ML17353A427
| ML17353A427 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 10/17/1995 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17353A426 | List: |
| References | |
| GL-93-05, GL-93-5, NUDOCS 9510240396 | |
| Download: ML17353A427 (4) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY E ALUA ION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.
177 TO FACILITY OPERATING LICENSE NO.
DPR-31 AND AMENDMENT NO. 171 TO FACILITY OPE TING LICENSE NO.
DPR-41 FLORIDA POWER AND LIGHT COMP NY TURKE POINT UNIT NOS.
3 AND 4 DOCKET NOS.
50-250 AND 50-251
- 1. 0 INTRODUCTION By letter dated July 26, 1995, Florida Power and Light Company (FPL or the licensee) proposed a change to the Technical Specifications (TS) for Turkey Point Units 3 and 4.
The changes requested implement selected recommended changes from Generic Letter (GL) 93-05, "Line-Item Technical Specification Improvements to Reduce Surveillance Requirements for Testing During Power Operation."
Specifically, the amendments would implement TS changes corresponding to the following GL 93-05 line numbers:
4.2; 5.4, 5.14, 6.1, and 12.
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 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 Pl'ant, Unit 2.
The staff examined operational data from licensee events
- reports, the nuclear plant reliability data system (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 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 staff issued guidance on the proposed TS changes to all holders of operating licenses or construction permits for nuclear power reactors in GL 93-05, September 27, 1993.
95i0240396 952017 PDR ADOCK 05000250 P
- 3. 0 EVALUATION The staff has evaluated the licensee's proposed TS SR modifications as described below:
(1)
TS SR 4.1.3.1.2:
Change the frequency interval for control rod movement test from monthly to quarterly.
This TS modification implements GL 93-05, Item 4.2, Control Rod Movement Test.
(2)
TS SR 4.6.5.1:
Change the hydrogen monitor calibration,from quarterly to each refueling interval, and the analog channel operational test from monthly to quarter ly.
This TS modification implements GL 93-05, Item 5.4, Hydrogen Monitor Surveillance.
(3)
TS SR Table 4.3-3:
Change the analog channel functional test from monthly to quarterly for radiation monitors.
Correct spelling of
'Radioactivity'n Item l.a.
This TS modification implements GL 93-05, Item 5. 14, Radiation Monitors.
The correction to the word 'Radioactivity'n Table 4.3-3 item l.a. is administrative and is, therefore, acceptable.
(4)
TS SR 4.4.6.2.2:
Increase the time allowed in COLD SHUTDOWN before leak testing the Reactor Coolant System (RCS) isolation valves is required, from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to ~7da s.
This TS modification implements GL 93-05, Item 6. 1, Reactor Coolant System Isolation Valves (PWR).
(5)
TS SR 4. 10. 1.2:
Changes the requirement for a rod drop test prior to reducing SHUTDOWN MARGIN from "within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />" to "within ~7 da s."
This TS modification implements GL 93-05, Item 12, Suspending Shutdown Margin Requirements.
The proposed TS modifications are consistent with the GL 93-05.
GL 93-05 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 found 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, are in accordance with GL 93-05, and, therefore, are acceptable.
- 4. 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.
5.0 STATE CONSULTATION
Based upon the written notice of the proposed amendments, the Florida State official had no comments.
- 6. 0 ENVIRONMENTAL CONSIDERATION These amendments involve a change in the surveillance requirements.
The 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 47617).
Accordingly, these amendments meet 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 amendments.
Principal Contributor:
R. Croteau pate.
October 17, 1995