ML19289C653
| ML19289C653 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 01/18/1979 |
| From: | Whitmer C GEORGIA POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7901220063 | |
| Download: ML19289C653 (8) | |
Text
c,mrr;a p%.., rj,nany no e, om,. w..:
Prf,t(/' A lbs M
Afl.sf d.t. (W/@ s G TOl Icir(hcre 404 $ N 6 % Q January 18, 1979 h
Georgia Power Chas. F. Whitma, yme p.e5 are Er'atvorov)
I'" " "'""'
- I'"
Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN 1. HATCH PLANT UNITS 1, 2 TECHNICAL SPECIFICATION: RPS LOW VOLTAGE TRIP Gentlemen:
The August 7, 1978, letter from the Operating Reactors Branch # 3, Division of Operating Reactors, U. S. Nuclear Regulatory Commission transmitted an Order for Modification of License and a related exemption which required the implementation of certain surveillance for the Reactor Protection System (RPS) power supply equipment of Plant Hatch Unit 1.
Similar surveillance requirements and a similar exemption were issued as a condition to the Unit 2 operating license.
One section of that required surveillance, subparagraph 4.9.D.b.2 of Unit l's Technical Specifications (subparagraph 4.8.2.1.2.b.2 of Unit 2's), specified the verification of the under-voltage protective instrumentation setpoint equal to or greater than 108 VAC (96 VAC for Unit 2).
This surveillance was implemented as an interim procedure until the ordered upgrading of the existing breakers could be accomplished.
The setpoints cited by the Modification of License for Unit 1 (108 VAC) and by the license condition for Unit 2 (96 VAC) do not reflect the physical characteristics of the installed breakers and are in error.
The correct value for these setpoints is 36 VAC for both Unit 1 and 2 during the interim period.
The breakers, as designed and installed, do not have the capability of providing a 108 VAC or 96 VAC trip and thus the requested changes are required to comply with the ordered surveillance.
Therefore, pursuant to 10 CFR 50.90, as required by 10 CFR 50.59 (c)(1), Georgia Power Company hereby proposes an amendment to the Technical Specifications (Appendix A to the respective operating licenses) for Plant Hatch Units 1, 2.
The proposed change will correct the value specified for the under-voltage trip setpoint for the RPS motor generator output circuit breakers as cited by the Order for Modification of License DPR-57 and by Operating License NPF-5.
The Plant Review Bcard and the Safety Review Board have reviewed and approved the proposed change to the Unit l's and Unit 2's Technical Specifications and have determined that they do not involve an unreviewed safety question and that the probability of occurrence or the consequences of an accident or o.alfunct' ion of equipment important to safety is not increased nor is the possibility of a new accident or malfunction of equipment important to safety created.
790122OC63 j
Georgia Power d Director of Nuclear Reactor Regulation January 18, 1979 Page 2 Enclosed with the proposed changes are instructions for the incorpora-tion of the proposed revision into the Technical Specifications, and an evaluation of the fee required under 10 CFR 170.12.
It should be noted that while a check for the amount due for a Class III and Class I rimultaneous two unit submittal is enclosed for the expedient processing of this request, it is the opinion of the applicant that this change falls under footnote 2 to the table of facility license amendment fees schedule, 10 CFR 170.22 in that it is a correction to Technical Specifications ordered by the Commission under 10 CFR 2.204.
It ic expected, therefore, that the fee will be refunded after review by the License Fee Management Branch of the NRC.
Yours very truly, 1
s
'Chas. F. Whitmer WEB /mb Enclosure Sworn to and subscribed bcfore me this 18th day of January,1979.
p S
E
.il eI
~/
Notary ruwe++
N
/
commaim Lyud W ~otym1Public Ms xe:
Mr. Ruble A. Thomas George F. Trowbridge, Esquire
LIMITING CONDITIONS FOR OPERATION SURVilLLANCE REQUIREMENTS 3.9.0 Reactor Protection System MG 4.9.D, Reactor Protection System MG Sets Sets Applicatiility Applicability The limiting conditions for operation apply The surveillance requirements a-bly to to the reactor protection system instru-the periodic testing requirene.ts of mentation.
the reactor protection system instru-mentation.
