R
S R
S 4
R S
2) 12 9
sj1 s n9 EQ C C R C R . R RE h ei6 R S r 2 (
P y-t2 h e1 gf2 i a5 . ) ) ) ) ) ) ) )
HS2 D 1 1 1 2 2 2 2 2 R
O m :g O C
3h.
- S 4h 4h 7h 7 5h 2h. 4h 8h.
- S - S S - - S - S - S e n H( H( J( A( B B( F( G(
- S B(
t i s w y a S r D D EG RN I I UT STTI STTI ST STI SS ST1 S STI STI QS FMLP FMLP FL FMP PF FNP F FNP FMP EE RT .
_ D TO -
3 SI S I S I O1 S I QO Q I O Q I Q I ER C B C B RB C B R B R B B TG TE I N P NI UT S
TEM
_ NTA
. I R R OEG NO
_ PCO EOT I R s
_ TI A s s s s s
_ EVP 0TC e e - e - e - e e
_ NR 1 r I I Y Y Y Y Y Y OE ESD TS R ON
_ L I
M
_ E
_ RE UD LO I M
_ A
_ F N N O/O / / / / /
I LI d d d d d d d TAT e e d d e /e e /e e /e /e I MC s n s n s n ns s n ns s n ns ns
_ SRN oe oe oe eo oe eo oe eo eo OOU l p l p l p pl l p pl l p pl pl PNF CO CO CO OC CO OC CO OC OC
_ N O
I r r r r r r T o o o o o o A t t - t - t - t t U o o o o o o T M M M M M M C
A
_ E .
_ P .
K. . K. K . .
Y A.
_ A H A H A. H A A
_ T G G C G C G C C G YS GS TA EAL 2 2 I 2 2 2 2 2 2 ZCC A A C 8 C B C 9 B I 4 4 A 8 8 6 4 4 6 SEE 3 DD OO CC 0 l 2 3 5 6 ER 3A 4B 5 1 i 1 A l 1 A 1 B VE V1 V1 V V6 V V3 V V1 V3
_ LB - 0 - 0 - - 0 - - 2 - - 2 - 2 AM M8 H R8 M
_ VU I 8 IN8 8 I 5 I 8 I 6 H9 I 8 NA I 2 M8 I 8 H9 I 8
_ N S - S - S1 S - S2 S - S2 S - S -
_ V - V - 8 - V - 9 - V - 9 - V - V 3M 3M 38 3M 36 3M 38 3M 3M 1,Io t
lh ;
' ([
,Llo [. . . .
Relief Request: . 'R-9 Valves: '3SIH*V13, V17 Category: C 3;
{
l ~ Code Class: 2 j Function: To prevent backflow to the associated safety
.4
} injection pump when secured and the parallel pump is j; -
in operation.
i
/
Test Requirements: Exercise (full stroke) quarterly.
j.
1-Basis for Relief: The source of flow to full stroke exercise these valves is the safety injection pumpt. (3SIH* PIA and PIB). The. shutoff head of these pumps (1,520 psig) l is insufficient to stroke these valven, against the normal reactor coolant system (RCS) pressure (this' is the only path to establish flow through these valves). Full stroking cannot be performed during cold shutdown because the required flow would risk overpressurization of the RCS.
Alternate Testing: The valves will be full stroke exercised during refueling outages when the reac+.or closure head is removed.
.12-3
4 e -., 'c'-
High Pressure Safety injection System
- 13. Would failure of valve 3SlH-V20 closed during quarterly stroke testing render both trains of the high pressure safety injection system unavailable to perform their safety function?
Response
Yes. Failure of valve 3SlH*V20 closed would render both trains of the high-presure safety injection system unavailable to perform its . intended safety function. This valve will be full stroked at cold shutdown. (See the attached Relief Request CSR-27).
1 13-1 l
i nA NN e P MR P
e-p e-p e-p e-p e-p eti b sl 0 1
1 t n OL J J J J J ee5 5 no CAI t t t t t nt uR 3 ei s x sz sx sa sn ms C ei ei ei e fF -
ei ei h meC1 ui E td td td td td wr r051 W cv P n n n n n o oe S k e I DR s p ep k e s p ep k e s p ep k e s p sp k e s p ep e nfh rcrn.
pea ee r
e LA LA LA I A LA C p e pP P n
o S 7 et i
FT 2 ES - 0 0 0 0 rc I E R 1 1 1 1 ue3 LU S - - - -
sj1 EQ C R R R R s n9 RE ei6 r R 2 .
P y-t 2 h e1 gf 2 i a5 . ) ) ) ) ) ) ) ) )
HS2 D 2 2 2 2 2 2 1 2 2 R
O .
6h.
7h.
m :g O C
8h
- S 7h
- S 5h
- S - S 6h
- S - S 6h.
- S 6h 4h e n G( H(
- S S t i K( K( K( R( 1 ( B( C(
s v y e S r D D EG RN IUT I
STI STTI V SI ST ST ST STTT R STI QS FMP FNLP FL FL FL FL FMFL S FNP EE RT D
TO 3 SI Q I S I OI OI OI OI Q I
TEM NTA I R P OEG NO PCO EOT I R TI A s s s s EVP OTC e e - - - - e - e NR MI I Y Y Y Y OE ESD TS RON SN PI LI L
I M
I M F A
F d
e s
N - N o O/O l / / / / / / /
I LI d C d d d d dd d d TAT /e / - e e e e ee e e I MC ns nn s n s n s n s n s s s n s n SRN e u ee oe oe oe oe oo oe oe OOU pl pp l p l p l p l p l l l p l p PNF OC OO CO CO CO CO CC CO CO N
O I r r r T o o r o A t t - - - - i - t U o o A o T M M M C
A E .
