ML20150E422
| ML20150E422 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 07/08/1988 |
| From: | Hood D Office of Nuclear Reactor Regulation |
| To: | Matthews D Office of Nuclear Reactor Regulation |
| References | |
| TAC-61271, TAC-61272, NUDOCS 8807150126 | |
| Download: ML20150E422 (3) | |
Text
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i July 8, 1988 t
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. Docket Nos.:
50-369 and 50-370 i
MEMORANDUM FOR:
David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II FROM:
Darl S. Hood, Project Manager Project Directorate II-3 Division of Reactor Projects-I/II
SUBJECT:
FORTHCOMING MEETING REGARDING PUMP AND VALVE INSERVICE TESTING PROGRAM, MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 (TACS61271/61272)
DATE & TIME:
August 16,17, and 18 8:30 a.m. - 4:30 p.m.
LOCATION:
ficGuire Site Cornelius, N.C PURPOSE:
To review the McGuire Station Pump and Valve Inservice Testing Program.
- PARTICIPANTS:
NRC DUKE POWER COMPANY T McLellan P. Nardocci D. Hood R. Sharpe, et. al.,
T. Cook (EG8G)
N. Stockton (EG&G) et al.,
Original signed by:
Darl S. Hood, Project flanager Project Directorate 11-3 Division Reactor Projects-I/II
Enclosure:
Agenda cc: See next page
- Meetings between NRC technical staff ard applicants for licenses are open for interested members of'the public, petitioners, intervenors, or other parties to attend as observers pursuant to "Open Meeting Statement of NRC Staff Policy," 43 Federal Register 28058, 6/28/78, PM:@s H w
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July 8, 1988 Docket Nos.:
50-369 and 50-370 MEMORANDUM FOR:
David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II FROM:
Darl S. Hood, Project Manager Project Directorate 11-3 Division of Reactor Projects-I/II
SUBJECT:
FORTHCOMING MEETING REGARDING PUMP AND VALVE INSERVICE TESTING PROGRAM, MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 (TACS61271/61272)
DATE & TIME:
August 16, 17, and 18 B:30 a.m. - 4:30 p.m.
LOCATION:
McGuire Site Cornelius, N.C PURPOSE:
To review the McGuire Station Pump and Valve Inservice Testing Program.
- PARTICIPANTS:
NRC DUKE POWER COMPANY T McLellan P. Nardocci D. Hood R. Sharpe, et. al.,
T. Cook (EG&G)
N. Stockton (EG&G) et. al.,
L Darl S. Hood, Project Manager Project Directorate !!-3 Division Reactor Projects-I/II
Enclosure:
Agenda l
cc: See next page
- Meetings between NRC technical staff and applicants for licenses are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to "Open Meeting St.atement of NRC Staff Policy," 43 Federal Register 28058, 6/28/78.
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Duke Power Company McGuire Nuclear Station cc:
Mr. A.V. Carr, Esq.
Dr. John M. Barry Duke Power Company Department of Environmental Health P. O. Box 33189 Mecklenburg County 422 South Church Street 1200 Blythe Boulevard Charlotte, North Carolina 28242 Charlotte, North Carolina 28203 County Handger of Mecklenburg County Mr. Dayne H. Brown, Chief 720 East Fourth Street Radiation Protection Branch Charlotte, North Carolina 28202 Division of Facility Services Department of Human Resources 701 Barbour Drive Mr. Robert Gill Raleigh, North Carolina 27603-2008 Duke Power Company Nuclear Production Department Mr. H. B. Tucker, Vice President' P. O. Box 33189 Nuclear Production Department Charlotte, North Carolina 28242 Duke Power Company 422 South Chruch Street J. Michael McGarry, III, Esq.
Charlotte, North Carolina 28242 Bishop, Liberman, Cook, Purcell and Reynolds 1200 Seventeenth Street, N.W.
Washington, D. C.
