ML20195J625
| ML20195J625 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 06/16/1988 |
| From: | Hood D Office of Nuclear Reactor Regulation |
| To: | Tucker H DUKE POWER CO. |
| References | |
| TAC-61271, TAC-61272, NUDOCS 8806290176 | |
| Download: ML20195J625 (15) | |
Text
r O June 16, 1988 Docket Nos.: 50-369 DISTRIBUTION:
~
and m-370 TeocketJ116 EJordan NRC PDR BGrimes Locol PDR ACRS (10)
PPM-3 Reading Mr. ii. B. Tucker, Vice President MCliUIRE READING Nuclear Production Department SVarga Duke Power Company Glainas 422 South Church Street DMatthen Charlotte, North Carolina 28242 flRood DHcod
Dear Mr. Tucker:
SUBJECT:
SUPPLEMENTAL REQUEST FOR ADDITIONAL INFORMATION REGARDING INSERVICE TEST!NG PROGRAM - MCGUIRE HUCLEAR STATION, UNITS 1 AND 2 (TACS 61271/61272)
The NRC staff, with technical assistance from EG8G Idaho, Inc., is reviewing the McGuire Nuclear Station Pump ana' Yalve Inservice Testir.g (IST) Program for the first 10 years of operation. The review is based upon Unit I revisions through Revision 10 and Unit 2 revisions through Revision 6.
We find tht?.
additional information, identified by the enclosure, i needed to complate this review. The enclosure is supplemental 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 Revision 6, the NRC and Duke have established a plan for completion of the review by the end of 1988. The plan includes a Chorlotte meeting in early August for Duke to provide support information to fin 611ze the IST PrJgram. The nurpose of the meeting is to resolve any outs 1!anding review-issues. The enclosure wi!1 be used as an acenda for the teeting to the extent that it contains cutstanding items.
You are encoureged to ininimize the agenda items by rcspending in advance of the meeting where possible. Where written responses have not been provided ir advance of the meeting, written rerponses l
should be provided during the meeting.
It has been our experience e m wnere that the success of w0rking meetings to finalize IST reviews in. tirely manner is dependent upon substt.ntive responses to issues and upon managennt support at the decision making level.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ton respondents; therefore. *B clearance is not regt' ired under P.L.96-511.
If you have questions regarding the encinure, ccntact me at (301) 492-1442.
Since rely, Original signed by:
8806290176 0a0616 EDR ADOCK 0S000369 7
PDR Darl Hood, Project Manager Project Directorate 11-3 Division of Reactor Projects I/II l
l l
Enclosure:
As stated cc: See next page l
2 3U L PDiJ-3 PH:PDII-3 011-3 l
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DHood tth
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June 16, 1988 s
Docket Nos.:
50-369 DISTRIBUTION:
and 50-370 DEeI7TTe-EJordan NRC PDR BGrimes Local PDR ACRS (10)
PDII-3 Reading Mr. H. B. Tucker, Vice President MCGUIRE READING Nuclear Production Department SVorga Duke Power Company Glainas 422 South Church Street DMatthews Charlotte, North Corolina 28242 HRoud DHood
Dear Mr. Tucker:
SUBJECT:
SUPPLEMENTAL RE0 VEST FOR ADDITIONAL INFORMATION REGARDING INSERVICE TESTING PROGRAM - MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 (TACS 61271/61272)
The NRC staff, with technical assistance from EG1G Idaho, Inc., is reviewing the McGuire Nuclear Station Pump ano Valve Inservice Testing (IST) Program for the first 10 years of operation. The review is based upon Unit I revisions through Revision 10 and Unit 2 revisions through Revision 6.
We find that additional informotion, identified by the enclosure, is needed to complete this review. The enclosure is supplemental 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 Revision 6, the NRC and Duke have estaF11shed a plan for completion of the review by the end of 1988. The pita includes a Charlotte meeting in early August for Duke 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 should be provided during the meeting.
It has been our experience elsewhere that the success of working meetings to finalize IST reviews in a timely manner is dependent upon substantive responses to issues and upon management support at the decision making level.