P .
K. R. K. X. L .
Y A A. H I H H A. E A T C G C C' C C C R C YS GS TA 2 2 EAL 2 2 2 2 2 A 8 2 ZCC B C C C I
SEE 4 W A 2
A 2
A 2
C A
2 4
/
3 4
/
3 8
6 DD OO CC 9 0 2 4 6 8 5 5 6 ER 1 R 2 2 2 2 2 6 7 7 A VE V1 Y5 V V V V V3 V8 V7 LB - 2 - 3 - - - - - 4 - 5 - 0 A
V1 *f M9 M8 NB NC HD NA H8 H8 M8 I 8 I 8 I 9 I 9 l 9 I 9 1 8 I 8 I 8 N S - S - S1 S1 S1 S1 S - S - S -
- V - V - 8 - 8 - 8 8 - V - V - V 3M 3M 38 38 38 38 3C 3R 3H gwb
L* ,qg t o -; . , v.
Relief Request: CSR-27 Valves: 3SIH*V20 L
Categor>L: A 1
l
[ , Code Class: 2 q 1
Function: HPSI to Cold Leg Master Isol Test Requirements: Exercise (full stroke) quarterly Basis for Relief:. This valve is required to be open and power removed-from the operators during modes 1, 2 and 3 per Tech.
, Spec. 3/4.5.2 to ensure operability of this ECCS subsystem.
~ Alternate Testing: These valves will be full stroke tested closed during.
cold shutdown.
l I
1 l;
4 1
13-3
. _ - _ _ - _ _ _ _ _ _ - ____-______-_A
qq High Pressure Safety Injection System -
- 14. Can valves 3SIH-V22, 24, 26, and 28 be partial-stroke exercised during cold shutdowns utilizing residual heat removal recirculation flow?
Response
No, there is no practical method to partial-stroke exercise these valves utilizing, the residual heat removal system.
1 14-1
l00 p-l High Pressure Safety Injection System
- 15. ' Would. failure .of valve 3SlH-V93 or 100 open during quarterly stroke testing render a train of the high pressure safety injection system unavailable to perform its safety function?
l Response l
Valves 3SlH-V93 and 100 will be full-stroke exercised at cold shutdowns. (Refer to the response to Question F4.)
15-1 i
I
fo) .
High Pressure Safety injection System j
- 16. Could exercising valves 3CHS-V259 and 260 during power operations result in the injection of refueling water storage tank water into the f reactor coolant system.
Response
No. The VCT has adequate pressure to overcome RWST discharge pressure. We are currently performing this per SP3604A.5 on a quarterly basis. Originally this was perforrned under SP3608.6 at cold shutdown.
I 16-1
/01 High Pressure Safety Injection System j 17. Would failure of valve 3SlH-V962 closed during quarterly stroke testing l render both trains of the high pressure safety injection system unavailable 9, j
to perform their safety function?
a
Response
Yes. If this valve failed closed during testing and an 51 occurred and the RCS did not depressurize to the 51 pumps discharge head, it would dead head the pumps.
(See the attached Relief Request CSR-29.)
l 4
t 17-1
NN a FE eF eF p i p P MR t C tC eF rA rA t p t p t n M 0 t C e e sA sA no OL r1 r1 0 0 p0 p0 e e ei CA o o r1 5 5 t 0 t 0 ms I f r f r o tR tR 5 5 ui C e6 e7 f r sI sF rR rR cv E d p9 d p9 e8 eC7 eC7 oF oF o e P e d p9 t 09 fC9 fC9 S e e t 09 09 DR nt . nt . n? .
1 1 n1 09 es pee n es n ern e k . k .
e .
n1 e
pe e p~ ad n ad n prn .
ene prn 0tP 6t P 0t P ene 0ee
- *
- L aP L aP
- pP 0ee
- pP n
o S i
et FT r c ES -
ue3 I E sj1 LU 1
- m. 1 9 s n9 EQ -
_ R- 2 ei6 RE R -
r 2 R P y- R t 2 S h e1 C
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)
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)
2
)
2
)
2
)
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)
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m n
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4h
- S 8h.
- S 8h 0 .
1 h 9h 7h t K( - S S 9h 9h s
i J( J( K( - S - S - S - S y
w K( D( C(
a D(
S r D D EG RN I I UT STI T STI T QS FMPL FMPL STI T ST ST ST1 E1 FMPL FL FL sri T STI T R1 FMP F Pf PL FMPL D
3 TO SI Q I Q
TG ER B 1
B Q I O O S I N TE B R R C 1 Q I Q I P B B B INIT S
TEM NTA I
R R OEG NO PLO EOT I P TI A s EVP OTC s s NR MI e e e s s OE I
Y Y - - e s ESD Y e e TS RON Y Y Y SN PI LI L
I M
M F C - -
A F F - C C F F F N N /
O/O * / /
I LI * * / /
dd dd / /
TAT ee ee dd ee d d *
- I MC s s s s e e d dd dd SRN s s s n /e ee ee O U 1' PiF loo l oo l l oo l l oe s n oe ns eo s s oo s s l CC CC CC l p l p pl oo CO CO OC l l CC l l CC N
O I
T r r r A r U
i A
i i
- o r r T A A - t i i C o A A A M E
F . .
