ML19225C250
| ML19225C250 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 07/19/1979 |
| From: | Whitmer C GEORGIA POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19225C251 | List: |
| References | |
| NUDOCS 7907260746 | |
| Download: ML19225C250 (3) | |
Text
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Chas. f. Whitmer v.c e rc.
July 19, 1979 s
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Director of Nuclear Reactor Regulation U.
S. Muclear Regulatory Commission Washington, D.
C.
20555 NRC DOCKETS 50-366 OPERATING LICE::SE NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 PROPOSED CHANGES TO TECHNICAL SPECIFICATI0::S Centlemen:
Pursuant to 10 CFR 50.90 as required by 10 CFR 50.59(c)(1), Georgia Power Company hereby pronoses an amendment to the Plant Hatch Unit 2 Technical Specifications (Appendix A to the Operating License).
The first proposed change corrects the Surveillance Requirements for the diesel geacrator by changing the rating of the rejected load from 1070 kw to 798 kw in Section 4.8.1.1.2.C.3.
This change is due to the previous inadvertent substitution of horsepower for the kilowatt rating.
The design basis of this system is to maintain 4160 volts on the essential bus when a large load is tripped off line; the case of an RHR pump being tripped uns used ir the analysis performed and used as the basis of the existing Technical Specifications.
The RHR pumps have a rating of 1070 hp which corresponds to 798 kw.
Table 3.3.6.2-1 contains the seismic nonitoring instrumentation and two of the instruments listed in the table contain the wrong m'L numbers (system identification code).
This proposed change corrects the >TL numbers only; no other changes to the table are proposed.
The Plant ' Review Board and Safety Review Board have reviewed and approved these proposed changes to the Plant Hatch Unit 2 Technical Speci-fications and have determined that they do not constitute an unreviewed safety question.
The probability of occurrence or the consequences of an accident or calfunction of equipment important to safety is not increased nor is the possibility for failures of a different type not previously considered introduced, since the proposed change corrects editorial errors which were incorrectly transcribed during pre-operational testing.
Because no change in analysis has been made, the cargins of safety as established by the bases for the lechnical Specifications have not been reduced.
The final proposed change alters paragraph 4.3.6.2.2 in the Unit 2 Technical Specifications which states that a channel calibration will be perforced within 5 days of a seismic event.
Kinenetrics, Inc., the vendor who calibrates our instruments has indicated to us that they cannot do the calibration in 5 days; therefore, the Georgia Power Company proposes changing the 5 day requirement to 30 days.
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Georgia Power d Director of Nuclear Reactor Regulation l'
S. Nuclear Regulatory Commission July 19, 1979 Page Two The Plant Review Board and the Safety Revice Board have reviewed and approved this proposed change to the Technical Specifications and have determined that it does not constitute an unreviewed safety question. The probability of occurrence or the consequences of an accident are not increased because the operabillej of the seismic instruments can be maintained until the channel calibrotion is performed, since the instruments are required to be restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of a seismic event.
The possibility of an accident or malfunction of a different type not previously considered is not introduced because the seismic instrumentation does not interface with any safety related functions of the plant.
The margins of safety established by the basis for this specification have not been reduced because the function and operability limits remain unchanged.
Yours very truly, p
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-Sw9rn to and subscribed before me this 19th day of July, 1979.
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