20036 Senior Resident Inspector c/o U.S. Nuclear Regulatory Commission Route 4. Box 529 Hunterville, North Carolina 28078 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 S. S. Kilborn Area Manager, Mid-South Area ESSD Projects Westinghouse Electric Corporation NNC West Tower - Bay 239 l
P. O. Box 355 Pittsburgh, Pennsylvania 15230 l
I
AGENDA June 16, 1988 Docket Nos.:
50-369 and 50-370 Mr. H. 8. Tucker, Vice President Nuclear Production Department Duke Power Company 422 South Church Street Charlotte, North Carolina 28242
Dear Mr. Tucker:
SUBJECT:
SUPPLEMENTAL RE0 VEST FOR AD0!TIONAL INFORMATION RECARDING INSERVICE TESTING PROGRAM - MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 (TACS 61271/61272)
The NRC staff, with technical mssistance from EGAG Idaho, Inc., is reviewing the McGuire Nuclear Station Pump ano Valve Inservice Testirg (IST) Program for the first 10 years of operation.
The review is baseo upon Unit I revisions through Revision 10 and Unit 2 revisions through Revision 6.
We find that additional information, identified by the enclosure, is needed to complete this review.
The enclosure is stpplainental to the request to which you responded March 31, 1983.
As acknowledged in your letter of May 6,1988, forwarding Unit 1 IST Revision 10 and Unit 2 IST R6 vision 6, tha 4RC and Duke have establisheo a plan for corr % tic. uf de review by th' en1 of 1988. The plan includes a Charlotte meeMng in e6rly August for ~. uke to provide support information to finalize the IST Program. The purpose of the meeting is to resolve any outstanding review issues.
The enclosure will be used as an agenda for the meeting to the extent that it contains outstanding items.
You are encouraged to minimize the agenda items by responding in advance of the meeting where possible. Where written responses have r.ot been provided in advance of the meeting, written responses I
should be provided curing the meeting.
It has been our experience elsewhere of working meetings to finalize IST reviews in a timely manner that the succe: #
1s d'spendent upon substantive responses to issues and upon management support l
at the decision making level.
The reporting and/or recordkeeping reouirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
If you have questions regarding the enclosure, contact me at (301) 492-1442.
Sincerely, i
Original signed by:
l Darl Hood, Project Manager l
Project Directorate II-3 Division of Reactor Projects I/II
Enclosure:
l As stated cc: See next page
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Mr. H. B. Tucker Duke Power Company McGuire Nuciear Station CC' Mr. A.V. Carr, Esq.
Dr. John M. Barry Duke Power Company Department of Environmental Health P. O. Box 33189 Mecklenburg County
.. 422 South Church Street 1200 Blythe Boulevard Charlotte, North Carolina 28242 Charlotte, North Carolina '28203 County Manager of Mecklenburg County Mr. Dayne H. Brown, Ch 7
720 East Fourth Street Radiation Protection Branch Chorlotte, North Carulina 28202 Division of Facility Services Department of Human Resources 701 Barbour Drive Mr. Robert Gill Raleigh, North Carolina 27603-2008 Ouke Power Company Nuclear Production Department P. O. Box 33189 Charlotte, North Carolina 28242 J. Michael McGarry, III, Esq.
Bishop, Liberman, Cook, Purcell and Reynolds 1200 Seventeenth Street, N.W.
Washington, D. C.
20036 Ser.ior Resident Inspector c/o U.S. Nuclear Regulatory Connission Route 4, Box 529 Hunterville, North Carolina 28078 Regiunal Administrator, Region II U.S. Nuclear Regulatory Connission, 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 S. S. Kilborn Area Manager, Mid-South Area ESSD Projects Westinghouse Electric Corporation MNC West Tower - Bay 239 P. O. Box 355 Pittsburgh, Pennsylvania 15230
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ENCLOSURE McGUIRE NUCLEAR STATION, UNITS 1 AND 2 pVMP AND VALVE INSERVICE TESTING PROGRAM REQUEST FOR ADDITIONAL INFORMATION 1.
