ML20244D156
| ML20244D156 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 01/11/1985 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20113E106 | List: |
| References | |
| TAC-56881, NUDOCS 8501230316 | |
| Download: ML20244D156 (5) | |
Text
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t ENCIIEURE 2 NRC D00GT 50-321 OPERATING LIGNSE DPR EININ 1. HMQi NUCIEAR PIANT INIT 1 PROPOSED CHANGE TO TE3NICAL SPECIFICATICRE The proposed change to 'nx:hnical-Specifications (Appendix A to Operating.-
License DPR-57) wtuld be incorporated as follows:
Remme Page Insert Page 1.0-7
- 1. 0-7 3.5-18
'3.5-18 1
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F..L. wunal System Availability (contitued).
Specification 3.6.
states the reallraments for the presaare relief furetion of the valves.
It is possible for any rumber of-the values assigned to the ADS to be incapable of performing their ADS functions beca2se of instrumentation failures yet be fully cgable of performirg
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their pressare relief function.
Beca3se the mitomatic depresa2rization syste does not provide makeup
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to the reactor. primary vessel, no credit is.taken for the steam coolirg of the core caused by the system actuation, to provide further conservatism to the Core Standby coolire Systens.
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2.
Operation with Inoperable maponents With one ADS valve known to be incapable of matomatic operation, six 1
valves remain operable to perform their ADS function.. Howeser, since-the BOCS Ioss. of 0)olant Accident analysis for small line breaks asaamed that all seven ADS valves were. operable, reactor. operation with one ADS valve inoperable is only allowed to contiue for seien (7) days provided that the HPCI system is demonstrated to be operable and that the actuation logic for the (remaining) six ADS. valtes is demonstrated to be operable, i
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G.
Mininum Cbre and Containment (boling Systens Availability
%e pirpose of this ' Specification is to asaire that adentate. core l
cooling egipnent is available at all times. If, for exanple, one core j
spray loop were cut of service and the diesel which powered the j
opposite core spray loop were out of service, only 2 RHR-pumps would be available.
Specification 3.9 sust also - be consulted to. determine other reasirements for the diesel generators.
%is Specification establishes conditions for the performance of major maintenance, a2ch as-draining of the. mappression
- pool, he availability of the stutdown cooling aaboystem of-the RER system and the RHR service water system enmate ' adegante supplies of reactor cooling and emergency makaip water when.the reactor; is 'in thef Cold Shutdown condition.
In addition this specification provides,.that,-
should major maintenance be performed, no work will be performed'which
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could lead to draining the water fttun the reactor vessel.
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MM. Mininum Critical Ptmer Ratio (MCPR) - Mininum Critical Power Ratio (EPR) is the value of the critical power ratio aWociated with the most limitig assembly in the reactor core.
Critical Power. Ratio (CPR)
-l is the ratio of that power in a fuel assetbly, which.is calculated to a
cease some point.in the assembl.y to experience boiling transition, to I
the actual assembly operating power NN. Trip System - A trip system means an arrangement of instrument channel trip signals and auxiliary emipment remired to. initiate action to accouplish a protective function.
A trip system may. remire one or more instrument channel trip signals related to one or more' plant
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parameters in order to initiate trip system action.
Initiation of j
protective action may remire the tripping of a single trip system or i
the coincident tripping of two trip systems l
l 00.
(Deleted) i PP. Fire Rippression Water System - A Fire Suppression Water System shall consist of: water storage tanks, punps, and distribution piping with associated sectionalizing control or isolation valtes.
Such valtes include yard hydrant curb valves, and the first valve ahead of the l
water flow alarm device on each sprinkler, hose stand pipe or spray
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system riser.
QQ. Channel Calibration - A 01armel Calibration is the adju stment, as necessary, of the channel ou tput asch that it responds with the i
5 necessary range and accuracy to known values of the parameter which the channel monitors.
%e Channel Calibration shall enempass the-entire channel including the sensor ard alarm and/or trip functions, and shall irclude the O)annel Ranctional Test.
%e Omnnel Calibration may be i
performed by any series of secuential, overlapping or total channel I
steps such that the entire channel is calibrated. '
RR.
Oiannel Rictional Test - A Channel Ranctional Test shall be:
a.
Analog Qiannels - the injection of a sinulated signal into the a
channel as close to the primary sensor as practicable to verify I
operability including alarm and/or trip functions.
l b.
Bistable Omnnels - the injection of a simulated signal into the.
channel sensor to verify operability including alarm and/or trip 1
furetions.
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SS. Fraction of Limiting Power Density (IUD) -the ratio of the linear heat -
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y generation rate (IJGR) existing at a given lowcation to the design IBGR j
for the kundle type.
Design IRGRs are 18.5 m/ft for.7x7 tundles and 13.4 m/ft for 8x8 tundles.
1 TT. Core Maxinum Fraction of Limiting Power Density (OfLPD) - the. OFLPD l
is the highest value existing in the core of the FLPD.
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s ENCLOSURE 3 SALP EVALUATION Licensing Evaluations 1.
Analysis With regard to the licensee's request for miscellaneous revisions to
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Technical Specifications (TS) submitted to NRC in a letter dated January 11
-l 1985, the overall performance - related to this request was considered j
adequate.
The licensee's resolution to the issue involved in the _ request was considered adequate.
Changes to the TS regarding administrative issues demonstrated management involvement.
1 2.
Conclusion Approach to Resolution of Issues - Category 2 Management Involvment - Category 2 l
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a