PY-CEI-NRR-2146, Submits Supplemental Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions

Submits Supplemental Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions

ML20136J021
Person / Time
Site:	Perry
Issue date:	03/14/1997
From:	Myers L CENTERIOR ENERGY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-96-06, GL-96-6, PY-CEI-NRR-2146, NUDOCS 9703190395
Download: ML20136J021 (4)

Text

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l CENTE" DOR ENERGY

' Power Generation Group Perry Nuclear Power Plant Mad Address: 216-280-6915 Low W. Myers 10 center Road P.O. Box 97 FAX:216-280-8029 Vce Presdent Perry, Ohio 44081 Perry, OH 44081 March 14,1997 PY-CEI/NRR-2146L United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Perry Nuclear Power Plant Docket No. 50-440 )

Supplemental Response to Generic Ixtter %06, " Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions" Ladies and Gentlemen:

Generic Letter (GL) %06, " Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions," dated September 30,1996, requested licensees to evaluate their plant design and detennine: (1) if containment air cooler cooling water systems are susceptible to either waterhammer or two-phase flow conditions during postulated accident corxlitions, and (2) if piping systems that penetrate the containment are susceptible to thermal expansion of fluid so that overpmssurization of piping could occur.

'Ihe response to GL 96-06 for the Perry Nuclear Power Plant (PNPP), which was submitted on January 28,1997, stated that the results of the review for GL %-06 indicate that 11 penetrations i are susceptible to the thermal expansion of fluid. 'Ihe operability evaluation at that time stated: i Fmm an operability perspective, the risk due to failure resulting fmm environmental heating is judged to be minimal, since pipe expansion and leakage thmugh the valve seat, packing, and potentially any gasket bolted joint where bolt relaxation may occur, would relieve pressure. A review ofleak rate testing data for the subject penetrations supported that valve seat leakage exists. 'lhis leakage is expected to increase at elevated intemal piping pressures, thereby further assisting in pressure relief. This led to the detennination that no safety related system or containment integrity would be lost, and therefore operability is maintained.

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PY-CEl/NRR-2146L

,- March 14,1997 y Page 2 of 2 Dunng subsequent evaluation of the local leak rate test (LLRT) data, it was determined that two of the containment penetrations (P-417 and P-424) may not leak. 'Ihe minimum recorded leak rate for the test procedure is 2 SCCM; therefore, actual leakage may be less than 2 SCCM. As a result of this, the following revised operability evaluation for these two penetrations was

prepared.

A calculation has been perfonned, and assuming no valve leakage and anticipated environmental conditions post accident, containment penetrations P-417 (Equipment Drain System) and P-424 (Reactor Water Cleanup System) remain operable. Calculated hoop stresses, due to post accident environmental conditions, remain within limits specified in Appendix F of Section III of the ASME Code. 'nds led to the determination that no safety j related system or containment integrity would be lost, and therefore operability is maintained. '

Tim attachment to this letter is a revised table of As-Left LLRT Test Data, which was previously

submitted to the NRC in the response to GL %-06.

'Ihe following table identifies those actions which are considened to be segulatory commitments.

Any other actions discussed in this document represent irnended or planned actions, are described for the NRC's infonnation, and are not regulatory commitments.

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Commitments

'Ihere are no commitments in this letter, if you have questions or requite additional information, please contact Mr. Henry L. Hegrat, l

Manager-Regulatory Affairs.at(216)280-5606.

Very truly yours, for Lew W. Myers KMN:sc Attachment cc: NRC Project Manager NRC Residentinspector NRC RegionIII l

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l I, Lonnie W. Worley, being duly sworn state that (1) I am Director, Perry Nuclear Services Department of the Cleveland Electric Illuminating Company, l (2) I am duly authorized to execute and file this certification on behalf of The '

Cleveland Electric Illuminating Company and Toledo Edison Company, and as the duly authorized agent for Duquesne Light Company, Ohio Edison Company, and Pennsylvania Power Company, and (3) the statements set forth herein are true and correct to the best of my knowledge, information and belief.

OWh L - ($ l}A/

Lonnie W. Worley l

1 Sworn to and subscribed before me, the / day of Nk4 C ,

PH7. '

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• M LIND J. B IKK A Notary P 11 e of Ohio My Comission Expires April 23,)2001 (Recorded in Lake County CODED /8838/sc

As-LeR LIRT Test Data

• Penetration AMatt RRTl.askage Description Number Vahm Number Modum ValveType Test Date Rate A **

Condensate P-111 1P11-F0000 water bunerfy 2/3/96 2 Condensate P-111 1P11-F0090 water bunerfy 2/3,96 3.5 FuelPoolCoolog P-301 1G41-F0140 water bunerfy 1/2996 6.7 Fuel PoolCooling P-301 1G41-F0145 water bunerty 1/2&96 87.5 Demineralized Water P-309 1P22-F0010 demm. water gate 2/21/96 2 Demineralized Water P-309 1P22-F0577 demm. water gate 2/13/96 33.68 Nuclear Closed Cooiing P-311 1P43-F0140 water bunerfy 2/25S6 2 Nuclear Closed Cooing P-311 1P43-F0215 water bunerly 2/2596 29.5 Chilled Water P-405 1P50-F0140 chilled water bunerfy 3/14/96 4.4 Chilled Water P-405 1P50-F0150 chihd water bunerfy 3/14/96 3.02 Fire Protecton P-406 1P54-F0726 water gate 1/28/96 2.03 Fire Protecton P-406 1P54-F0727 water gate 1/28/96 2 Post Accdent Sampimg P413 1P87-F0049 water globe 2/7/96 2 Post Accdent Sampling P413 1P87-F0052 water globe 2/7/96 85.56 Post Accdont Sampling P413 1P87-F0055 water globe 2/7/96 2 Post Accdert. Sampling P-413 1P87-F0046 water globe 2/7/96 103.15 Equipment Drain P417 1G61-F0000 water gate 3/7/96 2 Equipment Drain P417 1G61-F0075 water gate 2/28i96 2 Floor Drains P418 1G61-F0165 water gate 3/1596 2.44

• Floor Drams P418 1G61-F0170 water gate 3/1596 2 Backwash to RW P420 1G50-F0277 water gate 2/25/96 2.82 Backwash to RW P420 1G50-F0272 water gate 2/2596 10.14 l ReactorWater Cleanup P424 1G33-F0034 water gate 3/14/96 2 ;P & !

ReactorWater Cleanup P424 1G33-F0028 water cate 3/14/96 2 Ti

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Ri 2, F'

• NOTE: 'Ihe minimum recorded leak rate for the test procedure is 2 SCCM. As such, actual leakage may be less than 2 SCCM. - E 6

• • NOTE: All testing performed at 7.8 - 8.58 psig with air.

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