The reporting and/or recordkeeping requirements t.ontained 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, Original signed by:
- irl Hood, Project Manager
'c oject Directorate II-3 Jivision of Reactor Projects I/II
Enclosure:
As stated cc:
See next page R 3ll L
g-3 PM:PD!I-3 DII-3 DHoog/AA a(thews
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-n Mr. H. 8. Tucker Duke Power Company McGuire Nuclear S'tation cc:
Mr. A.V. Carr, Esq.
Dr. John M. Barry Duke Power Company Department of Environmental Health P. 0. 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, Chief 720 East Fourth Street Radiation Protection Branch Chorlotte, 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 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 Senior Resident Inspector c/o U.S. Nuclear Regulatory Commission Route 4, Box 529 Hunterville, North Carolina 28070 Regional Administrator, Region II U.S. Nuclear Regulatory Commission, 101 Marietta Street, N.W., Suite 2900 Atlante, 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
ci/16/E5 09:47 EGLG ID. TSALE MC. 003 003 ENCLOSURE b
McGUIRE NUCLEAR STATION, UNITS 1 AND 2 PUMP AND VALVE INSERVICE TESTING PROGRAM REQUEST FOR A00lT10!iAL INFORMATION 1.
VALVE TESTING PROGRAM A.
General Questions and Comments 1.
Provide the documentation that ensures that IWV-3300 is being met (remote position indication verification).
2.
The NRC nas concluded that the applicable leak test procedures and requirements for containment isolation valves are determined by 10CFR50, Appendix J.
Relief from paragraphs IWV-3421 through 3425 for containment isolation valves presents no safety problem since the intent of IWV-3421 through 3425 is met by Appendix J requirements, however, the licensee shall comply with Paragraphs l
IWV-3425 and 3427, 3.
Provide a licting of all valves that are Appendix J, Type C, leak rate tested which kre 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 IWV-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 requirements of IWV-3417(b) when the 2 second limit is exceeded.
General Relief Request I does not comply with this staff position.
S.
Provide the limiting values of full-stroke times for all'p5wer operated valves in the McGuire Nuclear Station, Units 1 and 2, l
l l
1
IST programs for our review.
What are the bases used to assign 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 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-stroke exercising unless it can be snown (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 test designated "MT" satisfy this NRC Staff position?
7.
Provide the documentation that ensures that !WV-3415 is being met (fail-ssfe testing of valves).
8.
Section XI specifically makes provisions for testing valves during :old shutdowns when it is impractical to exercise these valves QJarterly 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 mar,e 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'y 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 pumps.and valves should be included in the IST programs and tested in 2
Ea!.3 ID. T5A?.E tc. 002 002 accordance with the requirements of Section XI to the extent practical.
12.
What is the frequency of the testing 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 reoutre, ants.
Identify the valves, if any, at McGuire Nuclear Station that serve both a pressure boundary isolation function and a co9tainment isolation function.
performed on these valves?
What leak rate test'ing is B.
Annulus Ventilation System 1.
Why are valves 1(2)!VE-10A identified as passive valves?
i 2.
Review tie safety function of valves 1(2)IVE-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 1
, what prevents measuring the stroke time of these valves when they are exercised quarterly?
What is the frequency of the stroke timing now being done, i.e., during ESF testing?
i 2.
How are the following valves verified to full-stroke exercise quarterly?
5 1(2)CA 8 1(2)CA-10 m
112)CA-22 1(2)CA-26 1(2)CA-12 1(2)CA-31 3.
What is the current frequency of the stroke timing for valves" 1(2)CA-20AB7 m
3
i
.E 22 2..
tc.000 ces 4.
What is the safety grade water source for the AFW pumps?
Review the safety function of the following valves to determine if they should oe included in the IST program and tested to Section XI requirenents:
Valve 9610 Valve P&lO 1(2)CA-3 1(2)592-1.1 1(2)CA-4 1(2)S92 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)S92-1.1 D.
Boron Recycle System 1.
If the only practical method of verifying valve closure is leak rate testing, then closure verification can be demonstrated eacn refueling outage.