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G G C H A. A A C G G A G G YS GS TA 2 2 EAL A A 2
ZCC 4 A I I 2 2 4 4 2 A I
/ / C C B A 2 SEE 3 3
/ A A 4 4 B DD 3 2 2 3 / / 8 OO 3 3 CC 2 3 0 4 ER 0 0 l0 2 2 7 1
I 8 9 VE V1 1
V4 1 i I 6
9 8 8 5 LB - 8 - 2 V3 V V 9 9 2 AM H8 - 2 - -
V3 V4 V1 VU H8 H8 HA - 1
- 6 V2 N
l 8 ! 8 I 8 MC H8 H9
- 7 -
S - S - S - I 5 I 5 l 8 H8 Sl
- V S0 S0 l 8 l 8 H 3C - V - V - 9 S - S - S -
3C 3C - 9 - V - V C 38 38 3M - V -
3C 3C 3L WYto'
. . . . . 1 o '1 I
l Relief Request: CSR-29 Valves: 3SIH*V962
- Category: B Code Class: 2 k
Function: HPSI Master Mini Flow Isolation Test Requirements: Full stroke exercise closed quarterly Basis for Relief: Full stroke exercising of SIH*V962 closed during power operation would render both trains of HPSI unavailable to perform their safety function.
Failure of this valve closed during power operations, if an SI signal occured and the RCS did not.depressurize to the Safety Injection pump discharge head, it would dead head the pumps.
. Alternate Testing: The valve will be full stroke tested closed during cold shutdowns.
t 1
i I
I l
17-3 J
I*$
High Pressure Safety Injection System
- 18. Provide a more detailed technical justification for not exercising valve 3CHS-V261 during cold shutdowns.
Response
Refer to the revised Relief Request R-II.
i l
1
- f. 18-1
,~
.x . . .
lo4 Relief Request: R-11 ,
i Valves: 3CHS*V261 Category: .C Code Class: 2 Function: To prevent backflow from the chemical and volume control system to the refueling water storage tank (RWST).
Test-Requirements: Exercise (full stroke) quarterly.
Basis for Relief: 'This valve is in the suction line between the-charging pumps (3CHS*P3A,.P3B, and.P3C) and the .
refueling water storage tank. Stroking this valve by taking suction from RWST.with the charging pumps during operation or~ cold shutdown would result in-uncontrolled boration and over pressurization of the ;
l l
. Alternate Testing: The valve will be full stroke tested during refueling outages.
18-2
I o ') .
Quench Spray System
- 31. The code identifies valve disassembly as an acceptable method of verifying valve operability, however, the testing interval identified in Relief Requests R-7 and R-8 for valves 3QSS-V4,8,976,977,978, and 979 is not acceptable by the NRC Staff.
Response' Valves 3QSS-V978 and 979 have been deleted from Relief Request R-8 and have been added to Relief Request R-7. Both the relief requests have been revised to
. add disassembly and inspection in accordar.ce with the resonse to Question F.3.
l l
31-1
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.. Relief Request: R-7
' Valves: 3QSS*V4,'V8, V978, V979 Category: AC/C j[.,
[ Code Class: 2-Function: . Containment Isolation / Isolate the appropriate quench spray system (QSS) header in the event.it should-become inoperative.
Test Requirements: Exercise (full stroke) quarterly.
- Basis for Relief: There is no flow path available to full stroke exercise these valves without actual initiation of quench spray. This could result in damage to plant ,
equipment and spread of~ radioactive contamination.
Alternate Testing: These valves will be partially disassembled, inspected and manually exercised on a staggered sampling basis for each refueling outage. During each disassembly, the valve internals will be inspected for structural soundness (no. loose er corroded parts). In the event that a disassembled valve's full-stroke capability is questionable, additional valves will be disassembled until one hundred percent (100%) of the valves identified in this group have been disassembled and inspected.
J1-4
__________m
lli I
Relief Request: R-8 Valves: 3QSS*V976, V977 Category: C
{ Code Class: 2 Function: Isolate the appropriate quench spray system (QSS) header in the event it should become inoperative.
Test Requirements: Exercise (full stroke) quarterly.
Basis for Relief: There is no flow path available to full stroke exercise these valves without actual initiation of quench spray. This could result in damage to plant equipment and spread of radioactive contamination.
Alternate Testing: These valves will be partially disassembled, inspected and manually exercised on a staggered sampling basis for each refueling outage. During each disassembly, the valve internals will be inspected for structural soundness (no loose or corroded parts). In the event that a disassembled valve's full-stroke capability is questionable, additional valves will be disassembled until one hundred precent (100%) of the valves identified in this group have been disassembled and inspected.
J1-5
.. . -o RL Quench Spray System
- 32. Provide a more detailed technical justification for not verifying closure of valves 3HCS-V7 and 14 quarterly during power operations or during cold shutdowns.
