ML20081F341
| ML20081F341 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 03/10/1995 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20081F338 | List: |
| References | |
| GL-93-05, GL-93-5, NUDOCS 9503220094 | |
| Download: ML20081F341 (4) | |
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-st UNITED STATES i U.
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E NUCLEAR REGULATORY COMMISSION 5MY i!
WASHINGTON. D.C. 3088H001
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j SAFETY EVALUATION BY THE OFFICE OF NUCLEAR PEACTOR REGULATION j
RELATED TO AMENDMENT NOS.116 AND 109 TO FACILITY OPERATING LICENSE NOS. DPR-42 AND DPR-60 NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT NOS. 1 AND 2 DOCKET NOS. 50-282 AND 50-306
1.0 INTRODUCTION
By letter dated August 30, 1994, the Northern States Power Company (the licensee) submitted a request for change to the Technical Specifications (TS) appended to Facility Operating License Nos. DPR-42 and DPR-60 for the Prairie Island Nuclear Generating Plant, Unit Nos. I and 2.
Specifically, the request would revise TS Section Table 4.1-1C, " Miscellaneous Instrumentation Surveillance Daouirements," TS Table 4.1-2A, " Minimum Frequencies for Equipment le h," TS 4.3, " Primary Coolant System Pressure Isolation Valves,"
and TSs 4. 4.1, 4. 4.1. a, 4.4.1. b, 4. 4. I. b.1, 4.4. I.b.2, and 4.4. I. b.3,
" Electrical Hydrogen Recombiners," TS 4.5.A.2.b, " Containment Spray System,"
TSs 4.8. A.1, 4.8. A.2, and Footnote, " Auxiliary Feedwater System," and Bases 4.8, " Steam and Power Conversion Systems." These revisions would implement recommended changes from Generic Letter (GL) 93-05, "Line-Item Technical
'pecification Improvements to Reduce Surveillance Requirements for Testing during Power Operation." Specifically, the amendments would implement TS f
changes corresponding to the following GL 93-05 line numbers: 7.4, 4.2, 6.1, 8.5, 8.), and 9.1.
2.0 BACKGROUND
NUREG-1366, " Improvements to Technical Specification Surveillance Requirements," December 1992, reported the TS line-item improvements that were identified by the NRC staff. The TS improvements were based on an NRC study of surveillance requirements (SRs) and included information provided by licensee personnel that plan, manage, and perform surveillances. The study i
included insights from a qualitative risk assessment of SRs bases on the standard TS for Westinghouse plants and the TS for the Edwin I. Hatch Nuclear Plant, Unit 2.
The staff examined operational data from licensee events reports, the nuclear plant reliability data syster (NPRDS), and other sources to assess the effect of TS SRs on plant operation. The staff evaluated the effect of longer surveillance intervals to reduce the possibility for plant transients, wear on equipment, personnel radiation exposure, and burden on i
personnel resources.
Finally, the staff considered surveillance activities for which the safety benefits are small and not justified when compared to the effects of these activities on the safety of personnel and the plant. The NRC 950322o094 950310 DR ADOCK 0500 2
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,. y i i staff. issued guidance on the proposed TS changes to all holders of operating l
licenses or construction permits for nuclear power reactors in GL 93-05, September 27, 1993.-
3.0 EVALUATION l
l' The staff has evaluated the licensee's proposed TS SR modifications as described below:
Table 4.1-1C. " Miscellaneous Instrumentation Surveillance Requirements."
i Delete Item 14, "occumulator Level and Pressure" and corresponding frequency interval designations and place them into the Itcensee-controlled test procedures.
This TS modification implements GL 93-05, Item 7.4, Accumulator Water Level and Pressure Channel Surveillance Requirements (PWR) and is consistent with industry recognition that' accumulator instrumentation operability is not directly related to the capability of the accumulators to perform their safety function.
l Table 4.1-2A, " Minimum Frequencies For Equipment Tests." Revise the-frequency for partial movement of all control rod assemblies from every 2 weeks to once per quarter.
I This TS modification implements GL 93-05, Item 4.2, Control Rod Movement i
Test.
r TS SR 4.3, " Primary Coolant System Pressure Isolation Valves." Under l
Specification heading, extend the amount of time the plant can be' shut down before pressure isolation valve (PIV) testing will be required from j
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 7 days.
l This TS modification-implements GL 93-05, Item 6.1, Reactor Coolant System.
Isolation Valves (PWR).
i TS SRs 4.4.I, 4.4 I.a, 4.4.I.b, 4.4.I.b.1, 4.4.I.b.2, and 4.4.I.b.3,
" Electrical Hydrogen Recombiners." Revise the containment hydrogen recombiner testing surveillance frequency from every 6 months to every i
refueling interval. Delete the specific requirement to perform CHANNEL CALIBRATION of recombiner instruments and control circuits and relocate to licensee-controlled procedures. Delete the requirement to sequentially perform the resistance to ground test following the function test. This latter requirement has no technical basis and is unnecessarily restrictive.
Its removal would bring the TS into conformance with the Standard TS.
r This TS modification implements GL 93-05, Item 8.5, Hydrogen Recombiner (PWR,BWR).
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' I TS SR 4.5.A.2.b, " Containment Spray System." Revise the containment spray.'
systes nozzle testing surveillance frequency from once every 5 years.to once every 10 years.
~This TS modification' implements GL 93-05, Item 8.1, Containment Spray.
System (PWR).
TS SR 4.8.A.1, 4.8.A.2, and Footnote, " Auxiliary.Feedwater System."
Revise the testing frequency for the auxiliary feedwater pumps.from intervals of 1 month to semi-quarterly on' a STAGGERED TEST BASIS.
'This TS modification implements GL 93-05, Item 9.1, Auxiliary Feedwater Pump and System Testing (PWR).
TS Bases 4.8, " Steam and Power Conversion Systems." Revise the Bases to include testir.,, frequency for the auxiliary feedwater pumps from intervals of 1 month to semi-quarterly on a STAGGERED TEST BASIS. This is an administrative enange to bring the Bases into conformance with~the TS.
The proposed TS modifications are consistent with the guidance provided in GL 93-05.
This guidance is based on the NRC staff findings and recommendations stated in NUREG-1366. NUREG-1366. recognized that testing is important to periodically verify that systems, structures, and components are available to perform their safety functions. Testing is especially critical to reveal degradation and failures that occur while equipment is in standby mode. The study did find that, while most testing at power is important, safety can be improved, equipment degradation decreased, and an unnecessary burden on' personnel resources eliminated by reducing the amount of testing that TS required during power operation..However, only a small fraction of the TS. surveillance intervals warranted relaxation.
In addition, the licensee stated that the. proposed-TS changes are compatible with plant operating experience. The staff concludes that the proposed TS changes do not adversely affect ~ plant safety and will result in a net benefit to the safe operation of the facility, and, therefore, are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Minnesota State official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change surveillance requirements. Tb NRC staff has determined that the amendments involve 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 amendments involve no significant hazards consideration and there has been no public comment on such finding
.(60 FR 6305). Accordingly, the amendments meet the eligibility criteria for
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-.a. 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 amendments.
6.0 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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
H. Abelson, SRXB Date: March 10,1995 4
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