ML20138M992

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Summary of 850213 Meeting W/Util & State of Nj Dept of Environ Protection in Bethesda,Md Re Installation of Qualified Containment Purge & Vent Valves During Cycle 11R Outage.List of Attendees & Figure 6.2-28 Encl
ML20138M992
Person / Time
Site: Oyster Creek
Issue date: 12/16/1985
From: Donohew J
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8512230306
Download: ML20138M992 (6)


Text

  1. \ UNITED STATES 8 o NUCLEAR REGULATORY COMMISSION

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l $ E WASHINGTON, D. C. 20555

\ 4*** DEC 16586 Docket No. 50-219 LICENSEES: GPU Nuclear Corporation Jersey Central Power and Light Company p FACILITY: Oyster Creek Nuclear Generating Station

SUBJECT:

MEETING FEBRUARY 13, 1985, ON INSTALLATION OF QUALIFIED CONTAINMENT PURGE AND VENT VALVES DURING CYCLE 11R OUTAGE a

On Wednesday, February 13, 1985, a meeting was held at NRR Headquarters, Bethesda, Maryland,todiscussGPUNuclear's(thelicensee's) considerations to withdraw its comitments to (1) install qualified y containment (drywell) vent and purge valves and (2) upgrade the nitrogen vent and purge system during the Cycle 11 Refueling (Cycle 11R) outage.

This meeting was held at the request of the licensee. Attachment 1 is L the list of the indigiduals attending the meeting. The following is a sumary of the significant items discussed and the actions taken or proposed.

The meeting was a preliminary meeting for the licensee prior to submitting i a request to the staff. The licensee stated that this was part of its reassessment of commitments which have been made to the staff to upgrade Oyster Creek to determine if the comitments were appropriate and not t beyond the staff's requirements.

The commitment to install qualified purge and vent valves was part of the licensee's response to the staff's review of multi-plant generic activity t

B-24, Containment Purging During Normal Plant Operation. In the NRC letter of L November 29, 1978, the staff identified its generic concern to all operating reactor licensees. The licensee made the commitment in its letter dated July 31, 1930.

The comitment to upgrade the nitrogen vent and purge system was part of r

the licensee's response to the Short Term Lessons Learned NUREG-0578 of the staff's TMI Action Plan and to 10 CFR 50.44. The licensee made the comitment in its letter of June 10, 1980. This issue is also involved in the primary means for combustible gas control for Oyster Creek.

The licensee described the primary containment ventilation and inerting system. This system contains the purge and vent isolation valves and the

'l nitrogen vent and purge valves. These are shown in the figure from the Oyster Creek Updated Final Safety Analysis Report (FSAR) in Attachment 2.

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l 8512230306 851216 PDR ADOCK 05000219 P PDR j

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The licensee stated that the request to not replace the containment purge and vent isolation valves by qualified valves will affect valves V-27-1/2, t V-28-17/18/47 V-27-3/4, V-23-13/14 and V-23-15/16 in the figure in Attachment 2. All these are containment isolation valves. The request to not upgrade the nitrogen system will affect valves V-23-17/18 V-23-19/20, V-23-21/22 and V-28-47 of this figure.

The licensee stated that the comitment on the containment isolation valves is being considered to be withdrawn because these valves are blocked

! partially closed and met the staff's interim position for containment purge t

of October 23, 1979. The licensee would propose this interim position as its final position. The licensee stated that this position is conservative and the valves will close against the design basis accidents.

The licensee stated that considerations to propose the withdrawal of the comitment on the nitrogen system was based on the BWR Owner's Group model p of the hydrogen source term for the LOCA. This model was an analysis performed by General Electric (NED0-22155). The licensee stated the BWROG's model showed Oyster Creek should not reach the hydrogen flamability limit within 2 years after the LOCA.

The staff and the licensee discussed the technical arguments for the licensee's pro)osed withdrawal of its comitments. The staff stated that t

the licensee s1ould propose additional technical specifications on the existing containment vent and purge isolation valves to inspect and test I

these valves if they have resilient seals. The valves that would replace the existing valves do not have resilient seals. The staff referred to its L January 18, 1985, letter to the BWROG which stated that a containment high

- range radiation signal should go to all containment vent and purge isolation valves, large and small. The staff stated that 10 CFR Part 50.44(d) provides a design basis hydrogen source and that Generic Letter 84-09 (May 8, 1984) provides a basis for an exemption to the recombiner capability required in l 10 CFR Part 50.44(c)(3)(ii) but it is not applicable for design basis accidents.

The licensee submitted its request to withdraw the comitments to (1)

L install qualified containment vent and purge isolation valves and (2) upgrade the nitrogen vent and purge system in its letter dated September 24, 1985.