Response
Refer to the revised Relief Request R-16.
1 32-1
3...- ..
II3 Relief Request: - R-16 '
Valves:
3HCS*V7, V14
~
Category: AC Code Class: -
'2 Function:
Containment Isolation Valve Test Requirements:'
Exercise closed (full stroke) quarterly.
Basis for Relief:
The function of'these valves is to provide. ~
containment isolation when the hydrogen recombiner is not in operation.
There is no other flow path available to' stroke.these valves closed duri.ig power:
operations or cold shutdown, therefore, these valves cannot be. tested during normal operation or cold shutdown.
-Alternate Testing:
This valve is subject.to local leak rate testing 1 every two years as required by 10CFR50, Appendix J.,
This test uses a temporary pressurization source to check the valve's leakage rate which verfies that it goes to the closed position.
J2-2
. _ _ _ .___--_________L
. .i. . .
Quench Spray System -
- 33. Could failure of the open position of valve 3QSS-V30 or 31 during quarterly valve testing result in the flow of caustic chemicals into the refueling water st( age tank?
Response
No. The path is isolated by ('S*129 and V32 which are normally locked open (per Proecedure SP3609.9).
33-1
l.. . .. , . g L.'
Quench Spray System
- 34. Review the safety-related function of . valve 3QSS-V984 (P&lD 25212-26902 Sh. I coordinates E-4) to determine if it should be included in the-IST program.
1:
Responie This valve is only used for testing and is, therefore, not required to be included in the IST program.
l l
l l
34-1
Its Reactor Plant Component Cooling System Kl. - . Provide a more detailed technical justification for - not full-stroke exercising valves 3CCP-V18 and 60 quarterly during power operations.
_R_esponse
. Refer to the revised Relief Request CSR-14.
l l
l Kl-1 1
l12 .
Relief Request: CSR-14 Valves: 3CCP*V18, V60 Category: AC Code Class: 2 Function: Containment Isolation Test Requirements: Exercise (full stroke) quarterly Basis for Relief: In order to full stroke (close) each of these valves, it would be necessary to secure component cooling to the associated train. ("A" train for V18 and "B" train for V60). This would cause in a temporary loss of cooling water to the letdown heat exchanger for train "A" and the seal water heat exchanger for train "B". The result would be unnecessary thermal cycling of the supplied components causing premature failure of the charging lines to the RCS and, in the case of the letdown heat exchanger, an increase in the inlet temperature to the CVCS demineralizers.
In addition to these components, cooling would be lost to a number of important non-safety related components including the containment penetration coolers.
Alternate Testing: These valves will be full stroke tested during cold shutdowns when the heat load to the supplied components is at a minimum.
K1-2
Il % ,
'. . . 4 Reactor Plant Component Cooling System-K2. Do valves 3CCP-V989, 990 and 991 (P&lD 25212-26921 Sh. I coordinates I-7, I-3 and I-6) have required fail-safe positions?
Response
Valves 3CCP-V989,990, and 991 do not have required fall-safe position and need not be included in the IST program.
l l
l 4
K2-1
li g i . .. .
Main Steam and Blowdown System Ll.. Provide a more detailed technical justification for not full-stroke exercising valves 3 MSS-VI,4,7, and 10 quarterly during power operations.
Response
~
Strokin' g these valves full closed quarterly during power operations could result in a reactor trip (i.e., shrinking in the steam generator). (See the revised Relief Request CSR-15.)
L1-1
(10 Relief Request: CSR-15 Valves: 3 MSS *71, V4, V7, V10 Category: B l<
Code Class: 2 1
runction: Main Steam Isolation i Test Requirements: Exercise (full stroke) quarterly Basis for Relief: Full stroking these valves to the closed position during power operation would result in an unbalanced steam flow condition producing an abnormal power distribution in the reactor core possibly causing a e reactor trip. Therefore, full closure of these valves for the purpose of testing requires plant shutdown.
]
Alternate Testing: These valves will be part stroke tested during power operation and full stroke tested during cold shutdowns.
l i
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4 L1-2
_ _______--_____--_-_--_---J
lit Main Steam and Blowdown System L2. What Is the safety-related function of valves 3 MSS-V2, 5, 8, and 11? Is this an active function?
,Respons -
These valves are normally closed. Their safety function is to close during the plant cperttion. (See the revised Relief Request CSR-16.)
i 4
t L2-1 ll mJii...I
! %.1 -
Relief Request: CSR-16 Valves: 3HSS*V2, V5, V8, V11 Category: B
?
i Code Class: 2 r
Function: Provide steam to warm lines down stream of the MSIVs-and equalize pressure prior to opening.
Test Requirements: Exercise (full stroke) quarterly Basis for Relief: These valves are only required to be open while warming the steam lines and remain closed during I
. power operation. Opening these valves at power merely to test that they close could result in a failure of these valves in a nonconservative position. Since these valves provide no safety function during power operations they will be full stroke tested at cold shutdown.
Alternate Testing: These valves will be tested at a cold shutdown frequency to ensure closure immediately following opening during plant startup before placing the ;
turbine in operation.
f 4
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Main Steam and Blowdown System L3. Do valves 3 MSS-V12, 37 and 38 nerform safety function in. the closed position? If so, how are these valves verified to close during quarterly testing?
i
Response
Valves 3 MSS-V12, 37, and 38 do perform a safety function and will be exercised to the closed position quarterly using the motor operator.
