ML17334A540
| ML17334A540 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/07/1997 |
| From: | John Hickman NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9711200372 | |
| Download: ML17334A540 (19) | |
Text
November 7, 1997 American Electric Power Donald C: Cook Nuclear Plant, Units 1 and 2
,. LICENSEE:
1s
, FACILITY:
SUBJECT:
SUMMARY
OF OCTOBER 9, 1997, MEETING ON RWST MINI-FL'OW RECIRCULATION LINE VALVETESTING I,
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,On October 9, 1997, NRC staff members met in Rockville, Maryland, with representatives of American Electric Power (AEP). The purpose of the meeting was for AEP to discuss the acceptability of the testing methodology for the RWST mini-flow recirculation line valves.
The lack of leakage verification tests on four of the six mini-flow recirculation line valves was identified as Item 8 in the September 19, 1997, confirmatory action letter. A list of the meeting participants is included as Attachment 1, and a copy of the meeting handouts is provided as Attachment 2.
The licensee began the meeting with a brief discussion of the issue including the design of the flow paths and the design of the subject valves.
The licensee was proposing to test the valves in a reverse flow direction. That presentation was followed by a discussion between the licensee and NRC staff of the ASME Code requirements for these valves, It was agreed to be appropriate that the valves be added to the licensee's inservice testing program as Category B valves.
As Category B valves, the Code does not specify individual valve leakage testing.
For Category B valves, the only requirement is for closure exercising and system leakage testing.
Under these circumstances, the reverse flow testing is acceptable.
11 r-
1 Original signed by:
John B. Hickman, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316 Attachm'ents:
1.
List of Meeting Participants 2.
Meeting Handouts cc w/atts:
See next page DISTRIBUTION: See next page DOCUMENT NAME: G:iDCCOOKic010-997.MTS To receive a copy of this document, Indicate In the box: "C" = Copy without enciosures "E" = Copy viith endosures "N" = No copy OFFICE NAME DATE PD3-3:PM E
JHickman 11/
/97 PD3-3:LA E
CBoyle 11/
/97
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November 7,
1997 LICENSEE:
American Electric Power FACILITY:
SUBJECT:
Donald C. Cook Nuclear Plant, Units 1 and 2
SUMMARY
OF OCTOBER 9, 1997, MEETING ON RWST MINI-FL'OW RECIRCULATION LINE VALVETESTING On October 9, 1997, NRC staff members met in Rockville, Maryland, with representatives of American Electric Power (AEP). The purpose of the meeting was for AEP to discuss the acceptability of the testing methodology for the RWST mini-flow recirculation line valves.
The lack of leakage verification tests on four of the six mini-flow recirculation line valves was identified as Item 8 in the September 19, 1997, confirmatory action letter. A list of the meeting participants is included as Attachment 1, and a copy of the meeting handouts is provided as Attachment 2.
The licensee began the meeting with a brief discussion of the issue including the design of the flow paths and the design of the subject valves.
The licensee was proposing to test the valves in a reverse flow direction.
That presentation was followed by a discussion between the licensee and NRC staff of the ASME Code requirements for these valves It was agreed to be appropriate that the valves be added to the licensee's inservice testing program as Category B valves.
As Category B valves, the Code does not specify individual valve leakage testing.
For Category B valves, the only requirement is for closure exercising and system leakage testing.
Under these circumstances, the reverse flow testing is acceptable.
Original signed by:
John B. Hickman, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316 Attachments:
- 1. List of Meeting Participants
- 2. Meeting Handouts cc w/atts:
See next page RC KE CENT. eel V DISTRIBUTION: See next page DOCUMENT NAME: G:>DCCOOK>CO10-997.MTS To receive a copy of this document, indicate In the box: "C" = Copy without enclosures "E" ~ Copy with enciosures "N" ~ No copy OFFICE PD3-3:PM E
PD3-3:LA E
NAME JHickman DATE 11/
/97 CBoyle 11/
/97
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++*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 2055&0001 November 7,
1997 LICENSEE:
American Electric Power FACILITY:
Donald C. Cook Nuclear Plant, Units 1 and 2
SUBJECT:
SUMMARY
OF OCTOBER 9, 1997, MEETING ON RWST MINI-FLOW RECIRCULATION LINE VALVETESTING On October 9, 1997, NRC staff members met in Rockville, Maryland, with representatives of American Electric Power (AEP). The purpose of the meeting was for AEP to discuss the acceptability of the testing methodology for the RWST mini-flow recirculation line valves.
The lack of leakage verification tests on four of the six mini-flow recirculation line valves was identified as Item 8 in the September 19, 1997, confirmatory action letter. A list of the meeting participants is included as Attachment 1, and a copy of the meeting handouts is provided as Attachment 2.
The licensee began the meeting with a brief discussion of the issue including the design of the flow paths and the design of the subject valves.
The licensee was proposing to test the valves in a reverse flow direction. That presentation was followed by a discussion between the licensee and NRC staff of the ASME Code requirements for these valves.
