IR 05000277/1985023

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Summary of 870730 Meeting W/Util at Site Re Containment Leakage Testing,Fire Protection Issues,Insp Repts 50-277/85-23 & 50-278/85-23 & Util 860915 & 1010 Amended Requests for Changes to Tech Specs.Attendance List Encl
ML20239A639
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 09/14/1987
From: Martin R
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
Shared Package
ML20239A640 List:
References
NUDOCS 8709180041
Download: ML20239A639 (10)


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Docket No /50-278 Facility: Peach Bottom Atomic Power Station, Units 2 and 3 Licensee: Philadelphia Electric Company Subject: SUMMARY OF JULY 30, 1987 MEETING ON CONTAINMENT LEAKAGE TESTING AND FIRE PROTECTION ISSUE On July 30, 1987 members of the NRC staff met with representatives of the Philadelphia Electric Company (PECo) at the Peach Bottom Site to discuss routine licensing issues including (1)the NRC Inspection Reports 50-277/85-23 and 50-278/85-23 dated August 15, 1986, relating to containment isolation valve packing leakage testing, (2)the licensee's September 15, 1986 amended request for changes to the Technical Specifications (TS) relating to the large primary containment Purge and Vent isolation valves, (3)the licensee's October 10, 1986 amended request for changes to the TS relating to the containment leakage testing program, and (4)the NRC staff's systems related review of the Peach Bottom fire protection program. A list of attendees for discussion of the first three issues is provided and a separate list for the fourth issue is also provided in Enclosure Containment Isolation Valve Stem Packing I The issue set forth in the NRC Inspection Report No. 85-23, of August 15, i 1986, was discussed. A chronology to the issue and several figures were i

) provided by the licensee. Figure 1 is a schematic of the double isolation valve configuration being tested. The valves are local leak rate tested by pressurizing the space between the two valves, which for the valves in question, will provide a conservative measure of seat leakage since it tends tounseatthevalve(reversedirectiontesting). This local test does not test the 30tential path from the primary containment along the valve stem and through t1e valve stem packing; see Figure The meeting resulted in an agreement by the licensee that for Peach Bottom a response would be provided to the Inspection Report which covers at least the points listed below. PECO also noted that the BWR Owners Group efforts on this issue have been directed at commenting on paragraph C.20 of the proposed Regulatory Guide which would accompany the revision to Appendix PEC0's response should support their position regarding the integrity of these i valve packings with respect to precluding leakage paths to the environment and their position regarding compliance of this design with App J. by addressing at least the following: .'

- Identification of all subject valves

- Ability to detect gross leakage

- Packing inspection program t

- Packing maintenance program

- Any history of test results which shows how these valves traditionally perform

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- A rationale for concluding that, between the containment Type A text, which does test the stem leakage pathway, and the Type C test which tests the other s'de of the valve (seat leakage), adequate assurance of the valve's leak tight integrity is provide By letter dated August 7,1987 PECo indicated that a response to the inspection report would be provided by November 20, 1987.

l Purre and Vent Isolation Valves ( PECO's amended application dated September 15, 1986 regarding implementation of the 90 hour0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> annual limit on the use of the large containment purge and vent valves was discusse The staff compared the explicit wording of the proposed TS with the requirements of Appendix J. PEC0 stated the changes proposed in the amended application that are peripheral to the 90 hour0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> purge issue were made at the request of the NRC staff. This aspect of the proposed TS amendment remained unresolved and will be addressed in future action The discussion of item 4.7.E on proposed TS page 178 revealed that this issue is related to the staff's review of the safety grade pneumatic supply system for containment purge / vent inflatable seals and controls as described in PEC0's November 6, 1985 letter. The staff indicated that it would check on the status of this issu Containment Leakage Testing Program PECO's amended application dated October 10, 1986 regarding the containment leakage testing program as specified in TS section 3.7. A and 4.7.A was discusse The staff had multiple comments on the application based on an explicit comparison to STS language and the status of the enclosed requests for exemptions from certain requirements of Appendix J. It was determined that this meeting would not provide the time required for a discussion of these issue Fire Protection The issues identified in the staff's letter of July 17, 1987 (Enclosure 3)

were discussed. The staff indicated that for the items listed in part A it required a brief description of the modification, the analysis and how it affects safety related equipment. It was agreed that (a) the justification for continued operation (JCO) describes the problem adequately for these review purposes, and (b) the PECO safety evaluation descriptions consisting of several pages each would describe the resolution adequately for these review purpose PECO also provided a cross-reference between the staff's agenda items, the JCO, and the modification number (see Enclosure 4).