L3-1
- . - _ _ _ _ _ _ _ _ _ _ _ _ ~
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lLf Feedwater System M1. Can valves 3FWS-V15,22,29, and 36 be partial-stroke exercised quarterly ;
during power operations? What is the safety-related function of these l valves? ,
1
Response
Valve operability is demonstrated by proper operatior, of the steam generator level control system. Valves 3FWS-V15, 22, 29, and 36 will be full-stroke exercised at cold shutdowns.
Ml-1
Ih-f' Feedwater System M2. Provide a more detailed technical justification for not full- or partial-stroke exercising valves 3FWS-V18, 25,32, and 39 quarterly during power operations. What is the safety-related function of these valves?
Response
These valves are normally closed required to fall closed. (See the revised Relief Request CSR-19.)
l l
M2-1
.- _ _ ___ .-_-__ --____ a
11) l Relief Request: CSR-19 Valves: 3FWS*V18, V25, V32, V39 Category: B Code Class: 2 Function: To control feedwater at low power Test Requirements: Exercise (full stroke) quarterly Basis for Relief: These valves remain closed (their safety position) above 20 percent reactor power. Opening these valves to test that they close would subject the feedwater system to an unnecessary transient (on the steam generator water level control) possibly causing a reactor trip.
Alternate Testing: These valves will be stroke tested during cold shutdowns.
M2-2
. . - _ _ _ ~ . . . _ . . _ _ _ .
116L -)
q l
l Feedwater System l-M3. Provide a more detailed technical justification for not full- or partial- 1 stroke exercising valves 3FWS-V20,27, 34, and 41 quarterly during power operations. ,
3 Resoonse Full-stroke exercising these valves closed during power operations could cause a loss of feedwater and cause 'a plant trip. (See the' revised Relief Request CSR-18.)
1 i
j M3-1
- 1 Relief Request: CSR-18 Valves: '
3FWS*V20, V27, V34, V41 Category: B.
Code Class: 2 Function: Feedwater Isolation
-Test Requirements: Exercise (full stroke) quarterly Basis' for' Relief: Stroke testing these valves during power operation would secure flow to an operating steam generator and cause a loss of feedwater and a plant trip.
Alternate Testing: These valves will be stroke tested during cold shutdowns.
(
M3-2
f30 Feedwater System M4. Provide a more detailed technical justification for not exercising valves 3FWS-V898,899,920, and 921 quarterly during power operations.
Response
Full-stroke exercising these valves during power operations can cause a loss of
!feedwater resulting in a plant trip. (See the revised Relief Request CSR-20).
l M4-1
Relief Request: CSR-20 Valves: 3FWS*V898, V899, V920, V921 Category: C 1
Code Class: 2 Function: To prevent backflow from the associated steam Benerator on loss of feed Test Requirements: Exercise (full stroke) quarterly Basis for Relief: Stroke testing these valves at power would require securing feed flow to the associated operating steam generator causing a plant trip.
Alternate Testing: These valves will be verified closed when feed to the associated steam generator is secured during cold shutdown.
M4-2 _ ._ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ - _ - _ - _ - ..
i31 Feedwater System M5. Is credit taken for the reverse flow closure of the following auxiliary feedwater check valves? If so, how are these valves individually verified to closed?
3F WA-V9 3FWA-V23 3FWA-V882 3FWA-V884 3FWA-V14 3FWA-V28 3FWA-V883 3FWA-V885
Response
No. These valves are normally closed required to go open.
l l
i i
I M5-1
I33 Feedwater System M6. Which auxiliary feedwater check valves present diversion of flow through an idle auxiliary feedwater pump when another pump is operating? How are these individually. verified to close?
Response
Valves 3FWS-V35,' 39, 43, .47,12, 7, 21, 26,-3,17, and 31 will be verified in the closed position -during cold shutdown testings. -(See the revised Relief Request CSR-21.)
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134 Relief Request: CSR-21
.- i Valves: 3FWA*V3, V7, V12, V17, V21, V26, V31, V35, V39, V43, V47 Category: C Code Clasfi: 2 Function: Pass required auxiliary feedwater flow to the steam generator.
Test Requirements: Exercise (full stroke) quarterly Basis for Relief: Operating the auxiliary feedwater system at power is undesirable at the required flows to fully open these check valves. This places an unnecessary perturbation on the main feedwater control system which could result in a reactor trip. It also causes undesirable thermal transient on the feedwater piping. These valves cannot be tested closed individually. The valves in a train (i.e., series) will be tested closed during full stroke testing at cold shutdown.
Alternate Testing: These valves will be full stroke tested open and closed during cold shutdowns.
NOTE: The code does not require these valves to be tested closed because they are passive in the closed position. However, we have included these valves to be tested in the closed position due to importance of their safety function in the closed position.
M6-4
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Feedwater System M7.' Review the safety _ function of the . following valves (located 'in P&lD 25212-26930 Sh. 2) to determine if they should be included in the IST program and tested to the code requirements.