VALVE TESTING PROGRAM A.
General Questions and Coments 1.
Provide the documentation that ensures that IW-3300 is being met (remote position indication virification).
2.
The NRC nas concluded that the applicable leak test precedures and requirements for containment isolation valves are determined by 10CFR50, Appendix J.
Relief from paragraphs !W-3421 through 3425 for containment isolation valves presents no safety problem since the intent of IW-3421 through 3425 is met by Appendix J l
requiretents, however, 3he licensee shall comply with Paragraphs l
IWV 3425 and 3427.
3.
Provide i listing of all vs.1ves that are Appendix J. Type C, leak rate tested which are not included in the IST program and Categorized A or AC?
4.
The NRC staff has identified rapid-acting power operated valves as those which stroke in 2 seconds or less.
Relief may be obtained from the trending requirements of Section XI, Paragraph IW-3417(a), however, in order to obtain this Code relief the staff does require that the licensee assign a maximum limiting stroke time of 2 seconds to these valves and comply with the requirewnts of IW-3417(b) when the 2 second limit is exceeded.
General Relief Request ! does not comply with this staff position.
S.
Providethelimitingvaluesoffull-stroketimesforallTower operated valves in the McGuire Nuclear Station, Units 1 and 2, l
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IST programs for our review.
What are the bases used to asr in the limiting values of full-stroke time for these valves?
6.
When flow through a check valve is used to indicate a full-stroke exercise of the valve disk, the NRC staff position is thac 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-stroke exercising unless it can be s9own (by some n,eans such as measureme1t of the differe9tial 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 test designated "MT" satisfy this NRC Staff position?
7.
provide the documentation.that ensures that IWV-3415 is being met (fail-safe testing of valves).
8.
Section (I specifically makes provisions for testing valves during :old shutdowns when it is impractical to exercise these valves parterly during power operation.
A formal relief request is not required, however, the licensee should include a cold shutdow, justification in the IST program.
The cold shutdown justifi:ation bases should indicate the negative consequences that ma4e quarterly testing during operation impractical such as endangering personnel, damaging equipment, or resulting in a plant 19utdown.
10.
The valve testing frequency should be indicated in the valve tables.
Only a portion of the valves in the McGuire IST programs current'j have the testing frequency identified in the valve tables.
11.
Does the fuel pool cooling system perform a safety function at the McGuire Nuclear Station?
If so, the appropriate pumpa and valves should be included in the !$T programs and tested in 2
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<. 00 2 cce accordance with the requirements of Section XI to the extent practical.
12.
What is the frequency of the testieg designated SP in the valve test programs?
13.
The NRC staff position is that valves that serve both a pressure boundary isolation function and a containment isolation function must be leak tested to both the Appendix J and the Section XI requirements.
Identify the valves, if any, at McGuire Nuclear Station that serve both a pressure boundary isolation function and a containment isolation function.
performed on these valves?
What leak rate testing is B.
Annulus Ventilation System 1.
Why are valves 1(2)IVE-10A identified as passive valves?
i 2.
Review t9e safety function of valves 1(2)!VE 5A and 6B to determine if they should be categorized A.
C.
Auxiliary Feedwater System 1.
Concerning the relief request for valves 1(2)CA-60A, what prevents measuring the stroke time of these valves when they are exercised quarterly?
What is the frecuency of the stroke timing now being done, i.e., during ESF testing?
i 2.
How are the following valves verified to full stroke exercise quarterlj?
gg 112)CA 8 1(2)CA-10
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1(2)CA-12 112)CA-22 1(2)CA-26 1(2)CA-31 3.
What is the current frequency of the stroke t! ming for valter*"
1(2)CA-20AB?
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What is 9he safety grade water source for the AIW pu.rps?
Review the safety function of the following valves to determine if they should be included in the IST program and tested to Section XI requirenents:
Valve p&l0 Valve pelo 1(2)CA-)
1(2)S92-1.1 1(2)CA-4 1(21592 1.1 1(2)CA-5 1(2)S92-1.1 1(2)CA-6 1(2)CA-5 1(2)592-1.1 1(2)592-1.1 0.
