ML20211Q042

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Summary of 860623 Meeting W/Util & Burns & Roe,Inc at Site Re Sealing of Electrical Conduit to Meet Fire Protection Requirements & Potential Fire Protection Technical Exemptions.List of Attendees,Handout & BWR STS Encl
ML20211Q042
Person / Time
Site: Oyster Creek
Issue date: 07/16/1986
From: Donohew J
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8607230478
Download: ML20211Q042 (10)


Text

g f' %g UNITED STATES NUCLEAR REGULATORY COMMISSION

, 5 p WASHINGTON, D. C. 20555

\*****/ July 16, 1986 Docket No. 50-219 LICENSEES: GPU Nuclear Corporation Jersey Central Power and Light Company FACILITY: Oyster Creek Nuclear Generating Station

SUBJECT:

JUNE 23, 1986, MEETING WITH GPU NUCLEfR CORPORATION (GPUN)

TO DISCUSS SEALING OF ITS ELECTRICAL CONDUIT TO MEET FIRE PROTECTION REQUIREMENTS AND POTENTIAL FIRE PROTECTION TECHNICAL EXEMPTIONS On Monday, June 23, 1986, a meeting was held at Oyster Creek Station site with GPUN, the licensee, on how it plans to seal its electrical conduits to meet fire protection requirements and on potential fire protection technical exemptions. In the meeting summaries dated February 28 and May 22, 1986, of meetings between the licensee and the staff, the licensee explained that it

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was planning to submit technical exemptions to Appendix R to 10 CFR Part 50 before the restart from the current Cycle 11 Refueling (Cycle 11R) outage.

The licensee stated that these exemptions are similar to exemptions that the staff has granted to other licensees. This meetino served as an information exchange between the licensee and the staff before the licensee submits its reauest for exemptions to Appendix R.

Attachment 1 is the list of individuals who attended the meeting. Attachment 2 is the agenda for the meeting' handed out by the licensee. The following is a sumary of the significant items discussed and the actions, if any, taken or proposed. The sumary will be in terms of the issues listed in the agenda.

1.0 Conduit Internal Seals The licensee explained its criteria on sealing the electrical conduit was based on the internal conduit seal testing done at Perry Nuclear Plant. This is for sealing the conduit which is penetrating fire barriers at Oyster Creek. The Oyster Creek plant is currently in its outage for Appendix R modifications and must complete these modifications, includino conduit sealing, before the restart from this outage.

The staff and the licensee discussed the criteria for sealing conduit that came from testing performed at Perry and the differences being considered by the licensee in developing its criteria for Oyster Creek. The licensee stated that the criteria it expected to use for Oyster Creek is more restrictive than that used for Perry. The licensee discussed the specific differences between the Perry criteria and the criteria for Oyster Creek. This discussion was an information exchange and no decisions were made.

2.0 Potential Exemption Reauests The following discussions were of potential requests for technical exemptions to Appendix R. The licensee has not submitted a request for exemptions 8607230478 860716 PDR F

ADOCK 05000219 PDR

July 16, 1986 since its letter of April 3, 1985. The staff's approval of these exemptions is in its letter and safety evaluation dated March 24, 1986. The discussions in this meeting are on possible exemptions other than those previously approved by the staff.

The licensee explained that it will issue revision 4 of its Fire Protection Plan. This revision will contain the agreements it made with the staff in its October 9,1985, letter on its fire protection exemptions. Revision 5 will address the exemptions to be discussed in this meetino if these exemptions are submitted to the staff. These potential exemptions are the followina:

(1) Manual Action To Re Taken To Operate Valves These actions would be taken in a fire zone after the fire has been extinguished.

These manual actions would be required to operate valves for the safety of the plant and would be instead of providing remote operation of these valves. The staff acceptance of such manual operation is an exemption to the requirements of Appendix R.

The specific manual actions on opening valves which were discussed are the following:

(a) close the reactor vessel isolation valves to the reactor water cleanup system within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after shutdown to prevent loss of water from the vessel, (b) close the injection valves for the core spray system within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after shutdown to prevent loss of water from the reactor vessel, (c) open valves from the reactor vessel to the condensate storage tank within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 24 minutes after shutdown to add water to the vessel, and (d) open valves from the condensate storage tank to the core spray system within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after shutdown to add water to the reactor vessel.

(2) Fire wrappings, to prevent spurious signals, of three terminal boxes and terminals in the boxes for three electrical penetrations based on nearby fire suppression and detection systems.

(3) Manual action to repair loss of motor control center (MCC) for control room HVAC in a fire in the 480 switchgear room. The repair is outside the fire area and is required within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> after the loss of the MCC.

(4) Manual action to repair loss of 1A2/182 crosstie breaker in the A 4160/480 volt switchgear room. The repair is to disconnect the breaker from the IR?

bus in the R switchgear room which is next to the A switchgear room.

(5) Manual action to open the inlet and exhaust dampers to the A,B battery room and close the recirculation dampers within 45 minutes. This is external to the fire area. The dampers are designed to fail close to prevent cooling of the room in winter.

July 16, 1986 The staff discussed the potential exemptions listed above with the licensee.

The staff stated that the licensee must address the number of station personnel needed for the worst fire and the actions that the personnel must take to respond to the fire. These actions must include the actions discussed at this meeting. The discussion was an information exchance and no decisions were proposed or made.

