ML20246D454
| ML20246D454 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/22/1989 |
| From: | Hairston W GEORGIA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20246D457 | List: |
| References | |
| HL-676, NUDOCS 8908280104 | |
| Download: ML20246D454 (3) | |
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' August 22, 1989 j
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.U.S. Nuclear Regulatory Commission
. ATTN: 1 Document Control Desk Hashington, D.C.
20555 1
j PLANT HATCH - UNITS 1 2
NRC DOCKETS 50-321,
-366 OPERATING LICENSES DPR-d/, NPF-5
. REQUEST TO REVISE REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS i
- 1 Gentlemen:
l l,
By 1etter' dated March' 27, 1986, Georgia Power Company (GPC). proposed p
changes to. Plant Hatch Reactor Protection System (RPS) instrumentation surveillance. requirements in the Unit 1
and Unit 2
Technical Specifications (TS).
On June 6,'1989 the NRC approved these changes as
' Amendment.163 (Unit 1)'and 100 (Unit 2).
Our submittal contained minor-
. inconsistencies, which are described in Enclosure 1.
Per your request, we are resubmitting ' corrected TS changes.
The basis for change request and 10 CFR 50.92 evaluation provided in our March 27, 1986 submittal are
' applicable to'these' changes.
'To' allow time for procedure revisions and orderly incorporation into
.)
1 copies 'of 'the Technical Specifications, GPC requests the proposed amendment, once approved by the NRC, be issued with an effective date to be no later than 60 days from the date of issuance of the amendment.
'In accordance with the requirements of 10 CFR 50.91,-a copy of this I
letter and all-applicable enclosures will be sent to Mr. J. L. Ledbetter 1
of. the Environmental Protection Division of the Georgia Department of Natural Resources.
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l-8908280104 890822 PDR-ADOCK 05000321 i
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- U.S. Nuclear Regulatory Commission August 22s~1989-1
- Page Two.,
Mr. W. G. ' Hairston, III states that he is duly authorized -to execute l
this oath on _ behalf of Georgia Power Company, and to the best of his knowledge and belief the facts set forth in this letter are true.
By:
b H. G. Hairston, III l-Sworn'to and subscribed before me this cU day of d uon M
, 1989.
I
~ h a dwwt N cIr[
e6tary Public
{yhWl0N DPRES DEC.15,1992
- GKM/et'
Enclosures:
1.
Request to Revise Reactor Protection System (RPS)
Instrumentation Surveillance Requirements 2.
Request to_ Revise lechnical' Specifications Page Change Requests
- c: Georaia Power Comoany Mr. H. C. Nix, General Manager - Nuclear Plant Mr. J. D. Heidt, Manager Engineering and Licensing - Hatch GO-NORMS U.S. Nuclear Reaulatory Conmission. Washinoton. D.C.
Mr. L. P. Crocker, Licensing Project Manager - Hatch U.S. Nuclear Reaulatory Commission. Reaion II Mr. S. D. Ebneter, Regional Administrator Mr. J. E. Menning, Senior Resident Inspector - Hatch State Of Georola Mr. J. L. Ledbetter, Commissioner - Department of Natural Resources 4358N
ENCLOSURE 1 1
PLANT HATCH - UNITS 1, 2 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 REQUEST TO REVISE REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS This enclosure describes the minor. changes --being proposed to our March 27, 1986 Technical Specification (TS) submittal. The submittal was.
-approved _ by the NRC on ~ June 6.1989 as Amendment 163 -(Unit.1) and 100 (Unit 2).
Our submittal proposed several changes to the Unit 1 RPS and control rod block surveillance requirements to make them consistent with the Unit 2 Standard Techt,1 cal Specification (STS) format.
Unit 1 Table 4.2-7,
" Check, Functional Test, and Calibration Minimum Frequency for Neutron Monitoring ' Instrumentation Hhich Initiates Control Rod Blocks" was.
replaced with a new table based on Unit 2 and STS requirements and formats.
Channel functional test (FT) frequencies on the Average Power Range Monitor (APRM) and Rod Block Monitor (RBM) instrumentation (except APRM downscale) were relaxed from monthly to quarterly.
The relaxations in FT frequency were-justified for both units on Proposed Change 2 of our March 27, 1986 submittal; however, the corresponding Unit 2 Table 4.3.5-1 was never submitted.
Also, note "h" was inadvertently added to. the Main Steam Isolation Valve (MSIV) closure channel calibration frequency _in.
Unit 2 lable 4.3.1-1.
The note only applies -to the scram discharge volume water level-high calibration frequency.
The Basis for Change Request and 10 CFR 50.92 evaluation contained in our March 27, 1986 submittal are applicable for these changes.
4358N HL-676 El-1
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