ML20215E067
| ML20215E067 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 12/01/1986 |
| From: | Bernero R Office of Nuclear Reactor Regulation |
| To: | BOSTON EDISON CO. |
| Shared Package | |
| ML20215E071 | List: |
| References | |
| NUDOCS 8612170219 | |
| Download: ML20215E067 (3) | |
Text
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l 7590-1 l
UNITED STATES OF AMERICA l
NUCLEAR REGULATORY COMMISSION l
In the Matter of
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Docket No. 50-293 f
BOSTON EDISON COMPANY
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Pilgrim Nuclear Power Station
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EXEMPTION I.
Boston Edison Company (BEC0/the licensee) is the holder of Facility Operating License No. DPR-35 which authorizes the operation of the Pilgrim
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Kuclear Power Station (the facility) at a steady-state power level not in
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eie:ess of 1998 megawatts thermal. The facility includes a boiling water
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reactor (BWR) and is located at the licensee's site in Plymouth County, Massachusetts.
II.
By letter dated August 29, 1986, the licensee requested a schedular exemption from the 18-month test frequency requirement in 10 CFR Part 50, Appendix J, Section III. A.6(b). This section states that:
"If two consecutive periodic Type A tests fail to meet the applicable acceptance criteria in III.A.5(b), notwithstanding the periodic test schedule of III.D, a Type A test shall be perfomed at each plant shutdown for refueling or approximately every 18 months, whichever occurs first, until two consecutive Type A tests meet the acceptance criteria in III.A.5(b),
Although the most recent Type A primary containment leakage test conducted at Pilgrim Station in December 1984 met the criteria in III.A.5(b), the previous test did not. The above testing frequency therefore applies.
8612170219 861201
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PDR ADOCK 05000293 P
PDR l
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', III.
The Pilgrim Station was shut down on April 12, 1986 to make certain repairs and the outage has continued for various reasons, including a decision by the licensee to refuel the reactor prior to restarting the plant. This decision created the circumstances whereby two Type A tests will have to be performed during the current refueling outage (RF0 #7) unless relief is granted. The first Type A test would need to be conducted upon completion of the present ongoing Type B and C testing of air locks and valves, which, in accordance with the 18-month frequency requirement, commenced in June 1986. The second Type A test would be required following completion of all outage werk, including refueling.
IV.
Type A testing is performed to assure that primary containment leakage is within acceptable limits during plant operation. Pilgrim Station will not be operating prior to the end of RF0 #7 next spring, at which time a Type A test will be successfully performed. Thus, the performance of an earlier Type A test to meet the 18-month schedular requirements is unnecessary to achieve the underlyina purpose of the rule.
V.
Based upon the considerations described above, the staff has concluded that the licensee has presented a sound rationale for its need of schedular relief which will allow postponement of Type A testing until the end of RF0 #7.
.-:,. This will not present undue risk to the public health and safety because
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Pilgrim wil1 remain shut down until completion of the Type A testing following refueling.
In addition, the licensee will fix any leaks identified by the testing prior to restart.
The Commission has detennined that, pursuant to 10 CFR 50.12(a)(1), the schedular exemption requested by the licensee's letter of August 29, 1986, is authorized by law, will not present an undue risk to the public health and safety, and is consistent with the common defense and security. The Comission has further determined that special circumstances, as described in 10 CFR 50.12f a)(2)(ii), are present, namely, that application of the regulation in the particular circumstances would not serve the underlying purpose of the rul e.
Accordingly, the Comission crants this Exemption from the schedular requirements of 10 CFR Part 50, Appendix J.Section III.A.6(b) for the performance of a Type A containment leakage test until after refueling has been accomplished durinp refueling outage #7 and any leaks' identified by this testing shall be repaired prior to restart.
Pursuant to 10 CFR 51.32, the Commission has determined that the issuance of this exemption will have no significant impact on the environment (51 FR41308, November 28,1986).
This exemption is effective upon issuance.
Dated at Bethesda, Maryland this 1st day of December 1986.
l FOR THE NUCLEAR REGULATORY COMMISSION f
- r Robert M. Bernero, Director Division of BWR Licensing Office of Nuclear Reactor Regulation m
.