Boron Recycle System 1.
If the only practical method of verifying valve closure is leak rate testing, then closure verification can be demonstrated each refueling outage.
However, it must be done each refueling outage irrespe:tive of the Appendix J reovired frecuency.Does the testing frecuency for valves 1(2)NB-262 conform to this position?
E.
_BreathinQ Air System 1.
If the aqly practical method of verifying valve closure is leak rate testing, then closure verification can be demonstrated each refueling outage.
However, it must be done each refueling outage irresos:tive of the Appendix J requirad frequency. Does the testing frequency for valves 1(2)VB-50 conform to this position?
F.
Chemical and Volume Control System 1.
Are valves 1(2)NV-94AC and 958 ever required to perform a containnent isolation function?
2.
Review tne safety function of valves 1(2)NV-78, 457A, 458A EE
, and 459A to determine if they should be Categorized A.
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3.
De valves 1(2)NV-12 perform a safety function in the closed position?
m 4.
How will full-stroke exercising valves 1(2)NV-225 and 231 cuarterly result in an increase in RCS boren inventory?
4
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Review the safety function of the following valves co determine if they should be included in the IST program and tested to Section XI requirements:
Valve D&10 Valve Pa!0 1(2)NV-45 1(2)554-1.0 1(2)NV-29 1(2)554 1.0 1(2)NV-77 1(2)554-1,1 1(2)NV-61 1(2)554-1.1 1(2)NV-14 1(2)S54-1.2 1(2)NV-15 1(2)S54-1.2 1(2)NV-20 1(2)554-1.2 1(2)NV-841 1(2)554-1.2 1(2)NV-218 1(2)554-3.0 1(2)NV-241 1(2)S54-3.0 2NV-1044 2554-3.0 2NV-1046 2554-3,0 1(2)NV-264 1(2)554-3.1 1(2)NV-472 1(2)554-3.1 1(2)NV-267A 1(2)554-3.1 1(2)NV-2658 1(2)S54-3.1 1(2)NV-411 1(2)S54-5.0 1(2)NV-413 1(2)S54-5.0 G.
Component Cooling System 1.
De valves 1(2)KC-5, 8, 11, and 14 perform a safety function in the ope, and closed positions?
If so, the v41ves must be exercised to both positions.
2.
Review the safety function of valves 1(2)KC 972 (P&!D 1(2)573-1.1) to determine if they should be included in the IST program and tested to Section XI recuirements.
3.
Review the safety funct?;n of valves 1(2)KC-3158, and 3055 to determine if they should be categorized A.
H.
Containment Air Release and Addition System 1.
Clarify the testing being performed on valves 1(2)QV-1A, 2B, 58, and 6A.
1.
Containment Durge Ventilation i
1.
Clarify *he proposed alternate testing in the relief request for all containment purge ventilation category A valves.
The L& toke tirna of all power operated valve must be measured every time the i
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-i valve is full-stroke exercised as required in Section XI, paragraph IWV-3413(b).
I J.
Containment Soray System i
i 1.
The NRC Staff position is that check valves must be full-stroke I
exercised.
If Code required frequency is impractical, then the licensee must request relief to perform the testing at a lesser frequency.
However, relief requests seeking exemption for never full-st oke exercising check valves will not be granted.
Tne relief cequest for the following valves will be affected by this Staff position:
112)NS-13 1(2)NS-16 1(2)NS-30 1(2)NS 33 1(2)NS-41 1(2)NS-46 2.
Review the safety function of the following valves to determine if they should be categorized A:
ll2)NS-128 1(2)NS-1SB 1(2)NS-29A 112)NS-32A 1(2)NS-38B 1(2)NS 43A 4
K.
Diesel Generator Room Sump Pumo System i
1.
De valves 1(2)WN-3, 5, 11, and 13 perform a safety function in the closed position?