Objective:
Objective :
The objective of the limiting condition The objective of the surveillance require-of operation is to assure that failure of the ments is to verify that the RPS instrumen-motor-generator set voltage regulating tation MG sets are within their normal circuitry will not result in damage to range to preclude sustained over-voltage the reactor protection system components or under-voltage conditions that might with an attendant potential loss of compromise the capability of the RPS from capacity to scram the plant.
performing its intended safety function.
Specifications:
Specifications If in service the RPS instrumentation MG The specified RPS instrumentation MG set lA and/or 1B voltage will be within sets lA and 1B shall be determined the range of 108 to 132 VAC.
operable:
1.
With RPS instrumentation MG set lA a.
At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> by verifying:
and/or 1B voltage outside the range of 108 to 132 VAC, demonstrate the OPERABILITY 1.
RPS instrumentation MG sets l A and of all equipment which could have been 1B voltage to be between 108 and subjected to the abnormal voltage for 132 VAC, and all Class IE loads connected to the associated bus (es) by performance of a 2.
No unexplained chnage in RPS CHANNEL FUNCTIONAL TEST, as required, MG set lA and/or IB current within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
and voltage in excess of 5%
from its nominal value.
2.
With RPS instrumentation MG set lA and/or IB inoperable, restore the inoperable
.b.
At least once per 6 months and prior MG set (s) to OPERABLE status within 30 to resetting the Reactor Protection minutes or remove the inoperable l'G System trips following a seismic set (s) from service.
event of Operational Basis Earth-quake intensity, by demonstrating the OPERABILITY of RPS instrumenta-l tion MG set lA and IB over-voltage, under-voltage and under-frequency protective instrumentation by per-formance of a CHANNEL CALIBRATION l
including simulated automatic actuation of the protective relays, tripping logic and output circuit breakers and verifying the follow-ing setpoints:
1.
Over-voltage < 132 VAC, 2.
Under-voltage > 36 VAC, and 3.
Under-frequency > 57 Hz.
3.9-6a
9 ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS 4.8.2.1.1 The above required A.C. distribution system buses and inverters shall be determined OPERABLE:
a.
At least once per 7 days by verifying correct breaker alignment and indicated power availability, and b.
At least once per 31 days by determining that the 250 volt DC/600 volt AC inverters 2R44-5002 and 2R44-S003 are OPERABLE by verify-ing inverter output voltage of 600 volts + 5% while supplying their respective buses.
- 4. 8. 2.1. 2 The above specified RPS instrumentation MG sets 2A and 28 shall be determined OPERABLE:
a.
At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> by verifying; 1.
RPS instrumentation MG sets 2A and 2B voltage to be between 108 and 132 VAC, and 2.
No unexplained change in RPS instrumentation MG set 2A and/or 2B current in excess of 5% from the value observed during the Startup Test Program.
b.
At least once per 6 months and prior to resetting the Reactor Protection System trips following a seismic event of Operational Basis Earthquake intensity, by demonstrating the OPERABILITY of RPS instrumentation MG set 2A and 2B over-voltage, under-voltage and under-frequency protective instrumentation by performance of a CHANNEL CALIBRATION including simulated automatic actuation of the protective relays, tripping logic and output circuit breakers and verifying the following setpoints.
1.
Over-voltage < 132 VAC, 2.
Under-voltage > 36 VAC, and 3.
Under-frequency > 57 Hz.
HATCH - UNIT 2 3/4 8-11
ELECTRICAL POWER SYSTEMS A.C. DISTRIBUTION - SHUTDOWN
')
~
LIMITING CONDITION FOR OPERATICN 3.8.2.2 As a minimum, the following A.C. distribution system buses, inverters and motor-generator (MG) sett, shall be OPERABLE:
a.
