ML18011A838
| ML18011A838 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 03/10/1995 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18011A837 | List: |
| References | |
| NUDOCS 9503170259 | |
| Download: ML18011A838 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAF TY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RE ATED 0
AME D ENT 0.
0 FACILITY OPERATING LICENSE NO. NPF-63 C
OL POWER 8I LIGHT COMPANY SHEARON HARRI NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400
1.0 INTRODUCTION
By letter dated December 19, 1994, Carolina Power
& Light Company (the licensee) submitted a request for changes to the Shearon Harris Nuclear Power Plant, Unit 1
(SHNPP), Technical Specifications (TS).
The proposed changes would revise Technical Specification 4.6.1.2.a, Overall Integrated Containment Leakage Rate, to provide a one-time extension for the third Type A test interval beyond the required TS surveillance interval of 40 months plus or minus 10 months.
This extension will allow the licensee to perform the third set of the three Type A tests for the first 10-year service period during refueling outage 7, which is currently scheduled for March 1997.
This one-time extension will allow the third Type A test to be performed approximately 54 months after the second Type A test, so that this test will coincide with first 10-year plant inservice inspections during refueling outage 7.
2.0 BACKGROUND
Section III.D.1(a) of Appendix J to 10 CFR Part 50 establishes the required retest schedule for Type A, overall integrated containment leakage rate tests.
The rule states that after the preoperational leakage rate tests, a set of three Type A tests shall be performed, at approximately equal intervals during each 10-year service period.
The third test of each set is required to be performed when the plant is shutdown for the 10-year plant inservice inspections.
At the SHNPP, the requirements of Appendix J are reflected in the test schedule included in TS 4.6..1.2.a.
This TS requires that three Type A tests shall be conducted at 40 plus or minus 10 month intervals during each 10-year service period.
The first and second type A integrated leak rate tests (ILRT) of the first 10-year service period for the SHNPP were performed in October 1989 and September 1992, respectively.
This represents testing intervals of 44 months (from the initial preoperational testing) and 35 months, respectively.
In order to meet all requirements of the rule and technical specifications, the licensee would need to perform the third ILRT at 36 months during refueling outage 6 that is currently scheduled for September 1995
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(for compliance with TS 4.6. 1.2.a);
and consequently, a fourth test would be needed during refueling outage 7 during the shutdown for the 10-year'lant inservice inspection (for compliance with 10 CFR Part 50, Appendix J, paragraph III.D.(a)).
In the December 19, 1994 request, the licensee proposed to extend the TS-required interval between the second Type A test and the third the Type A test to approximately 54 months because the current refueling outage schedules for the SHNPP cannot support both the schedule established in Appendix J and the plant TS 4.6.1.2.a.
This extension will allow the licensee to complete all three Type A tests for the first 10-year service period and also to perform the third Type A test during the first 10-year inservice inspection which is scheduled during the seventh refueling outage commencing in larch 1997.
- 3. 0 EVALUATION The intent of the established test interval is that three approximately equally spaced Type A tests be conducted within a given 10-year service period.
At SHNPP, the Appendix J and TS Type A testing requirements do not coincide with the anticipated refueling outage schedules such that the third Type A test would need to be performed during both the sixth and seventh refueling outages, resulting in a total of four Type A tests for the first 10-year inservice inspection period.
This additional testing, resulting solely from the circumstances of the refueling outage schedules, is contrary to the intent of the regulations and existing SHNPP TS.
The licensee stated in their December 19, 1994, submittal that the results of previously performed Type A tests indicate that an extension of the maximum test interval for the interval between the second and the third Type A tests by approximately four months will have no effect on the maximum allowable overall containment
- leakage, on the 0.75L, start-up limit, or on the requirement to perform the tests during outages.
Based on data from the first and second Type A ILRT conducted at the SHNPP, the licensee stated that the containment integrity for the plant is maintained continuously by the ILRT program.
The as-left leakage rate for the last ILRT was 0.0614 weight percent per day (wtX/day) which is well below the 0.075 wtX/day allowed by the TS.
The data illustrate that there is sufficient leakage margin for the containment to remain well below the.0.075 wtX/day allowed by the TS.
The licensee further stated that the majority of the leakage detected during both the first and second ILRT was from the containment penetrations and not from the containment barrier itself.
Local leak rate testing of penetrations will continue to be performed as required by TS and can be relied upon to detect the most probable sources of containment leakage.
The licensee would also be required by Appendix J,Section IV.A, to perform additional testing to demonstrate containment integrity if any major modifications affecting containment are performed prior to the proposed third Type A test during the seventh refueling outage.
l
Based on the past Type A test results, the continued performance of 'local leak rate testing, and the requirement of the Appendix J (that the three tasks be performed at approximately equal intervals),
the staff finds that the proposed one-time extension of the TS required test interval for Type A tests is consistent with the requirements of Appendix J and would not adversely affect or endanger the health or safety of the general public and is, therefore, acceptable.
3.0
~ET TE CONRULTATIOM In accordance with the Commission's regulations, the State of North Carolina official was notified of the proposed issuance of the amendment.
The State official had no comments.
- 4. 0 ENVIRONMENTAL CONSIDERATION The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes the Surveillance Requirements.
The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released
- offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a
proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (60 FR 6298).
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
- 5. 0 CONCLUSION The Commission has concluded, based on the considerations discussed
- above, that:.
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed
- manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
N. B.
Le Date:
MARCH 10, 1995