ML20249A601
| ML20249A601 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 06/15/1998 |
| From: | Pickett D NRC (Affiliation Not Assigned) |
| To: | Myers L CENTERIOR ENERGY |
| References | |
| GL-96-06, GL-96-6, TAC-M96850, NUDOCS 9806170130 | |
| Download: ML20249A601 (7) | |
Text
__
Vice President - Nuclear, Perry Centerior Service Company P.O. Box 97, A200 Perry, OH 44081
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RELATED TO GL 96-06 RESPONSE - PERRY NUCLEAR POWER PLANT, UNIT 1 (TAC NO. M96850)
Dear Mr. Myers:
Generic Letter (GL) 96-06, " Assurance of Equipment Operability and Containment integrity During Design-Basis Accident Conditions," dated September 30,1996, included a request for licensees to evaluate cooling water systems that serve containment air coolers to assure that they are not vulnerable to water hammer and two-phase flow conditions. Centerior Energy prrvided its assessment of the water hammer and two-phase f!ow issues for the Perry plant in letters dated January 28 (PY-CEl/NRR-21321.), and May 30,1997 (PY-CEl/NRR-2174L). In order to complete our review of these issues, we will require additional information as discussed in the enclosure.
In order to support our review schedule, we request that this information be provided by August 30,1998.
Sincerely, Original signed by:
Douglas V. Pickett, Senior Project Manager Project Directorate 111-3 Division of Reactor. Projects Ill/IV g
Office of Nuclear Reactor Regulation DISTRIBUTION Docket No.:
50-440 PUBLIC PDlli-3 r/f I
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BBoger EAdensam
Enclosure:
As stated BWetzel RBellamy JTatum GGrant, R3 cc: See next page DOCUMENT NAME: G:\\PERRWA96850.RAI To recervs a copy of this document. Indicate in the box: "C" = Copy without enclosures "E" = Copy with enclosures *N" = No copy 0FFICE PM:PDIII-;D E
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BC:SPLB NAME DPicke T Efdnbill Q P/
LMarsh*
DATE 06/15'/98 06/il798 06/10/98 06/ /98 06/ /98 0FFICIAL RECORD COPY
- See Marsh to Savio Mamorandum dated June 10,1998 9006170130 98061'S PDR ADOCK 05000440
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June 15, 1998 e
Mr. Lew W. Myers Vice President - Nuclear, Perry l
Centerior Service Company P.O. Box 97, A200 Perry, OH 44081 SL'G JECT:
REQUEST FOR ADDITIONAL INFORA'.Ki:0N RELATED TO GL 96-06 RESPONSE - PERRY NUCLEAR POWER PLANT, UNIT 1 (TAC NO. M96850)
Dear Mr. Myers:
Generic Letter (GL) 96-06, " Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions," dated September 30,1996, included a request for licensees to evaluate cooling water systems that serve containment air coolers to assure L
that they are not vulnerable to water hammer and twc-phase flow conditions. Centerior Energy provided its assessment of the water hammer and two-phase flow issues for the Perry plant in letters dated January 28 (PY-CEl/NRR-2132L), and May 30,1997 (PY-CEl/NRR-2174L). In order to complete our review of these issues, we will require additional information as discussed in the enclosure.
In order to support our review schedule, we request that this information be provided by
- August 30,1998.