Two 4160 volt Essential Buses, 2E, 2F and/or 2G, b.
One 600 volt Essential Bus, 2C or 21, c.
One 120/208 volt Essential Cabinet, 2A or 28, d.
One 120/208 volt Instrument Bus, 2A or 2B, e.
A.C. inverters 2R44-S002 and 2R44-5003*, and f.
If in service, Reactor Protection System instrumentation MG sets 2A and 28.
APPLICABILITY:
CONDITIONS 4 and 5.
ACTION:
a.
With less than the above required A.C. distribution system buses and inverters OPERABLE, suspend all operatione. involving CORE ALTERATIONS, irradiated fuel handling, positi'<
eactivity changes or operations that have the potential of ci 'ning the reactor vessel.
The provisions of Specification 3.0.3 are not applicable.
b.
With RPS instrumentation MG set 2A and/or 2B voltage outside the range of 108 to 132 VAC, demonstrate the OPERABILITY of all equipment which could have been subjected to the abnormal voltage for all Class IE loads connected to the associated bus (es) by performance of a CHANNEL FUNCTIONAL TEST or CHANNEL CALIBRATION, as required, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c.
With RPS instrumentation MG set 2A and/or 2B inoperable, restore the inoperable MG set (s) to OPERABLE status within 30 minutes or remove the inoperable MG set (s) from service.
SURVEILLANCE REQUIREMENTS 4.8.2.2 At least the above required A.C. distribution system buses, inverters and MG sets shall be determined OPERABLE per Specifications 4.8.2.1.1 and 4.8.2.1.2.
)
HATCH - UNIT 2 3/4 8-12
ATTACIIMENT 1 NRC DOCKETS 50-321, 50-366 OPERATING LICENSE DPR-57, NPF-5 EDWIN I. IIATCll NUCLEAR PLANT UNIT 1, 2 PROPOSED CllANCES TO TECllNICAL SPECIFICATIONS Pursuant to 10 CFR 170.12(c), Georgia Power Company has evaluated the attached proposed amendment to Operating License DPR-57 and NPF-5 and have determined that:
a)
The proposed amendment does not require the evaluation of a new Safety Analysis Report or rewrite of the facility license; b)
The proposed amendment does not contain several complex issues, does not involve ACRS review, or does not require an environmental impact statement; c)
The proposed amandment does not involve a complex issue, an environ-mental issue or more than one safety issue; d)
The proposed amendment does involve' a single issue; namely the correc-tion of an incorrect value contained in Technical Specifications originated by the NRC; c)
The proposed amendment is duplicated for Unit 2 which is essentially an identical unit at the same site for processing with that of Unit 1; f)
The proposed amendments are therefore a Class III and Class I for Units 1 and 2, respectively; g)
The footnote Number 2 of 10 CFR 170.22 applies since this is a correction to Commission Orders issued pursuant to 10 CFR 2.204 and is requested to correct and clarify those orders.
No fee is required.
ATTACHMENT 2 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. IIATCil NUCLEAR PLANT UNIT 1 PROPOSED CllANCE TO TECHNICAL SPECIFICATIONS The proposed change to Technical Specifications (Appendix A to Operating License DPR-57) would be incorporated as follows:
Remove Page Insert Page 3.9-6a 3.9-6a e
G V
ATTAC11 MENT 3 NRC DOCKET 50-366 OI'ERATING LICENSE NPF-5 EDWIN I. IIATCII NUCLEAR PLANT UNIT 2 PROPOSED Cl!ANGE TO TECHNICAL SPECIFICATION j
The proposed change to Technical Specifications (Appendix A to Operating License NPF-5) would be incorporated as follows:
Remove Page Insert Page 3/4 8-11, 12 3/4 8-11, 12 G
9 k
v