Valve . ' Valve Valve 3FWA-V6 3FWA-V27 3FW A-46 '
. 3FWA-V 11 3FWA-V36 13FWA-60 3FWA-V13 3FWA-V38 3FWA-62 3FWA-V20 ' 3FWA-V40 ~ 3FWA-854 3FWA-V22 3FWA-V42 3FWA-855 3FWA-V25 3FWA-V44
Response
The safety function for these valves is to fail open and they are normally open..
Therefore, these are passive per ASME IWP2100.
Valves 3FWA-60 and'62 do not have a failure position and, therefore, these are passive per ASME11 IWP2100.
~
- Valves 3FWA-854 and 855 are' normally closed and are' required to fail close.
Thus,.these'are passive per ASMEll IWP2100. The remaining valves identified-above are being reviewed to determine. if they should be included in the IST program. -
1 I
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M7-1 1 l
13 5 Service Water System i
N1. Provide . a .more detailed . technical justification for not. full-stroke I exercising valves 35WP-V25, 27, 58, and 60 quarterly during power I operations and during cold shutdowns.
)
Response
Securing component cooling to the nonsafety related equipment / safety-related l equipment during power operation would provide inadequate cooling to plant equipment. (Refer to the revised Relief Request 'R-14.) f l
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Relief Request: R-14 .k i
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Valves: 3SWP*V25, V27, V58, V60 i
1 Category: B l
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' Code Class: 3 o
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Function: Service water aupply valves to the recirculation spray system coolers.
Test Requirements: Exercise (full stroke) quarterly.
Basis for Relief: -These valves are interlocked so that they cannot be opened unless valves 3SWP*V33'and V65 are closed shutting off service water supply to the component cooling water coolers. Component cooling water cannot be secured during operation or cold shutdown, it would not provide proper cooling to non-safety:
relate'd equipment and cause a SWP pump runout.
Alternate Testing: Full stroke during refueling outages. l 1
s N1-2
I L(o h
Service Water System N2. Could failure of either valve 35WP-V33 or 65 closed during quarterly testing cause equipment damage as a result of loss of cooling flow to the component cooling water heat exchangers.
Response
j Yes, Relief Request CSR-28'provides technical justification for not full-stroke exercising these valves quarterly during plant operations.
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,. Relief-Request: CSR-28.
p ' Valves: 3SWP*V33, V65
' Category: 'B
' Code' Class: .3.
Function: Train A &'B Service Water Header.to RPCCW Heat Exchanger Inlet Manifold Test Requirements: Exercise (full stroke) quarterly Basis for Relief: Full stroke exercising'either of these valves closed-quarterly would isolate component cooling water heat exchanger resulting in equipment damage to both safety related and non-safety related trains.
Alternate Testing: These valves will be full stroke tested during cold shutdown.
N2-3
IN-3 Service Water System N3. How are valves 3SWP-V705 and 706 verified to close during quarterly testing?
Response
These valves will be disassembled during refueling outages. (Refer to ' the attached Relief Request R-23.)
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Valves:- l.3SWP*V705,706,:707,708 Ur LCategory:. :C.
. Code Class: 3
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f Functioni ' Safety injection' pump coolers /MCC and rod control booster pump. suction.
Test Requirements: ~ Full rtroke exercise.(quarterly).
i%
(- + A Basis for Relief: Full stroke exercising:these valves closed at power operations would require isolating service water'to safety related equipment. This would result-in equipment damage.
g ' Alternate Testing:- These valves will be partially disassembled, inspected-and manually exercised'on a staggered sampling basis for each refueling outage. During each disassembly, the valve internals will be inspected for structural.
soundness (no loose cn corroded' parts). In the event that a disassembled valve's full-stroke capability is questionable, additional valves will be disassembled until one hundred percent (100%) of the valves identified in'this group have been disassembled and inspected.
i N3-2
] 4 5' Service ' Water System l -
N4. Do valves 35WP-V14 and 47 (P&ID 25212-26933 Sh. 2 locations F-9 and F-
- 2) have required fall-safe positions?
- Response No. Valves 3SWF-V14 and V47 need not be included in the IST program.
N4-1 1
1
14 6 1
Service Water System
- 01. Provide a more detailed technical justification for r.ot full-stroke exercising valves 3IAS-V131 and 809 quarterly during power operations.
Response
Full-stroke exercising these valves closed would result in loss of instrument air inside containment causing loss of pressurizer control of CVCS letdown resulting in a plant trip. (See the revised Relief Request CSR-22.)
1 01-1
IN7I 16 ,.. T
'i,.o l' Relief Request: CSR-22 4
, Valves: 3IAS*V131, V009
' Category: A Code Class: 2' 1 Function: Containment Isolation Test Requirements: Exercise (full stroke) qusrterly Basis for Relief: These valves isolate the entire inside containment.
instrument air system from their normal source outside containment. Full stroke testing of these valves during power operation would cause a complete-loss of~ instrument air inside containment. As a result, all' valves inside containment supplied by inotrument air would stroke to their fail safe position resulting in a plant shutdown at power.
Alternate Testing: These valves will be full stroke tested during cold shutdown.
01-2
l Service Water System
- 02. Are 'there any valves in the air / nitrogen supply of the MSIVs and main feedwater isolation valves whose failure could prevent these. Isolation valves from performing their safety-related functions?
