ML17059A038
| ML17059A038 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 09/07/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17059A036 | List: |
| References | |
| NUDOCS 9309150070 | |
| Download: ML17059A038 (8) | |
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0 UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY TH OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.
47 0 FACILITY OPERATI G LICENSE NO.
PF-69 NIAGA MO AWK POWE CORPORATION NINE MILE POINT NUCLEAR STATION UNIT 2
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1.0 INTRODUCTION
By letter dated April 30,
- 1993, Niagara Mohawk Power Corporation (the licensee) submitted a request for changes to the Nine Mile Point Nuclear Station, Unit 2 (NMP-2), Technical Specifications (TSs).
The requested changes would revise Action Statement a.2. of TS 3.6.5.3.
This Action Statement is applicable in OPERATIONAL CONDITION
- when one standby gas treatment system (SGTS) subsystem is inoperable.
The proposed revision would permit handling of irradiated fuel in the reactor building, CORE ALTERATIONS, and operations with a potential for draining the reactor vessel to continue in OPERATIONAL CONDITION
The proposed revision would also permit entry into and continued oper ation in OPERATIONAL CONDITION
- with one SGTS subsystem inoperable provided the OPERABLE subsystem is in operation.
- 2. 0 EVALUATION Action Statement a.2. of TS 3.6.5.3, currently permits operations to continue for up to 7 days in OPERATIONAL CONDITION * ("When irradiated fuel is being handled in the reactor building and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel" ).
The provisions of TS 3.0.4 are currently applicable to Action Statement a.2. of TS 3.6.5.3; these provisions prohibit entry into OPERATIONAL CONDITION
- when one SGTS subsystem is inoperable.
The proposed change would remove the 7 day limit on continued operation with one subsystem inoperable provided the remaining OPERABLE subsystem is in operation.
The proposed change would also note that the provisions of TS 3.0.4 are not applicable for entry into OPERATIONAL CONDITION
- provided the OPERABLE subsystem is in operation.
The SGTS is provided to filter the reactor building atmosphere prior to its release to the environment.
The SGTS is composed of two 100X capacity subsystems which are normally maintained in a standby status.
Each subsystem starts automatically upon detection of high radiation levels in the reactor building.
Each subsystem has a rated capacity of approximately 4000 cubic feet per minute and is designed to maintain a negative pressure in the reactor building of at least 0.25 inch water gauge with respect to the outside 0
93091 50070.930907 PDR ADOCK 05000410 PDa
atmosphere when the subsystem is operating.
This negative pressure ensures that air discharged from the reactor building is filtered before its release to the environment so as to minimize the release of radioactivity to the environment.
During normal operations in OPERATIONAL CONDITION *, the reactor building is ventilated by its normal ventilation system.
The normal ventilation system maintains the reactor building at a negative pressure of at least 0.25 inch water gauge with respect to the outside environment but this system does not have the capability to filter radioactivity from the discharged air. 'If radioactive materials are released into the reactor building atmosphere and their concentrations exceed a predetermined limit, the normal ventilation system is automatically stopped and isolated.
The OPERABLE SGTS subsystems are then automatically started.
Operation of a single OPERABLE subsystem will reestablish the required negative pressure in the reactor building and provide a filtered release to the environment.
The first part of the proposed change would remove the 7-day limit on continued operation with one SGTS subsystem inoperable provided the remaining OPERABLE subsystem is in operation.
This part of the proposed change is acceptable since placing the OPERABLE subsystem in operation ensures that its safety function (filtering of the reactor building atmosphere before release to the environment) is being accomplished.
This part of the proposed change is also consistent with the NRC staff's current position which permits continued operation with one SGTS subsystem provided the OPERABLE subsystem is in operation.
The NRC staff's current position is reflected in the guidance provided in the NRC's revised Standard Technical Specifications (STS) for Boiling Water Reactors (NUREG-1433).
The second part of the proposed change would provide that the provisions of TS 3.0.4 are not applicable for entry into OPERATIONAL CONDITION
- when one SGTS subsystem is inoperable and other subsystem is in operation.
NHP-2 TS 3.0.4 prohibits entry into an OPERATIONAL CONDITION unless the conditions of the Limiting Condition for Operation are met without reliance on the ACTION requirement.
The proposed exclusion from the provisions of TS 3.0.4 is consistent with the guidance provided in NRC Generic Letter (GL) 87-09, "Sections 3.0 and 4.0 of the Standard Technical Specifications (STS) on the Applicability of Limiting Conditions for Operation and Surveillance Requirements," for ACTION requirements which permit continued operation of the facility. for an unlimited period of time and is, therefore, acceptable.
TS 3.0.4 of NUREG-1433 includes the above noted provisions of GL 87-09.
Therefore, an exclusion from the provisions of NMP-2 TS 3.0.4 must be provided in Action Statement a.2. of TS 3.6.5.3.
The proposed change includes all related requirements of NUREG-1433.
Consequently, we have concluded that this proposed change satisfies the Commission's Final Policy Statement on TS (58 FR 39132).
The NRC staff is considering these changes as a potential line-item improvement of the NRC's STS.
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~IA UIIAAULTATIU 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 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.
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 ther'e has been no public comment on such finding (58 FR 32385).
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:
Donald S.
Brinkman Date:
September 7,
1993
Docket No. 50-410 Hr. B. Ralph Sylvia Executive Vice President, Nuclear Niagara Mohawk Power Corporation 301 Plainfield Road
- Syracuse, New York 13212 September 7,
1993
Dear Hr. Sylvia:
SUBJECT:
ISSUANCE OF AMENDMENT FOR NINE MILE POINT NUCLEAR STATION, UNIT 2 (TAC NO. H86379)
The Commission has issued the enclosed Amendment No. 47 to Facility Operating License No.
NPF-69 for the Nine Mile Point Nuclear Station, Unit 2.
The amendment consists of changes to the, Technical Specifications (TSs) in response to your application transmitted by letter dated April 30, 1993.
The amendment revises Action Statement a.2. of TS 3.6.5.3.
This Action Statement is applicable in OPERATIONAL CONDITION
- when one standby gas treatment system (SGTS) subsystem is inoperable.
This revision to Action Statement a.2. of TS 3.6.5.3 permits handling of irradiated fuel in the reactor building, CORE ALTERATIONS, and operations with a potential for draining the reactor vessel to continue in OPERATIONAL CONDITION
This revision also permits entry into OPERATIONAL CONDITION
- with one SGTS subsystem inoperable, provided the OPERABLE SGTS subsystem is in operation.
The changes approved by this license amendment are being considered by the NRC staff as a potential line-item improvement to the NRC's Standard Technical Specifications.
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.
Sincerely,
Enclosures:
l.
Amendment No. 47 to NPF-69 2.
Safety Evaluation cc w/enclosures:
See next page Distribution:
See attached sheet Original signed by:
John E. Henning, Project Manager Project Directorate I-1 Division of Reactor Projects
.I/II Office of Nuclear Reactor Regulation
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