Part B items on the alternative safe shutdown procedure SE-10 have been completed by PECO. The staff will review this subject in its Fire Protection Audit Revie _ ___ _

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s 7-3-The Part C discussion on high/ low pressure interfaces revealed that PEC0's definition of the high/ low pressure interfaces requires revisio PECO committed to respond in writing to thi The Part D discussion on suppression pool temperature and RHR pump NPSH indicated that PECO's response appears acceptable. The staff requested that PECO document the respons Regarding item E.a on high-impedance faults, PEC0 does not comply fully with the guidance in Generic Letter 86-10 in that they do not automatically shed load from electrical buses upon indication of a fire in an area. Operators l instead rely on symptom oriented procedures and only strip loads off if the

! symptoms warrant the actio PECO believes that their systems are ininune from sustained high impedance faults due to hard grounding of cable trays, etc.

l The staff indicated that it would consider this and respond to PECO on their positio Regarding item E.b, Peach Bottom has redundant fusing for the alternate shutdown mode equipment; which would be effective after the control transfer switch is thrown. This will be reviewed in the staff's Fire Protection Audit Revie Regarding item E.c, Peach Bottom requires no hot shutdown repairs for the long ter PECO committed to submit a description of the cold shutdown repairs require Regarding item E.d, PEC0 will document its answer regarding the number of people available to shut the plant down with the fire brigade activate /a/

Robert E. Martin, Project Manager Project Directorate I-2 Division of Reactor Projects I/II Enclosures:

As stated cc: Licensee / Applicant & Service List

. DISTRIBUTION LDocket File ~ OGC-Bethesda NRC PDRs EJordan Local PDRs JPartlow PDI-2 Reading NRC Participants WButler ACRS (10)

RMartin/DClark HBClayton Previously concurred *:

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l The Part C discussion on high/ low pressure interfaces revealed that PECO's definition of the high/ low pressure interfaces requires revisio PECO committed to respond in writing to thi The Part D discussion on suppression pool temperature and RHR pump NPSH l indicated that PEC0's response appears acceptable. The staff requested that

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PEC0 document the respons Regarding item E.a on high-impedance faults, PEC0 does not comply fully with the guidance in Generic Letter 86-10 in that they do not automatically shed load from electrical buses upon indication of a fire in an area. Operators

'instead rely on symptom oriented procedures and only strip loads off if the symptoms warrant the actio PEC0 believes that their systems are immune from sustained high impedance faults due to hard grounding of cable trays, et The staff indicated that it would consider this and respond to PECO on their positio Regarding item E.b, Peach Bottom has redundant fusing for the alternate shutdown mode equipment; which would be effective after the control transfer switch is thrown. This will be reviewed in the staff's Fire Protection Audit Revie Regarding item E.c, Peach Bottom requires no hot shutdown repairs for the long ter PECO committed to submit a description of the cold shutdown repairs require Regarding it'em E.d. PEC0 will document its answer regarding the number of people available to shut the plant down with the fire brigade activate )QQf[) as

    / Robert E. Martin, Project Manager Project Directorate I-2 Division of Reactor Projects I/II Enclosures:

As stated cc: Licensee / Applicant & Service List l l

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_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ - _ _ _ _ _ - o I ! t 0 I-' Mr. E. G. Bauer, J Peach Botton Atomic Power Station, Philadelphia Electric Company Units ? and 3 f I ! cc: Troy B. Conner, Jr. , Es Mr. R. A. Heiss, Coordinator 1747 Pennsylvania Avenue, Pennsylvania State Clearinghouse l Vashington, D.C. 20006 Governor's Office of State Planning j and Development  !