However, it must be done each refueling outage irrespe:tive of the Appendix J required frequencyDoes the testing frequency for valves 1(2)NB-262 conform to this position?
E.
Breathino Air System 1.
If the 311y 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 required 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 l
containment isolation function?
2.
Review the safety function of valves 1(2)NV-7B, 457A EE
, 458A, and 459A to determine if they should be Categorized A.
1
==
3.
De valvas 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 E
quarterly result in an increase in RCS boron inventory?
4
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007 5.
Review the safety function of the following valves to determine if they should be included in the IST program and tested to Section XI requirements:
Valve p&lD Valve P&ID 1(2)NV-45 1(2)554-1.0 1(2)NV-29 1(2)S54 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)554 1.2 1(2)NV-15 1(2)554-1.2
' ( 2 )NV-20 1(2)S54-1.2 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-10'4 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-265B 1(2)S54-3.1 1(2)NV-411 1(2)554-5.0 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 closet positions?
If so, the valves must be exercised to both positions.
2.
Review the safety function of valves 1(2)KC-972 (P&ID 1(2)S73-1.1] te determine if they should be included in the IST program and tested to Section XI requirements.
3.
Review the safety function of valves 1(2)KC-3158, and 3058 to determine if they should be categorized A.
l l
l H.
Containment Air Release and Addition System l
l 1.
Clarify the testing being performed on valves 1(2)QV-1A, 2B, 5B, and 6A.
i I.
Containment Purge Ventilation 1.
Clarify *,he proposed alternate testing in the relief request for all containment purge ventilation category A valves.
The tigoke time of all power operated valve must be measured every time the 1
5 I
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75A;E us.cc:
ces valve is full-stroke exercised as required in Section XI, paragraph IWV-3413(b).
J.
Containment Soray System 1.
The NRC Staff position is that check valves must be full-stroke exercised, if Code reovired frecuency is impractical, then the licensee must request relief to perform the testing at a lesser f requenc.y.
However, relief requests seeking exemption for never full-st oke exercising check valves will not be granted.
The relief request for the following valves will be affected by this Staff position:
112)NS-13 1(2)NS-16 1(2)NS-30 112)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:
112)NS-128 1(2)NS-158 1(2)NS-29A 112)NS-32A 1(2)NS-38B 1(2)NS-43A Diesel Generator Room Sump Pump System 1.
De valves 1(2)WN-3, 5, 11, and 13 perform a safety function in the closed position?
i L.
Diesel Generator Starting Air System 1.
Provide P& ids MC 1609-4.0 and 2609-4.0 for our review.
5 M.
Equipment Decontamination System m
1.
What tyae of valve is 2WE-23?
Is the AC categorization for this valve correct?
m 1
6
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EGL3 10. T5 ALE tC.002 003 N.
Licuid Waste Recycle System 1.
Review the safety function of valve INI-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 quarterly?
P.
Main Steam Vent to Atmosphere 1.
Review the safety function of thr. following valves to determine if they should be included in the IST program and tested to Section XI requirements:
Valve P&ID Valve P&fD 1(2)SV-25 1(2)593-1.3 1(2)SV-26 1(2)554-1.3 1(2)SV-27 1(2)593-1.0 1(2)SV-28 1(2)S93-1.0 Q.
_uclear Sampling N
1.
What ty>t 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-41B and 2RN-43A are listed in both Unit I and Unit 2 valve taales.
Is this correct?
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r,c. cai ete S.
Reactor.oolant System 1.
The NRC Staff position is that the PORVs should be exercised during cold shutdown or prior to establishing conditions where the PORVs are utilized for low temperature overpressure protect'on.
The relief request 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 PalD MC-1553-2,1 for our review.
4.
Are valses 1(2)NC-141 and 142 passive valves?
T.
Refueling Water System 1.
Provide a detailed technical justification for not full-stroke exercising valves 1(2)FW-28 during cold shutdowns.
2.
Why are valves 1(2)FW-52 designated passive while all other small check valves that perform a thermal relief function are not?
l U.