Sincerely, Original signed by:
Douglas V. Pickett, Senior Project Manager Project Directorate ill-3 Division of Reactor. Projects lil/IV Office of Nuclear Reactor Regulation DISTRIBUTION Docket No.:
50-440-PUBLIC PDill-3 r/f BBoger EAdensam
Enclosure:
As stated -
BWetzel RBellamy JTatum GGrant, R3 cc: See next page
. DOCUMENT NAME: G:\\ PERRY \\MG6850.RAI Ta eseelve e copy of this stocument, Indcate in the box: 'C" = Copy without enclosures *E" = Copy with enclosures *N" = No copy PM:PDI l-;Q E
LA:PDIII-3
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BC:SPLB 0FFICE l
NAME DPicketF EBarnhill Q (Y LMarsh*
DATE 06/15/98 06/lg/98 06/10/98 06/ /98 06/ /98 0FFICIAL RECORD COPY
- See Marsh to Savio Memorandum dated June 10,1998
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-NUCLEAR RE2ULATORY COMMISSION
'I WASHINGTON, D.C. 30806 4001 o
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June 15, 1998 Mr. Lew W. Myers Vice President - Nuclear, Perry Centerior Service Company P.O. Box 97, A200 Perry, OH 44081
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RELATED TO GL 96-06 RESPONSE - PERRY NUCLEAR POWER PLANT, UNIT 1 (TAC NO. M96850)
Dear Mr. Myers:
Generic Letter (GL) 96-06, " Assurance of Equipment Operability and Containment Integr9/
During Design-Basis Accident Conditions," dated September 30,1996, included a requr st for licensees to evaluate cooling water systems that serve containment air coolers to a ssure that they are not vulnerable to water hammer and two-phase flow conditions. Centeric r Energy provided its assessment of the water hammer and two-phase flow issues for the Perry plant in letters dated January 28 (PY-CEl/NRR-2132L), and May 30,1997 (PY-CEl/NRR-2174L). In order to complete our review of these issues, we will require additional information as discussed in the enclosure.
In order to support our review schedule, we request that this information be provided by August 30,1998.
Sincerely,
\\/
E Douglas V. Pickett, Senior Project Manager Project Directorate lll-3 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation Docket No.:
50-440
Enclosure:
As stated cc: See next page l
L. Myers Perry Nuclear Power Plant, Units 1 and 2 Centerior Service Company.
cc:
Jay E. Silberg, Esq.
James R. Williams Shaw, Pittman, Potts & Trowbridge Chief of Staff 2300 N Street, NW.
Ohio Emergency Management Agency Washington, DC 20037 2855 West Dublin Granville Road l
Columbus, OH 43235-7150 Mary E. O'Reilly Centerior Energy Corporation Mayor, Village of Perry 300 Madison Avenue 4203 Harper Street Toledo, OH 43652 Perry, OH 44081 Resident inspector's Office Roy P. Lessy, Jr.
U.S. Nuclear Regulatory Commission Akin, Gump, Strauss, Hauer P.O. Box 331 and Feld, L.L.P.
Perry, OH 44081-0331 1333 New Hampshire Ave., NW.
Suite 400 Regional Administrator, Region til Washington, DC 20036 U.S. Nuclear Regulatory Commission 801 Warrenville Road Radiological Health Program Lisle,IL 60532-4531 Ohio Department of Health P.O. Box 118 Lake County Prosecutor Columbus, OH 43266-0118 l
Lake County Administration Bldg.
l 105 Main Street Ohio Environmental Protection Painesville, OH 44077 Agency DERR-Compliance Unit l
Sue Hiatt ATTN: Mr. Zack A. Clayton I
OCRE Interim Representative P.O. Box 1049 8275 Munson Columbus, OH 43266-0149 Mentor, OH 44060 Chairman Terry J. Lodge, Esq.
Perry Township Board of Trustees 618 N. Michigan Street, Suite 105 3750 Center Road, Box 65 Toledo, OH 43624 Perry, OH 44081 l
Ashtabula County Prosecutor State of Ohio 25 Webt Jefferson Street Public Utilities Commission Jefferson, OH A4047 East Broad Street Columbus, OH 43266-0573 Henry L. Hegrat Regulatory Affairs Manager William R. Kanda, Jr., Plant Manager Cleveland Electric illuminating Co.
Cleveland Electric illuminating Co.
Perry Nuclear Power Plant Perry Nuclear Power Plant P.O. Box 7. r210 P.O. Box 97, SB306 l
Perry, OH.c4081 Perry, OH 44081 l.