Response
No. Nitrogen supply to these valves is a Class 4 (nonsafety-related) system and is isolated at power. The only supply to these valves at power is steam. -
I 02-1
., ,.. N9 t-I' 1
1 1
- j. Fire Protection System Pl . . Are valves 3FPW-663 and 668 (P&ID No. 25212-26946 Sh. 2 coordinates C-4 and B-4) Appendix 3, Type C, leak rate tested?
Response
Yes. These are identified in the IST Manual as Appendix 3 Type "C" valves.
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ICD i.
Control Building HVAC System Ql. Is credit taken for operability of the control room chilled water system to meet post-accident control room habitability requirements. If so, all-applicable active system valves should be included in the IST program and '
, be tested to the code requirements. 1
Response
We have reviewed the control room chilled water system and determined that there are no active valves per IWV 2100. -
Ql-1
t71 i'
Containment Structure Ventilation System RI. Is valve 3CVS-Vl9 ever required to change position in order to mitigate the consequences of an accident, shutdown the reactor to the cold shutdown condition or to perform any other safety-related function? If so, it is an active valve and must be exercised and have its stroke time measured ' quarterly in accordance with the code. If not, it should be identified as being a passive valve in the IST program.
Response '
Valves 3CVS-V!9 and V20 are required to be closed per Technical Specification 3/4.6.5.1 in modes 1-4. This valve will be considered as passive in the IST Manual.
I Rl-1
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l
- 51. Are valves 3LMS-II,12,13, and 14 (P&lD No. 25212-26954 coordinates G-6, G-7 and G-8) Appendix 3, Type C, leak-rate tested.
Response
No. These valves are not Appendix 3 type tested.
l l
S1-1
IT9 Emergency Diesel Generator System T1. The NRC Staff position is that the emergency diesel generators perform a safety-related function and that the appropriate valves in the emergency diesel air start, cooling water and fuel oil transfer systems should be included in the IST program and be tested in accordance with the code.
Review all active valves in these diesel generator subsystems to determine if they should be included in the IST program.
Response
The fuel oil transfer systems valves 3EGF-VI, V3, V7, and V9 will be included in .
the ISTl manual and tested quarterly. The attached Relief Request R-25 addresses alternate testing of the emergency generator air start valves. We have reviewed the service water supply system to the emergency diesel generator and determined that there are no additional active valves.
In addition to the review of ASME systems supporting the diesel, the diesel skid-mounted equipment has also been reviewed to ensure that diesel testing is capable _ of identifying component problems. It has been determined that the Technical Specification surveillance testing for the diesel is adequate to demonstrate operability of all the skJd-mounted equipment.
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Relief' Request': R-25 :
Valves: 3EGP*V25, 26, 51,.52 Category: ' B _.
h Code' Class: 3 ,
1 Function: , Emergency Diesel Generator' Air START Solenoid Valves.
. Test Requirements: Full stroke testing quarterly.
~
Basis for Relief: It is 1mpractical to measure'theilimiting value of full-stroke time of these valves. These valves do not have remote position indication. Measuring the stroke time of these valves by. observing stem travel' would require disassembly of the-operator. The safety function of these valves is to open to' support the: start-up of its respective diesel to provide rated frequency and voltage in less than ten seconds.
Successful start-up of each emergency diesel generator within the above specified conditions is dependent upon the proper operation and speed of these valves. Measuring start-up time of each emergency diesel generator is an indirect method of verifying the degradation of these valves and meets the intent of the code. Upon failure of the diesel generators to start as required, corrective action shall be taken to assure proper diesel start-up conditions.
-Alternate Testing: These valves shall be full-stroke tested using the I emergency diesel generator start-up times per Surveillance Procedure 3646A.1, 2 as an indirect indication of valve operability.
7~ 1 ~ 2-i
156 Pump Testing Program
- 1. How are the pump inlet pressures and flowrates measured for the service water pumps during quarterly testing?
Response
a) The service water inlet pressure is measured by taking the ' tide level (measured at the pump house local indication). The inlet pressure ir. then !
converted to pressure by following formula:
Pressure = (tide level (f t) x .43 (#/f t))
(Tide level must be between 0 to 4'.)
b) The flow rate is measured by shedding all loads except for CCI, CCE, and EDG bypass flow, and the output from one CCP heat-exchanger is throttled to 9000 gpm 1500 at the heat exchanger outlet. (Per procedure SP 3626.7, Section 7.164). - This flow is determined using 35WPF143A/B at the main control board (MB-1).
(Refer to Relief Request 26.)
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i' Relief Request: R-26 Pumps: 3SWP* PIA, PIB, PIC, PID Code Class: 3 Function: Pumps are required to perform a function in shutting down the reactor, or mitigating the consequences of an accident, and are provided with an emergency power source.
Test Requirements: IWP-4200 Pressure Instruments.
Basis for Relief-: The service water pumps are vertical shaf t pumps with no direct means to obtain the inlet pressurement as required by IWP-4200.
Alternate Testing: The inlet pressure will be calculated based on the water level above the. pump inlet. This method provides sufficient information for evaluation of the hydraulic condition of the pumps.
NOTE: The flow rate is measured by shedding all loads except for a CCI, CCE and EDG bypass flow (the are very minimal flow losses),
the output through one CCP heat exchanger is then throttled to the reference flow identified in the surveillance procedure.
