ML20049J182
| ML20049J182 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 03/04/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Fiedler P JERSEY CENTRAL POWER & LIGHT CO. |
| Shared Package | |
| ML20049J183 | List: |
| References | |
| LSO5-82-03-024, LSO5-82-3-24, NUDOCS 8203120233 | |
| Download: ML20049J182 (7) | |
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'g UNITED STATES o
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p, NUCLEAR REGULATORY COMMISSION flRC PDR WAS$41NGTON, D. C. 20555 j
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March 4,1982 ORB Reading NSIC l
HSmith DCrutchfield Docket No. 50-219 LS05-82-03-024 OELD g
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ACRS (10) co SEPB Mr. P. B. Fiedler JLombardo e
Vice President ari Director - Oyster Creek
'N Oyster Creek Nuciear Generating Station p
HEC 5fYEO Post Office Box 388
(,#awIMRy7b0$2h..
I Forked River, New Jersey 03731
Dear Mr. Fiedler:
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SUBJECT:
APPENDIX J TO 10 CFR PART 50
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- 43 RE:
Oyster Creek Nuclear Generating Station a
This letter transmits the Safety Evaluation (SE)3r t'he Appendix J f
review for the Oyster Creek Nuclear Generating Station in response to your letter dated December 24, 1975, as supplemented by letters dated August 12, 1976, November 22, 1978 and June 27, 1980. We find the analysis submiyted by GPU Nuclear Corporation (GPUNC) to be acceptable as reflected fn our SE.
In addition, your letter dated June 27, 1980 stated that nodifications to the Instr -
t Air / Nitrogen Sys' ten and the Demineralized Water System were co.pleted during a 1980 outage, and that al.1 other modifi-cations will be completed duringp 1981 (cycle 10) refueling outage.
The cycle 10 refueling outageTiginally scheduled for November 1981 has been mutually ed upon to be rescheduled for the summer of 1982.
You are requested to sbbmit your proposed Technical Specifications within 30 days of receipt of this letter.
Since this request for information is plant specific OMB clearance is not required under P.L.96-511.
Sincerely,
. i Dennis M. Crutchfield, hief Operating Reactors Branch #5 Division of Licensing
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Mr. P. B. Fiedier 2-March 4,1982
Enclosure:
Safety Evaluation Report w/ Technical Evaluation Report dated May 21, 1981, by Franklin Research Center cc w/ enclosure:
See next page 9 9 g
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Mr. P. B. Fiedler March 4,1982 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. Lieber nan, Esquire Commissioner Berlack, Israels & Lieberman New Jersey Department of Energy 26 Broadway 101 Commerce Street New York, New York 10004 Newark, New Jersey 07102 Natural Resources Defense Council Ronald C. Haynes, Regional Administrator 917 15th Street, N. W.
Nuclear Regulatory Commission, Region I Washington, D. C.
20006 Office of Inspection and Enforcement 631 Park' Avenue J. Knubel King of Prussia, Pennsylvania 19406 BWR Licensing Manager GGPU Nuclear 100 Interplace Parkway Parsippany, New Jersey 07054 Deputy Attorney General State of New Jersey.
Department of Law and Public Safety 36 West State Street - CN 112 Trenton, New Jersey 08625 Ms. Phyllis Haefner 101 Washington Street l
Toms River, New Jersey 08753 l
l Mayor Lacey Township 818 Lacey Road Forked River, New Jersey 08731 l
U. S. Environmental Protection
' gen:y Region II Of fice ATTN:
Regional Radiation Representative 26 Federal Plaza New York, New York 10007 Licensing Supervisor Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731
ENCLOSURE UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION SAFETY EVALUATION REPORT APPENDIX J REVIEW OYSTER CREEK DOCKET NO. 50-219
1.0 INTRODUCTION
On August 7,1975[1], the NRC requested Jersey Central Power and Light (JCP&L) Company to review its containment leakage testing program ~for Oyster Cre.ek and the associated technical specifications, for compliance with the requirements of Appendix-J to 10 CFR Part 50.
Appendix J to 10 CFR Part 50 was published on Februar.y '14,'1973.
Since by this date there were already many operating nuclear plants and a number more in advanced stages of design or construction, the NRC decided to have these plants re-evaluated against the requirements of this new regulation.
Therefore, beginning in August 1975, requests for review of the extent of compliance with the requirements of Appendix J were made of each licensee.
Following the initial responses to these requests, NRC staff positions were developed which would assure that the objectives of the~ testing requirements of the above cited regulation were satisfied.
These staff positions have
.since been applied in our review of the submittals filed by the licensee for 0yst.e.r Creek _.
The results of our evaluation ar'e provided below.
2.0 EVALUATION Our consultant, the Franklin Research Center (FRC), has reviewed the licen-see's submittals [2, 3, 4] and prepared the attached evaluation of contain-men't tests for Oyster Creek, Unit 'l.
'We have reviewed this evaluation and concur in its bases and findings.
3.0 CONCLUSION
Based on our review of the attached technical evaluation report regarding the referenced Appendix J submittals by JCP&L for Oyster Creek
~
, e conclude.that:
w 1.
The licensee's request [4] that the~ systems or portions of the systems listed below need not be vented and drained prior to and during the Type A test is acceptable, and exemptions from the requirements of Appendix J are n.ot needed.
Emergency condenser system condensate' return
~
Reactor sample line
~
Reactor cleanup system Feedwater system CRD hydraulic return to reactor Liquid poison Core spray to reactor Reactor coolant instruments Shutdown cocling Reactor building closed cooling water I
CRD insert and withdraw lines.
2.
The licensee's request that the root-mean-square-error, derived from a statistical analysis of instrument error, not be added to the measured leakage rate is acceptable. The licensee has indicated that the reported leakage rate is the upper limit of the 95 percert conficence level on the calculated leakage rate. The applicant also performs supplemental tests; therefore, the requirements of Section III.A.3(C) of Appendix J are satisfied and no exemption from the regulation is necessary.
l l
The licensee's request [4] to test drywekl airlocks at 6-month inter-3.
vals at Pa (35 psig), and within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of every first of a series of openings at 10 psig, is found acceptable.
No exemption from the require-ments of Appendix J is necessary because of the revision to Section III.D.2 of Appendix J, effective October 22, 1980. However, the measured result of a reduced pressure tes't should be extrapolated to Pa to determine the test acceptability, using the formula reconmended in the attached report or other equivalent method.
4.
The licensee's request [4] for ex*emptidH' fro ~m Type C testing require-ments for Valves V-17-19 and V-17-54 (Shutdown Cooling System), and Valves V-14-30 and V-14-39 (Emergency Condenser System) is found ac-ceptable.
No exemption from Appendix J requirement is necessary.
4.0 REFERENCES
1.
NRC Generic letter to JCP&L regarding implementation of 10 CFR Part 50, Appendix J at Oyster Creek, dated August 7,1975.
i i
2.
JCP&L lette.r from I. R. Finfrock, Jr.
to K. R. Goller (NRC), dated December 24, 1975.
l JCP&L letter from I. R. Finfrock, Jr. to Secret $ry (USNRC), dated 3.
August 12, 1976.
4.
JCP&L letter from I. R. Finfrock, Jr., to Director (NRR), dated November 22, 1978.
5.
JCP&L letter from I. R. Finfrock, Jr. to, Director (NRR),
dated June 27, 1980.
Attached:
TER prepared by Franklin Research Center dtd.
May 21,1981 Date:
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