ML17058B855
| ML17058B855 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 07/12/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17058B854 | List: |
| References | |
| NUDOCS 9308030412 | |
| Download: ML17058B855 (10) | |
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 43 TO FACILITY OPERATING LICENSE NO. NPF-69 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR ST TION UNIT 2 DOCKET NO. 50-410
- 1. 0 INTRODUCTION By letter dated Hay 18,
- 1993, Niagara Mohawk Power Corporation (the licensee) submitted a request for changes to the Nine Nile Point Nuclear Station, Unit 2 (NHP-2), Technical Specifications (TSs).
The requested changes would revise TS 4.6. 1.2.a to provide a one-time extension of the required test interval for overall integrated containment leak rate tests (Type A tests).'S 4.6. 1.2.a requires that three Type A tests be 'conducted at 40 plus or minus 10-month intervals during each 10-year service period, and that the third test of each set of three be conducted during the shutdown for the 10-year plant inservice inspection.
Part 50 of Title 10 of the Code of Federal.Regulations (CFR), Appendix J,Section III.D.1, requires that a set of three approximately equally spaced Type A tests be performed during each 10-year service period, and that the third test of each set be conducted during the plant shutdown for the 10-year plant inservice inspection.
The licensee indicated in its submittal of Hay 18, 1993, that the first Type A test of the first 10-year service period was conducted on January 14, 1991, during the first refueling outage.
The next (third) refueling outage is scheduled to begin in October 1993.
If the second Type A test is performed during the third refueling outage to comply with the 40 plus or minus 10 months requirement, a
third Type A test would be required during the fifth refueling outage in 1996 or 1997.
In addition, a fourth Type A test would be required during the sixth refueling outage in 1998 or 1999 to coincide with the end of the 10-year inservice inspection period.
This would result in four tests being performed in the first 10-year inservice period, instead of the three Type A tests required by the TSs and 10 CFR Part 50, Appendix J.
The licensee stated in the submittal of Hay 18, 1993, that the need to conduct four'ype A tests during the first 10-year inservice period resulted from a short second fuel cycle (12 months).
The licensee has proposed that the maximum allowed test interval of 50 months be extended by 4 months on a
one-time basis to permit performance of the second Type A test during the fourth refueling outage that is scheduled to start in Hay or June 1995.
The licensee stated that the proposed changes would provide for. three approximately equally spaced Type A tests within the first 10-year inservice period, consistent with 10 CFR Part 50, Appendix J.'he licensee has proposed that the one-time extension of the test interval be incorporated into the TSs 9gp8p304i2 50004ip qS0712
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by adding a footnote to TS 4.6. 1.2.a.
The extension would expire upon
-completion of the fourth refueling outage.
Since the TS change proposed by the licensee is consistent with the requirements of 10 CFR Part 50, Appendix J, no exemption from the requirements of the regulations would be needed.
2.0 EVAN~10 The licensee has proposed that the following be added to the TSs as a footnote to TS 4.6.1.2.a:
"The test interval for conducting the second Type A test of the first 10-year service period shall be extended to 54 months to allow the Type A test to be performed during the 4th refueling outage.
This extension expires upon completion of the 4th refueling outage."
The intent of the established test interval is that three approximately equally spaced Type A tests be conducted within a given 10-year inservice period.
The proposed extension remains consistent with that intent.
The alternative of conducting the second periodic Type A test during the third refueling outage in order to meet the 40 plus or minus 10 months requirement would necessitate conducting four tests during the first 10-year inservice period.
This is clearly contrary to the intent of the regulations in 10 CFR Part 50, Appendix J, to have equally spaced Type A tests.
The licensee has estimated that performance of an additional test would add 4 days to the outage schedule with associated costs and 2.25 man-rem of exposure to test personnel.
The licensee has stated that the results of previous Type A tests indicate that an extension of the maximum test interval by 4 months would not jeopardize the ability of the containment to maintain the leakage rate at or below the applicable limit.
The allowable leakage rate stated in TS 3.6. 1.2.a is l. 1 percent by weight of the containment air per day when testing is performed at a pressure of 39.75 psig.
The preoperational Type A test performed on April 14, 1986, resulted in an integrated leakage rate of 0.6585 percent per day.
The Type A test performed on January 14,
- 1991, resulted in an integrated leakage rate of 0.623 percent per day.
The results of these two previous Type A tests showed that the actual average integrated leakage of primary containment was less than 58 percent of the TS limit.
In addition, the results of the first inservice Type A test showed that the ability of the containment to maintain leakage at or below the TS limits had not degraded during the previous 57 months.
Actual testing at NHP-2 has shown that approximately two thirds of the total primary containment leakage is from penetrations that receive Type B and C local leak rate tests.
These Type B
and C tests will continue to be performed at the frequency required by the TSs with repairs being performed as necessary.
The demonstrated operability of these penetrations will provide added assurance that overall containment leakage remains satisfactory.
The licensee also indicated that since the last Type A test there have been no permanent modifications to the containment structure, liner, or penetrations nor other temporary alterations that would adversely affect Type A test results.
No such modifications to the containment boundary are planned prior to the fourth refueling outage when the next Type A test would be conducted under the proposed TS change.
Any unplanned modifications to the containment prior to the next scheduled Type A test would be subject to the special testing requirements of 10 CFR Part 50, Appendix J, Section IV.A.
The licensee also stated that there have been no pressure or temperature excursions in the containment that could have adversely affected containment integrity.
Based on the past Type A test results and the absence of modifications to the containment and its penetrations, the staff finds that the proposed amendment for a one-time extension of the required test interval for Type A tests would not adversely affect plant safety and is, therefore, acceptable.
3.0
~5A CONKULTAT GN In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment.
The State official had no comments.
4.0 NVIRONMENTAL CONSIDERAT ON 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 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 (58 FR 32387).
Accordingly, the amendment meets the eligibilitycriteria 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.
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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:
John E. Penning Date:
July 12, 1993
- July 12, 1993 Docket No. 50-410 Hr.
B. Ralph Sylvia Executive Vice President, Nuclear Niagara Hohawk Power Corporation 301 Plainfield Road
- Syracuse, New York 13212
Dear Hr. Sylvia:
SUBJECT:
ISSUANCE OF AHENDHENT FOR NINE NILE POINT NUCLEAR STATION, UNIT 2 (TAC NO. H86448)
The Commission has issued the enclosed Amendment No.
43 to Facility Operating License No. NPF-69 for the Nine Nile Point Nuclear Station, Unit 2.
The amendment consists of changes to the Technical Specifications (TSs) in response to your application transmitted by letter dated Hay 18, 1993.
The amendment revises TS 4.6. 1.2.a to provide a one-time extension of the required test interval for overall integrated containment leak rate tests (Type A tests).
This extension will allow the second Type A test of the first 10-year service period to be performed during the fourth refueling outage and expires upon completion of that refueling outage.
A copy of the related Safety Evaluation is enclosed.
A Notice of Issuance will be included in the Commission's next regular biweekly Federal Re<eister notice.
r'incerely, Original signed by:
John E. Henning, Project Hanager Project Directorate I-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Enclosures:
l.
AmendmentiNo.'43 to NPF-69 2.
Safety Evaluation cc w/enclosures:
See next page Distribution:
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