L------_
cc: (continued)
Donna Owens, Director Ohio Department of Commerce Division of Industrial Compliance Bureau of Operations & Maintenance 6606 Tussing Road P.O. Box 4009 Reynoldsburg, OH 43068-9009 Mayor, Village of North Perry North Perry Village Hall 4778 Lockwood Road North Perry Village, OH 44081 Attorney General Department of Attorr3y General 30 East Broad Street Columbus, OH 43216
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i UNITED STATES g
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20066-0001
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REQUEST FOR ADDITIONAL INFORMATION RESOLUTION OF GL 96-06 ISSUES PERRY NUCLEAR POWER PLANT, UNIT NO.1 DOCKET NO. 50-440 Generic Letter (GL) 96-06, " Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions," dated September 30,1996, included a request for licensees to evaluate cooling water systems that serve containment air coolers to assure that they are not vulnerable to water hammer and two-phase flow conditions. Centerior Energy (the licensee) provided its assessment of the water hammer and two-phase flow issues for the
)
Perry plant in letters dated January 28, and May 30,1997. The licensee's response indicated j
that the cooling systems associated with the drywell cooling system (DCS) and the containment vessel cooling system (CVCS) are relevant to the water hammer and two-phase flow concems discussed in GL 96-06. The licensee indicated that the containment heat removal functions associated with these systems are not safety-related and are not relied upon for post-accident heat removal. In order to assess the licensee's resolution of the water hammer and two-phase flow issues, the following additional information is requested:
Note: The following questions are applicable to the cooling water systems associated with the DCS and CVCS.
I 1.
The licensee concluded that the CVCS was not susceptible to water hammer and two-phase flow conditions because the containment design temperature of 185* F would not support steam formation in the containment vessel chilled water system (CVCWS),
which provides cooling for the containment coolers. Confirm that water hammer and two-phase flow conditicns will not occur in the CVCWS following any postulated loss-of-coolant accident (LOCA) or main steam line break (MSLB) event inside containment, irrespective of containment design temperature and whether steam formation is a possibility or not. Also, confirm that this determination includes identification and consideration of the worst-case scenarios for water hammer (including column separation and rejoining events) and two-phase flow conditions that could occur within the existing design basis of the plant. Describe the worst-case scenarios for water hammer and two-phase flow in detail and identify the minimum margin to boiling that will exist for these worst-case scenarios.
2.
The licensee's response indicated that no safety concems would result from failures associated with the non-safety related DCS because the cooling function of the DCS is ENCLOSURE 1l.
(
2 not required for accident mitigation and a rupture of the nuclear closed cooling system (NCCS), which provides the cooling medium for the DCS, would be detected by a surge tank low level alarm. Describe in detail the worst-case scenarios for water hammer and two-phase flow in the NCCS and describe the actions (including operator response times) that must be taken to establish containment integrity should the NCCS rupture due to these worst-case scenarios, and describe in detail what effects rupture of the NCCS would have on the accident consequences (including release estimates, flooding, boron dilution, etc.). Also, in order to establish containment integrity, operability cf the containment isolation valves must be assured. Discuss the effects of water hammer and two-pliase flow on containment isolation capability, and justify your assumption that the contain'nent isolation valves will remain operable.
3.
Discuss spa cific system operating parameters that must be maintained in order to assure that: (a) water hammer and two-phase flow will not occur in the CVCWS, and (b) rupture i.f the NCCS will be identified and act;ons will be taken as assumed to maintain containment integrity. Explain why it would not be appropriate to establish Technical Specification requirements for these system parameters, and describe and justify reliance on any non-safety related instrumentation and controls in this regard.
4.
Confirm that the water hammer and two-phase flow analyses associated with the CVCWS and NCCS included a complete failure modes and effects analysis (FMEA) for all components (including electrical and pneumatic failures) that could affect the outcome of these analyses, and confirm that the FMEA is documented and available for review or explain why a complete and fully documented FMEA was not performed.
5.
Explain and justify all uses of " engineering judgement" that are credited in the analyses that have been completed.
6.
Provide a simplified diagram of the affected systems, showing major components, active components, relative elevations, lengths of piping runs, and the location of any orifices and flow restrictions.
i 7.
Describe in detail any plant modifications or procedure changes that have been made or are planned to be made to resolve the water hammer and two-phase flow issues, and
. provide schedules for comp!eting these actions.
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