1-2
IrB Pump Testing Program
- 2. How are the pump inlet pressures measured for the MCC and rod control area service water booster pumps during quarterly testing?
Response -
Temporary QA pressure gauges are installed at the suction of the pumps when the test is performed.
i I
2-1 i
)
!f9 Pump Testing Program
- 3. How are the pump flowrates measured for the boric acid transfer pumps during quarterly testin,g?
Response
The pump flow rates are measured through the flow transmitter (3CHS*FT110) and the flow is recirculated back to the respective boric acid tanks.
3-1
/G o a ,
Pump Testing Program
- 4. How are the pump inlet pressures measured for the emergency generator fue! oil transfer pumps during quarterly testing?
Response
Inlet pressure for the fuel oil transfer tank cannot be measured as we do not have any instrumentation. The tank level is monitored and per Technical Specifications the level cannot go below 87E Refer to Relief Request R-27.
4-1
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Relief Request: R-27 Pumps: 3EGF* PIA, IB, 3C, ID l
Code Class: 3 1
i Function: Pumps provide the emergency diesel day tanks with L proper fuel oil supply.
Test Requirements: 1WP-4200 Pressure Measurements.
Basis for Relief: The fuel oil transfer pumps take suction directly from the fuel oil storage tanks and discharges to the fuel cil day' tank. No inlet (suction) pressure l indication is available. Pump discharge pressure is aveilable and will be recorded.
Alternate Testing: The fuel oil storage tanks are required per Technical Specifications 3.8.1.1.b.2 to be filled to e minimum volume of 88% (32,760 gallons). The discharge pressure will be recorded quarterly and the ASME limits per Table IWP-3100-2 will be applied to this reading.
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16 L
.O t Pump Testing Program
- 5. How are the pump flowrates measured for the steam generator auxiliary
' feedwater pumps during quarterly testing?
Response .
Controlotrons are installed on~ the recirculation path to the demineralized water storage tank.
1 1
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5-1
_ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ - - _ _ _ - _ _ - - - - - - - - - - _ - - - - - - - - - - - - --------------J
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Pumn Testing Program
- 6. Provide the basis for the proposed pump vibration velocity acceptance criteria (refer to Relief Request No. R-19).
Response
Refers to the revised Relief Request R-19 and the revised Table IWP-1.
6-1
IsY 4 9 Relief Request: R-19 Specific relief is being requested from the Sub-section IWP-4500 for the method of testing and allowable ranges (Table 3100-1 and 37)0-2) for pump vibration measurements of all safety-related pumps.
Code Requirement: At least one Displacement Vibration Amplitude (peak-to peak composite) measurement shall be taken during each inservice test and the allowable ranges, in relation to reference values, are tabulated in Table IWP-3100-2.
Basis for Relief: Experience has shown that measurement of overall vibration amplitude in mils does not provide the desired early warning of pump degradation. Vibration amplitude is adequate for measuring unbalance, misalignment, and other low frequency failure modes.
It does not give early earning of bearing degradation since the magnitude of higher frequency vibrations created by such degradation is 10 to 1,000 times lower than the normal pump movements. Experience at Northeast Utilities has shown that monitoring pump vibration velocity (in/sec) provides earlier warning of pump degradation. Collection and review of vibration " signatures" (plots of vibration velocity vs. frequency) over a range from slightly below running frequency to several times running frequency provides optimal early warning of pump degradation.
6-2
1c ,- 1 i
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-Alternate Testing: 'In lieu of measuring overall amplitude (mils), the following vibration monitoring program will be
- l. implemented:
Vibration will be monitored at least quarterly using equipment which collects vibration velocity signatures. Overall, vibration velocity (in/sec'RMS) will be compared to the following acceptance criteria:
NOTE: This acceptance criteria is based on Rev.
10 of O&M-6.
Acceptance Range - O to 2.5 times Reference Velocity Alert Range - > 2.5 to 5 times' Reference Velocity but not greater than 0.325 in/sec. (RMS)
Required Action Range - > 5 times Reference Velocity but not greater than 0.07 in/sec. (RMS)
Reference Velocity shall be the average overall velocity determined during an inservice test at reference conditions when the pump is known to be operating acceptably.
In addition to the above quantitative analysis of overall vibration levels, vibration signatures will be reviewed at least quarterly to identify potential bearing degradation or other developing faults. When potential faults are identified, action as required for a pump in the Alert Range of vibration will be initiated.
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Pump Testing Program l
- 7. -
' Does the "controfotron" provide readout repeatability within the accuracy limits of Section XI, Table IWP-4110-l?
Response
The current controlotrons being utilized arelwithin 13 percent of full scale. We are currently purchasing controlotrons that are within 1 percent of full scale.-
7-1
s 1 ~) O 4> %
Pump Testing Program
- 8. Are the pump vibration velocity measurements taken at the locations specified in Section XI, IWP-45107 Do the vibration instruments used to make these measurements meet the accuracy and range requirements of IWP-4110 and 4120?
Response
The pump velocity measurements are taken at locations specified in IWP4510.
The vibration instrumentation used to take data meets the accuracy requirements specified in Table IWP-4110-1 and the digital readout meets the range requirement of IWP4120.
l S-1
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