ML20052G752
| ML20052G752 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 05/13/1982 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| LAC-8290, NUDOCS 8205180638 | |
| Download: ML20052G752 (3) | |
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[k COOPERATNE
- PO BOX 817 2615 EAST AV SOUTH
- LA CROSSE. WISCONSIN 54601 (608) 788-4000 May 13, 1982 In reply, please refer to LAC-8290 DOCKET NO. 50-409 Director of Nuclear Reactor Regulation ATTN:
Mr. Dennis M. Crutchfield, Chief Ope.ating Reactors Branch #5 Division of Operating Reactors U.
S.
Nuclear Regulatory Commission Washington, D.
C.
20555
SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE NO. DPR-45 10 CFR 50, APPENDIX J - CONTAINMENT BUILDING LEAKAGE TESTING
References:
(1) 10 CFR 50 APPENDIX J (2)
LACBWR Technical Specifications (3)
NRC Letter, Goller to Madgett, dated August 5, 1975.
(4)
DPC Letter, Madgett to Goller, LAC-3379, dated September 9, 1975.
(5)
AEC Letter, Skovholt to Madgett, dated December 1, 1972.
Gentlemen:
Reference 3 requested that DPC determine if containment testing was being conducted in accordance with Reference 1.
Reference 4 described areas in which the LACBWR program differed from Appendix J.
One additional minor difference has been identified.
A description of the difference and justification for maintaining' the LACBWR program as-is follows.
The requirements for containment leakage tests are set forth in Reference 1.
Section I, the Introduction, states in part:
1 "The purposes of the tests are to assure that (a) leakage j
through the primary reactor containment and systems and components penetrating primary containment shall not exceed allowable leakage rate values as specified in the Technical Specifications or associated bases"...
The term La is defined in Section II as the maximum allowable leakage rate in percent /24 hours at pressure Pa as specified for preoperational 017
- 820 518 0 (f 37
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-O Mr. Dennis'M. Crutchfield, Chief LAC-8290 Operating Reactors Branch #5 May 13, 1982 tests in the Technical Specifications or associated bases, and as specified for oeriodic tests in the operating license.
Section III. A. 5. (b) (2), however, states the acceptance criteria for periodic peak pressure tests is that the measured leakage rate shall be less than 0.75 La.
LACBWR Technical Specifications, Reference 2,.Section 2, Design and Performance Requirements, states in part:
"2.1.1.1 The containment vessel chall be capable of containing an internal pressure of 52 poig at 280 F, and it chall be capable of withstanding an external-over-internal precoure of 0. 5 pai.
2.1.1.2 The leakage rate from the containment vessel shall correspond to a leakage rate that, per 24-hr.
period, does not exceed 0.1 percent by ucight of a steam-air mixture at 273*F, 28.5 poig, and a steam-to-initial-air ratio of 2.2."
Reference 2, Section 5.2.1.1.,
" Containment. Integrated Leakage Rate Test (Type A Tests)" states:
"(b)
Acceptance Criteria:
The maximum allouable teot leakage rate Lpm chall not exceed 0.1 percent per 24 houra at the test preocure of 52 poig.
If local, leakage measure-menta are taken to effect repairo in order to meet the acceptance criterion, these measurements shall be taken at a test preocure of 52 poig.
To provide a margin for possible deterioration of_the con-tainment leakage integrity during the service interval extending to the cubacquently acheduled Type A test, the measured leakage rate Lpm shall.be reduced, if_necessary, to a value Lpo not in excess of 75% of the leakage rate limit (0.075% per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at the test preocure of 52 peig).
This leakage reduction chall be accomplished prior to re-cumption of plant operation."
The above Technical Specification was approved by the Atomic Energy Commission in Reference 5.
The AEC concluded:
"We have revieued your proposal to perform containment leakage tests three timca within a period of ten' years rather than the preacnt annual test.
We have concluded that performance of the teata in the' manner you have described is consistent with the proposed Appendix J to 10 CFR Part 50 and provideo an acceptable test program.
We also have concluded that the 1
F-i Mr. Dennis M.
Crutchfield, Chief LAC-8290 Operating Reactors Branch #5 May 13, 1982 proposed changco do not present significant hazards not described or implicit in the LACBWR Safety Analysis Report (Hazardo Summary Report, as amended) and that there is reaaonable accurance that the health and cafety of the public vill not be endangered by these changes.
Accordingly, pursuant to Section 115.47 of 10 CFR 116, the Technical Specifications of Provisional _ Operating Authorization No. DPRA-G are hereby changed as act forth in Attachment A to this letter to include the changes you have proposed."
DPC agrees with the AEC conclusion.
The acceptance criteria in the LACBWR Technical Specification meets the purpose of the Appendix J regulation quoted above, that leakage not exceed allow-able leakage rate values as specified in the Technical Specifica-tions or associated bases.
The additional criteria for startup in the LACBWR Technical Specifications matches the criteria in Appendix J,Section III. A. S. (b) (2).
Therefore, as concluded by the AEC, the acceptance criteria in the LACBWR Technical Specifica-tions is consistent with Appendix J and there is reasonable assurance that the health and safety of the public will not be endangered by the LACBWR acceptance criteria.
Therefore, a change to the LACBWR Integrated Leak Rate Test program is not necessary.
If you have any questions regarding this submittal, please let us know.
Very truly yours, DAIRYLAND POWER COOPERATIVE h
i Frank Linder, General Manager 1
i l
PL:LSG:af l
cc:
J.
G.
Keppler, Dir., NRC-DRO III NRC Resident Inspector R. Dudley, NRC-NRR i
l-.. _
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