L.
Diesel Generator Starting Air System 1.
Provide P& ids MC-1609-4.0 and 2609-4.0 for our review.
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Equipment Decontamination System
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1.
What ty)4 of valve is 2WE-237 Is the AC categorization for this valve c3* rect?
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Licuid Waste Recycle System 1.
Review the safety function of valve IN!-266A to determine if it should be categorized A.
O.
Main Steam Supply to Auxiliary Equipment 1.
How are valves 1(2)SA-5 and 6 verified to full-stroke open Quarter 1/7 P.
Main Steam Vent to Atmosphere 1.
Review the safety function of the following valves to determine if they should be included in the IST program and tested to Section Al requirements:
Valve P&lD
_ Valve P&lD 1(2)$V-25 1(2)593-1.3 1(2)$V-26 1(2)554-1.3 1(2)SV-27 1(2)S93-1.0 1(2)SV 28 1(2)593-1.0 Q.
Nuclear Samoling 1.
What tyao of valves are 1(2)NM-420 and 4217 Should these valves be categorized AC7 R.
Nuclear Service Water System 1.
De valves 1(2)RN-28 and 30 perform a safety function in both the open and closed positions?
If so, both positions must be verified during valve testing.
I 2.
Valves 24N-418 and 2RN-43A are listed in both Unit I and Unit 2 valve taales.
Is this correct?
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The NRC Staff position is that the PORVs should be exercised during cold shutdown or prior to establishing conditions where i
the POR/s are utilized for low temperature overpressure i
protect'en.
The relief rcquest for the PORVs will be affected by this Staff position.
2.
What is the full stroke test frequency for valves 1(2)NC-27C and 29C?
3.
Provide D&l0 MC-1553-2.1 for our review.
4.
Are valves 1(2)NC-141 and 142 passive vr.lves?
T, Refueling Water System 1.
Provide 4 detailed technical justification for not full-stroke exercising valves 1(2)FW-28 durir.g cold shutdowns.
2.
Why are valves 1(2)FW-52 designated passive while all other small i
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check vslves that perform a thermal relief function are not?
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Residual Heat Removal System i
1.
What tyoe of leak testing is performed on valves 1(2)ND-18 and l
2AC? Do these valves perform both a pressure isolation function l
and a containment isolation function? See general coment A.13.
2.
Provide a detailed technical justifkation for not full-stroke exercising valves 1(2)ND-8 and 23 during cold shutdowns.
3.
Provide a more detailed technical justification for not full-stroke exercising valves 1(2)ND-70 quarterly and during cold shutdowns, e
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4 Why must both trains of the residual heat removal system be removed from service to test the 1(2)ND-58A valves?
V.
Safety injection System 1.
Review the safety function of valves 1(2)N!-12 to determine if they should be categorized AC.
2.
Review the safety function of valves 1(2)NI-11 [P&ID 1(2)S62-1.0) to determine if they should be included in the IST program and tested to Section XI requirements.
3.
How are valves 1(2)NI-59, 70, 81, and 93 verified to full-stroke open duaing refueling outages?
4.
How are valves 1(2)N1-60, 71, 82, and 94 verified to full-stroke open during cold shutdowns?
5.
Review the safety function of valves 1(2)NI-121A and 1528 to determine if they should be categorized A.
6.
What is the safety function of valves 1(2)NI-122B?
l 7.
Describe the procedure used to full-stroke exercise the following valves during refueling outages:
112)NI-124 1(2)NI-128 1(2)NI-156 112)NI-157 1(2)NI-159 1(2)NI-160 8.
How are valves 1(2)NI-125, 125, 129, and 134 verified to full-stroke during cold shutdowns.
9.
Review the safety function of the following valves to determine l
if they should be categorized A:
ae if2)NI-162A 1(2)N!-173A 1(2)N!-1788 112)NI-1848 1(2)N!-185A L
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10.