Residual Heat Removal System 1.
What tyoe of leak testing is performed on valves 1(2)ND-1B and 2AC7 Da these valves perform both a pressure isolation function and a containment isolation function? See general coment A.13.
l 2.
Provide a detailed technical justification for not full-stroke l
exercising valves 1(2)ND-8 and 23 during cold shutdowns, 1
3.
Provide a more detailed technical justification for not full-stroke exercising valves 1(2)ND-70 quarterly and during cold shutdowns.
8
e-iz '6i ci:n EGLG lt'. T54E NC.002 0:1 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)NI-12 to determine if they should be categorized AC.
2.
Review the safety function of valves 1(2)N!-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)N!-59, 70, 81, and 93 verified to full-stroke open during refueling outages?
4.
How are valves 1(2)NI-60, 71, 82, and 94 verified to full-stroke open during cold shutdowns?
l S.
Review the safety function of valves 1(2)NI-121A and 1528 to l
determi u if they should be categorized A.
6.
What is the safety function of valves 1(2)N!-12287 7.
Describe the procedure used to full-stroke exercise the following valves during refueling outages:
112)NI-124 1(2)NI-128 1(2)N1 156 II2)NI-157 1(2)NI-159 1(2)NI-160 8.
How are valves 1(2)NI-125, 126, 129, and 134 verified to l
full-stroke during cold shutdowns.
9.
Review the safety function of the following valves to determine if they should be categorized A:
e if2)N1-162A 1(2)NI-173A 1(2)N1-1788 1(2)NI-1848 1(2)N!-185A i
1 1
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01Ts 10.
Review tne safety function of the following valves to determine if they should be included in the IST program as category A valves and tested to Section XI requirements:
Valve p&ID 1(2)NI-163 1(2)S62-3.1 1(2)N!-174 1(2)562-3.1 1(2)N1-179 1(2)S62-3.1 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)N! 175, 176, 180, and 181 full-stroke exercised during cold shutdowns?
13.
The NRC Branch Technical Position, RSS 5-1, establishes requiren9nts for taking reactor plants from power operation to cold shatdown using only safety-grade equipment.
To comply with this position, credit is normally taken for the safety injection accumulator vent paths and/or the accumulator motor operated isolatian valves.
Evaluate the safety function of the following valves to determine if tr.sy should be included in the IST program and tested to the Code requirements:
l
- Valve, p&!D Valve P&l0 1
1(2)N!-50 1(2)562-2.0 1(2)NI-54A 1(2)S62~2.0 l
1(2)NI-61 1(2)S62-2.0 1(2)NI-658 1(2)562-2.0 1(2)N!-72 1(2)562-2.1 1(2)NI-76A 1(2)562-2.1 1(2)NI-83 1(2)S62-2.1 1(2)NI-84 1(2)S62-2.1 1(2)NI-88B 1(2)562-2.1 14.
Review the safety function of the following valves to determine if they should be included in the IST program and tested to Section XI requirements:
Valve P&l0 Valve p&lD 1(2)NI-242B 1(2)S62-4.0 1(2)NI-243A 1(2)5f2-4.0 1(2)NI-244B 1(2)S62-4.0 1(2)NI-245A 1(2)S62-4.0 IN1-266A 1562-4.0 i
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a 15.
What type of the valves are the following:
IN!-248 INI-249 1NI-250 IN!-251 IN!-252 1N!-253 2.
PUMP TFSTING PROGRAM 1.
The dev*ations from the Code requirements discussed in Item !.A and B, osge 1.1-1, have not been indicated on the pump table.
2.
Section XI recuires that both flow and differential pressure be measure.1 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 I.C does not agree with this Staff position.
3.
Has McGaire Nuclear Station attempted to procure purtable I
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 j
measure pump bearing temperature annually, however, specific relief must be requested describing the difficulties encountered l
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 I
l position.
1 l
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 t
11
tC.002 014 J
reques%d.
This requirement will affect the pump test program for the diesel fuel oil transfer pumps, diesel generator sump pumos, and the standby makeup pumps.
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