' Thomas A. Deming, Es P.O. Box 1323 j Assistant Attorney General Harrisburg, Pennsylvania 17120 l l Department of Natural Resources  ! Annapolis, Maryland 21401 Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection , Philadelphia Electric Company Pennsylvania Department of ATTN: Mr. D. M. Smith, Manager l Environmental Resources ' Peach Bottom Atomic Power Station P.O. Box 2063 - Route 1, Box 208 Harrisburg, Pennsylvania 17120  ! Delta, Pennsylvania 17314 l Mr. Albert R. Steel, Chairman l Mr. J. W. Gallagher, Vice President Board of Supervisors Nuclear Operations Peach Bottom Township l Philadelphia Electric Company R. D. #1 i 2301 Market Street Delta, Pennsylvania 17314 Philadiphia, Pennsylvania 19101 Mr. Gary Mock  ; Mr. W. M. Alden P.O. Box 09181 Engineer-In-Charge-Licensing Columbus, Ohio 43209 i Philadelphia Electric Company ' 2301 Market Street Mr. Thomas S. Shaw, J Philadelphia, Pennsylvania 19101 Vice President - Production ) Delmarva Power and Light Company  ; Morgan J. Morris, III 800 King Street ' General Manager - Operating Services Wilmington, Delaware 19899 Atlantic Electric P. O. Box 1500 l 1199 Black Horse Pike i Pleasantville, New Jersey 08232 i Resident Inspector U.S. Nuclear Regulatory Commission Peach Bottom Atomic Power Station P.O. Box 399 j Delta Pennsylvania 17314 i Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 l I

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%, * . . * p ENCLOSURE 1 Attendees for 7/30/87 Meeting CONTAINMENT RELATED ISSUES R. E. Martin   NRC Project Manager T. T. Varjarante   NRC/NRR Plant Systems Branch Jack Kudrick   NRC/NRR/PSB T. Chandrasekaran-   NRC/NRR/PSB C. N. Swenson   PEC0/Nuc. Op. - PBAPS J. P. Durr   Dep. Dir. DRS(Acting) ,

C. J. Anderson NRC-RI, Chief PSS i J. W. Chung NRC-RI,-Lead R. En ' Tom Johnson NRC-P.B. Senior Pesident Ins Al Fulvio PEC0-Technical Engr. PBAPS . ' William M. Alden PECO-EIC-Licensing-Nuc. Support John F. O'Rourke PEC0/M.E. Division /Nuc. Serv. B . William J. McFarland PEC0/M.E. Division /Nuc. Serv. Br-D. R. Helwig PEC0/M.E./Pwr. PL. Des. Section W. J. Brady PEC0/M.E./Pwr. PH. Des. Section T. Loomis PEC0/ Licensing /Nuc. Support ! D. P. Helker PEC0/ Nuclear Support / Licensing M. A. Phillips PSE & G J. A. Jordan PEC0/ Nuclear Ops. PBAPS D. R. Shaulis PEC0/ Nuclear Ops. PBAPS C. J. Campbell PEC0/ Nuclear Ops PBAPS

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s .e II. Attendees for 7/30/87 Meeting FIRE PROTECTION RELATED ISSUES-R. E. Martin' NRC Project Manager W. J. Boyer Philadelphia Electric C D. R. Helwig PEC0/Pwr/Pl. Des. Section C. N. Swenson PEC0/Nuc. Op. - PBAPS J. M.'Marrinveci GE J. F. O'Rourke PEC0/M.E. Division /Nuc. Serv. B William M. Alden

   . PECO EIC-Licensing Section-Nuc. Support A. Krasopoulos  Reactor Engineer, NRC D. M. Spamer  PEC0 - Elec. En Tom Johnson  NRC - SRI Peach Bottom
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J. Brady PEC0 - M.E./PPDS J. J. McCawley .PEC0 - EE G. Termine PEC0 - EE M. W. Lohr PEC0 - EE M. A. Phillips PSE & G A. Melikian EPM D. Brecker EPM R. Hodor BNL/NRC K. Sulliva BNL/NRC T. Chandrasekaran NRC/NRR/PSB Jack Kudrick NRC/NRR/PSB' T. Varjoranta NRC/NRR/PSB

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s v . PEACH BOTTCM ATOMIC POWER STATION 10CFR50, APPEtOIX J CHRONOLOGY I

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US NRC Requests PECo to review PBAPS 8/7/75 App. J comp 1iance PECo, Interim' Response 9/12/75 PECo Appendix J submittal 8/13/76

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NRC Requests Additional Information on 1/22/81 j 1976.Submltta PECo Updates 1976 Submittal 5/15/81 NRC Requests Amendment of -1976 Submittal 9/12/83 via Telecon PECo forma 11y' Amends 1976 Submittal 4/19/84 NRC reauests another amendment to 8/13/76 9/10/85 and 4/19/84 Submittal via Telecon PECo submtts Second Amendment 10/10/86

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