It was agreed to be appropriate that the valves be added to the licensee's inservice testing program as Category B valves.
As Category B valves, the Code does not specify individual valve leakage testing.
For Category B valves; the only requirement is for closure exercising and system leakage testing.
Under these circumstances, the reverse flow testing is acceptable.
John B. Hickman, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316 Attachments:
1.
List of Meeting Participants
- 2. Meeting Handouts cc w/atts:
See next page
Indiana Michigan Power Company CC:
Regional Administrator, Region III U.S. Nuclear Regulatory'Commission 801 Warrenville Road Lisle, IL 60532-4351 Attorney General Department of Attorney General 525 West Ottawa Street
- Lansing, HI 48913 Township Supervisor Lake Township Hall P.O.
Box 818
- Bridgman, HI 49106 Al Blind, Site Vice President Donald C.
Cook Nuclear Plant 1 Cook Place
- Bridgman, MI 49106 U.S. Nuclear Regulatory Commission Resident Inspector's Office 7700 Red Arrow Highway Stevensvi1 1 e, MI 49127 Gerald Charnoff, Esquire
- Shaw, Pittman, Potts and Trowbridge 2300 N Street, NW.
Washington, DC 20037 Mayor, City of Bridgman P.O.
Box 366
- Bridgman, MI 49106 Special Assistant to the Governor Room 1 - State Capitol
- Lansing, HI 48909 Drinking Water and Radiological Protection Division Michigan Department of Environmental guality 3423 N. Martin Luther King Jr Blvd P.O.
Box 30630, CPH Hailroom
- Lansing, HI 48909-8130 Donald C.
Cook Nuclear Plant Units 1 and 2
Steve J.
Brewer Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive
- Buchanan, MI 49107 E.E. Fitzpatrick, Vice President Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive
- Buchanan, HI 49107
DISTRIBUTION FOR
SUMMARY
OF OCTOBER 9, 1997, MEETING WITH AMERICAN ELECTRIC POWER Hard Co w/atts:
Docket File PD III-3 Reading PUBLIC BBurgess, Rill OGC ACRS E-mail w/att 1:
SCollins (SJC1)
FMiraglia (FJM)
GTracy (GMT)
RZimmerman (RPZ)
EAdensam (EGA1)
GMarcus (GHM)
TMartin (SLM3)
RLobel (RML)
JHuang (JXH)
JThompson (JWT1)
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MEETING ATTENDEES NRC AND AMERICAN ELECTRIC POWER DISCUSSION OF RWST MINI-FLOWRECIRCULATION LINE VALVETESTING OCTOBER 9, 1997 NRC John Hickman Richard Lobel John Huang American Electric Power Steve Brewer Gordon Arent Frank Pisarsky Attachment 1
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~ BB.c -Lea age to R ssue o oncern
'AL:"Refueling Water. Storage Tank (RWST)
Mini-fiowRecirculation Lines (NRC)"
"Only two ofsix mini-flowrecirculation line valves have leakage verification tests.
Justification willbe provided that the total leakage for the six valves is less than 10 gpm to ensure that Part 100 dose rates are not exceded ifcontainment sump water were to leak back to the RWST during a design basis accident."
. Bac Lea age Investigation
~ There are four potential back flowpaths (through 8 valves) to the RWST.
~ Two ofthe four paths were being leak tested The high head safety injection mini-flow recirculation return to the RWST (IMO-262, -263)
The RHR System return line isolation to the RWST (RH-130)
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Bac Lea age Investigation
~ Two flowpaths containing five valves were not included Suction path for the high head safety injection pumps (SI-101 k, IMO-261)
Suction path for the centrifugal charging pumps (SI-185, IMO-910, IMO-911)
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. Bac Lea agetoR Reso ution T
~ Procedure developed to leak test additional five valves
~ Testing has been completed
~ The additional five valves (IMO-261, -910,
- 911 A SI-101, -185) had no leakage in either Unit.
Unit 1 = 0.0 gpm Unit 2 ='0.0 gpm
. Bac Lea age to R Reso ution T
~ Previously tested IMO-262, -263 had no leakage.
Unit 1 = 0.0 gpm Unit 2 = O.Q gpm
~ RH-130 is an RCS boundary valve and is leak tested as part ofthe more conservative TS 3.4.6.2(b) surveillance (RCS unidentified leakage).
9/17/97 values: Unit 1 = Q.O gpm Unit 2 = 0.48 gpm total leakage
~ Total leakage:
Unit 1 = No leakage Unit 2 = Less than.5 gpm (maximum)
. Long Term P an
~ A leak rate test has been added to the IST Program for each valve in the four potential back-flow paths.
~ The valves willbe seat leakage tested to assure 10CFR100 dose rate leakage limits are not exceeded.
Anchor Model 2S-1028-3 Flex Wedge Gate Valve 1-IMO-261, 1-IMO-910, 1-IMO-911, 2-IMO-261, 2-IMO-910, 2-IMO-911
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