3. Summary The staff requested that the formal submittal of exemptions to Appendix R be sent to the staff no later than August 15, 1986 The licensee must also submit Technical Specifications (TS) changes to reflect the requirement on the alternate shutdown panel and to revise the existing fire protection tables in the TS. This must be before the restart of the current outage. Acceptable TS on the alternate shutdown panel from the RWR Standard Technical Specifications are in Attachment 3.

The staff stated that the fire inspection by NRC Region I is oresently scheduled for November 1986 afte'r the restart from the current outage. Personnel from the staff will attend this inspection.

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j Jack N. Donoheh,.1r., Project Manager y RWR Project Directorate #1 Division of BWR Licensing Attachments:

1. List of Attendees
2. Licensee's handout
3. BWP Standard Technical Specifications cc: R. Bernero G. Lainas G. Hulman M. Srinivasan

_ l 0FC :BWD1: DBL :RYD1 L :BWD1: DEL :BWD1: DBL  :  :  :

_____:_________ :_. ____:____:._l______:.___________:____________:____________:___________

NAME :CJamerson .df ono ew:em :JS :JZwolinski :  :  :

_ _ _ _ _ : _ _ _ _ _ _ _ _ _ _ _ : N_ L..y_______:_.

_ : _ _ .ga gA ___________:___________

DATE :07/pl/86 :07/1g/86 :07/N /86 :07/D/86  :  :  :

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Y OFFICIAL RECORD COPY

  • Oyster Creek Nuclerr Generating Station cc:

Ernest L. Blake, Jr. 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 Commissioner Rishop, 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 Ouality U.S. Nuclear Regulatory Commission Department of Environmental 631 Park Avenue Protection King of Prussia, Pennsylvania 19406 380 Scotch Road Trenton, New Jersey 08628 BWR Licensing Manager P. B. Fiedler GPU Nuclear Vice President & Director 100 Interpace Parkway Oyster Creek Nuclear Generating Station Parsippany, New Jersey 07054 P. O. Box 388 Forked River, New Jersey 08731 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 Forked River, New Jersey 08731 D. G. Holland i Licensing Manager Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731 i

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ATTACHMENT 1 MEETING WITH GPU NUCLEAR CORPORATION (GolfN)

TO DISCUSS FIRE PPOTECTION June 23, 1986 NAME ORGANIZATION J. Donohew NRC/NRR/ DBL J. Stang NRC/NRR/ DBL G. Busch GPUN J. Yuen GPUN M. Sanford GPUN M. Coltmreary GPUN

- J. Siegel GPUN F. Collado GPUN  :=

R. Podesfinski Burns and Roe, Inc.

R. Ashby GPUN A. Bais GPUN

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ATTACHMENT 2 POIPTS OF DISCUSSION

1. Conduit Internal Seals
2. Exemption Requests
3. Submittals e
4. Inspection i

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, ATTACHMENT 3  :

. Y INSTRIJMENTATION I c- .

r'j REMOTE SHUTDOWN MONITORING INSTRUMENTATION i

LIMITING CONDITION FOR OPERATION 1

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3.3.6.4 The remote shutdown monitoring instrumentation channels shown in Table 3.3.6.4-1 shall be OPERABLE with readouts displayed external to i i the control room. -

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-( APPLICABILITY: CONDITIONS 1, 2, and 3. ,

ACTION:

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.. a. With the number of OPERABLE remote shutdown monitoring channels ,

s less than the requirements of Table 3.3.6.4-1, either restore the inoperable channel to OPERABLE status within 30 days, or be in at

. least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN

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within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. .

, [ b. The provisions of Specification 3.0.4 are not applicable.

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t-c SURVEILLANCE REQUIREMENTS N

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4.3.6.4 Each of the above required remote shutdown monitoring instru-l c ?? mentation channels shall be demonstrated OPERABLE by performance of the i i, y;' CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies l  ;;. shown in Table 4.3.6.4-1.

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TABLE 3.3.6.4-1 REMOTE SHUTDOWN INSTRUMENTATION R

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d MINIMUM READOUT CHANNELS FUNCTIONAL UNIT LOCATION OPERABLE

1. Reactor Vessel Pressure -

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2. Reactor Vessel Water Level 1 1
3. Safety / Relief Valve Position ((2) valves) 1
4. Suppression Chamber Water Level 1 f 5. Suppression Chamber Water Temperature 1
6. Suppression Chamber Air Temperature 1 1 w l 'e 1 7. Drywell Pressure 1 i w j h 8. Drywell Temperature 1 i

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TABLE 4.3.6.4-1 REMOTE SHUTDOWN INSTRUENTATION SURVEILLANCE REQUIREMENTS cn T

w d CHANNEL CHANNEL FUNCTIONAL UNIT CHECK CALIBRATION

1. Reactor Vessel Pressure M Q i

i 2. Reactor Vessel Water Level M Q

3. Safety / Relief Valve Position M NA 4
4. Suppression Chamber Water Level M R
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5. Suppression Chamber Water Temperature M R l w 6. Suppression Chamber Air Temperature M R

! 5 1 w 7. Primary Containment Pressure M Q

8. Drywell Temperature M R 9.

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Distribution for Meeting Sumary Dated: July 16, 1986 Facility: Oyster Creek Nuclear Generating Station

  • q Docket J (50-21h ma. YUR Local PDR BWD1 Readina J. Zwolinski J. Donohew J. ,Stang
y. Jamerson OGC(Forinfoonly)

E. Jordan B. Grimes ACRS (10)

R. Bernero G. Lainas G. Hulman '

M. Srinivasan OC File

  • Copies sent to persons on facility service list i

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