ML20008E653
| ML20008E653 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/28/1981 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20008E651 | List: |
| References | |
| NUDOCS 8103090340 | |
| Download: ML20008E653 (3) | |
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Docket No. 50-2h5 ATTACIMENT Millstone Nuclear Power Station, Unit No.1 PROPOSED TECIINICAL SPECIFICATION CFjdIGES FOR LOCAL LEAK RATE TF3T February, 1981 810 809 0 'bgo
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DESCRIPTION OF CHANCES AND SAFETY EVALUATION
SUMMARY
The proposed changes to the Millstone Unit No. 1 Technical Specifications would revise the preser.t acceptance criteria for the local leak rate test to be consistent with the Standard Technical Specifications for General Electric Boiling Water Reactors, Sectica 3/4.6.1, and 100FR50, Appendix J,Section III.C.3.
The attached changes would increase the combined Type B and C leak rate test limits from 40% L to 60% L before repairs and retests eo a
would need to be performed to correct the condition.
La, which is the maximum allowable leak rate at 43 psig, shall not exceed 1.2 weight percent per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The allowable operational leak rate, L o, shall not exceed t
75% La.
The FSAR off-site dose calculations are based on 5.0 weight percent per day leakage. The proposed changes do not effect the maximum values of L o or La, which are already significantly less than the leak rate t
assumed in the FSAR off-site dose calculations.
I Implementation of the modifications committed to in Reference (3) require a larger number of valves being included in the local leak rate test, as well as some present valves being reversed such that test pressure tends to unseat the valves and accident pressure tends to seat them. Therefore, implementation of these modifications may increase the total leakage during testing, but it should also increasa overall safety. The proposed changes would only increase the combined Type B and C leak rate test limits before repairs and retests would be required. However, once again, La and Leo remain uneffected by the proposed changes.
Pursuant to 10CFR50.59, these changes have been reviewed, and it has been determined that they do not involve any unreviewed safety questions in that they do not increase the probability of occurrence or the consequences of an a(cident or malfunction of equipment, create a possibility for a different type of accident or malfunction, or reduce the margin of safety as defined in the Technical Specifications.
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LIMITiNS CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT e.
Local Leak Rate Tests (LLRT)
(1) Primary containment testable pentrations and isolation valves shall be tested at a pressure of 43 psig except the main steam line isolation valves shall be tested at a pressure of 25 psig each operating cycle. Bolted double-gasketed seals shall be tested whenever the seal is closed after being opened and at least once during each operating cycle.
(2) Personnel air lock door seals shall be tested at a pressure of 43 osig at least once every 6 months.
If the airlock is opened when primary containment integrity is required during the interval between the above tests, the air lock door seals shall be tested at 10 psig within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the first of a series of opening.
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Acceptant. criteria and corrective action for LLRT:
If the total leakage rates listed below are exceeded, repairs and retests shall be performed to correct the condition.
(1)
(a) A combined leakage rate of fE 0.60 La for all penetrations and valves, except for main steam isolation valves, subject to Type B and C tests when pressurized to Pa.
(b) Any one penetration or isolation valve except main steam isolation valves 5% L o (43).
t Amendment No. 9, EJ 3/4 7-8