. h o c Manager WR Project Director #1 ivision of BWR Licensing Attachments:

1. List of Attendees
2. Licensee Handout l

I cc: J. Zwolinski

! G. Lear H. Kister, Region I J. Chen i K. Leu N. Chokshi i

w. .. - ~ _..~.. . . - . . - .- ---

L cc:

G. F. Trowbridge, Esquire Resident Inspector Shaw, Pittman, Potts and Trowbridge c/o U.S. NRC 1800 M Street, N.W. Post Office Box 445 Washington, D.C. 20036 Forked River, New Jersey 08731 J.B. Liberman, Esquire Conunissioner Bishop, Liberman, Cook, et al. New Jersey Department of Energy 1155 Avenue of the Americas 101 Commerce Street New York, New York 10036 Newark, New Jersey 07102 Eugene Fisher Assistant Director Regional Administrator, Region I Division of Environmental Quality U.S. Nuclear Regulatory Coninission Department of Environmental 631 Park Avenue Protection King of Prussia, Pennsylvania 19406 380 Scotch Road Trenton, New Jersey 08628 BWR Licensing Manager GPU Nuclear 100 Interpace Parkway Parsippany, New Jersey 07054 I

Deputy Attorney General State of New Jersey Department of Law and Public Safety 36 West State Street - CN 112 Trenton, New Jersey 08625 Mayor Lacey Township 818 West Lacey Road F Forked River, New Jersey 08731 D. G. Holland Licensing Manager I Oyster Creek Nuclear Generating Station Post Office Box 388 l Forked River, New Jersey 08731

- Mr. P. B. Fiedler Vice President & Director Oyster Creek Nuclear Generating Station Post Office Box 388

. Forked River, New Jersey 08731 t

7. _

L ATTACHMENT 1

,t MEETING OF FEBRUARY 13, 1985 ON THE ESSF Name Affiliation J. Donohew NRC/NRR/DL M. Laggart GPUN*

M. Hober State of New Jersey **

R. Wright NRC/NRR/DE J. Kudrick NRC/NRR/DSI N. Trikouros GPUN P. Wells GPUN P. Smith GPUN R. Lorenzo GPUN A. Rochino GPUN i

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The licensee stated that the request to not replace the containment purge and vent isolation valves by qualified valves will affect valves V-27-1/2, V-28-17/18/47, V-27-3/4, V-23-13/14 and V-23-15/16 in the figure in Attachment 2. All these are containment isolation valves. The request to not upgrade the nitrogen system will affect valves V-23-17/18, V-23-19/20, V-23-21/22 and V-28-47 of this figure.

The licensee stated that the commitment on the containment isolation valves is being considered to be withdrawn because these valves are blocked partially closed and met the staff's interim position for containment purge of October 23, 1979. The licensee would propose this interim position as its final position. The licensee stated that this position is conservative and the valves will close against the design basis accidents.

The licensee stated that considerations to propose the withdrawal of the commitment on the nitrogen system was based on the BWR Owner's Group model of the hydrogen source term for the LOCA. This model was an analysis performed by General Electric (NED0-22155). The licensee stated the BWR0G's model showed Oyster Creek should not reach the hydrogen flannability limit within 2 years after the LOCA.

The staff and the licensee discussed the technical arguments for the licensee's proposed withdrawal of its conunitments. The staff stated that the licensee should propose additional technical specifications on the existing containment vent and purge isolation valves to inspect and test these valves if they 'have resilient seals. The valves that would replace the existing valves do not have resilient seals. The staff referred to its January 18, 1985, letter to the BWROG which stated that a containment high range radiation signal should go to all containment vent and purge isolation valves,-large and small. The staff stated that 10 CFR Part 50.44(d) provides a design basis hydrogen source and that Generic Letter 84-09 (May 8, 1984) provides a basis for an exemption to the recombiner capability required in 10CFRPart50.44(c)(3)(ii)butitisnotapplicablefordesignbasis accidents.

Thelicenseesubmitteditsrequesttowithdrawthecommitmentsto(1) install qualified containment vent and purge isolation valves and (2) upgrade the nitrogen vent and purge system in its letter dated September 24, 1985.

Jack N. Donohew, Project Manager BWR Project Director #1 Division of BWR Licensing Attachments:

1. List of Attendees DISTRIBUTION
2. Licensee Handout ,M;D NRC PDR

.cc: J. Zwolinski Local PDR G. Lear BWD#1 Rdg H. Kister, Region I JZsolinski J. Chen JDonohew K. Leu OELD N. Chokshi EJordan 3

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