Review tne safety function of the following valves to determine if they should be included in the !$7 program as category A valves and tested to Section XI requirements:
Valve P&!O 1(2)N!-163 1(2)562-3.1 1(2)N!-174 1(2)562-3.1 1(2)N1 179 1(2)562-3.1 11.
Describe how the interlocks mentioned in the relief request for valves *.(2)NI-1848 and 185A preclude valve operation.
12.
How are valves 1(2)NI-175, 176, 180, and 181 full-stroke exercised during cold shutdowns?
13.
The NRC Sranch Technical Position, RS8 5-1, establishes requirenents for taking reactor plants from power operation to cold sh;tdown using only safety-grade equipment. To comply with this position, credit is normally taken for the safety injection accumuister vent paths and/or the accumulator motor operated isolatian valves.
Evaluate the safety function of the following valves to determine if they should be included in the !$T program and tested to the Code requirements:
Va l ve, P&fD Valve Pa10 1(2)N!-50 1(2)S62-2.0 1(2)NI-54A 1(2)S62 2.0 1(2)NI-61 1(2)S62-2.0 1(2)NI-65B 1(2)552-2.0 1(2)N!-72 1(2)562-2,1 1(2)NI-76A 1(2)$62-2.1 1(2)N!-83 1(2)562-2.1 1(2)NI-84 1(2)S62-2.1 1(2)NI-888 1(2)S62 2.1 14 Review the safety function of the following valves to determine l
if they should be included in the IST crogram and tested to Section XI requirements:
Valve P&l0 Valve P610 1(2)N!-2428 1(2)S62-4.0 1(2)N!-243A 1(2)5f2-4.0 1(2)N!-244B 1(2)S62-4.0 1(2)NI-245A 1(2)$62-4.0 IN!-266A 1562-4.0 10
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15.
What type of the valves are the following:
1N!-248 1N1-249 1NI-250 1N!-251 INI-252 IN!-253 2.
PUMP TESTING PROGRAM 1.
The dev ations from the Code recuirements discussed in Item I.A and B, page !.1-1, have not been indicated on the pump table.
2.
Section XI recuires that both flow and differential pressure be measured during the performance of pump testing, i.e., all quantit'es required by Table IWP-3100 1 should be recorded and that la:k of installed instrumentation is not a suitable long term justification for not. performing the required Section XI testing.
Item 1.C does not agree with this Staff position.
3.
Has McGJire Nuclear Station attempted to procure portable vibration instrumentation that meets the accuracy requirements of Section XI?
4 Is the pump vibration monitoring program conducted utilizing units of vibration displacement or vibration velocity?
5.
Relief may be granted from the requirement of Section XI to measure pump bearing temperature annually, however, specific relief must be requested describing the difficulties encountered in each case.
These relief reques,ts will then be reviewed on a case by case basis.
Item I.E does'not agree with this Staff position.
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6.
Is the flow rate of the diesel generator fuel oil transfer pumps determined while the diesel engine is running?
7.
In those cases where instrumentation is not installed to permit monitoring pump performance, individual specific relief must be 11
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reques%e9.
j This requirement will affect the pump test program for the diesel fuel oil transfer pumps, diesel generator i
sump pumss, and the standby makeup pumps.
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.s DISTRIBUTION FOR MEETING NOTICE DATED: July 8, 1988 Facility: McGuire Nuclear Station, Units 1 and 2*
F0ecket' File}
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Local POR POII-3 Reading T. Murley/J. Sniezek 12-G-18 F. Miraglia 12-G-18 S. Varga 14-E-4 G. Lainas 14-H-3 D. Matthews 14-H-25 P DC l 14-H-25 D. Hood 14-H-25 W. Lanning 11-E-22 OGC-Rockville 15-B-18 E. Jordan HNBS-3302
- 8. Grimes 9-A-2 L. McLellan 9-H-3 ACRS (10)
H-1016 GPA/PA 17-F-2 V. Wilson 12-H-5 D. Morley 12-E-4 B. Troskoski RI!
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