ML19254D919
| ML19254D919 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 10/19/1979 |
| From: | Kelly R GEORGIA POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7910300316 | |
| Download: ML19254D919 (6) | |
Text
Georgia Power Company 230 Peachtree Street Post C?tce Scx 4545 Atlanta. Gooria 30302 Te!ephone 404 522 6060 October 19, 1979 R. J. Kelly GCOfoia Power vice Presicent and Generai Manager b
Power Generat on f 9 nf 9,7, g,..g g.y 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 I. HATCH NUCLEAR PLANT UNITS 1, 2 COMMITMENTS REGARDING THE SHORT-TERM RECOMMENDATIOSS OF TMI-2 LESSONS LEARNED TASK FORCE Gentlemen:
On September 24, 1979 Georgia Power Company received the U. S. Nuclear Regulatory Commission's request for our commitment to meet the requirements cited by NUREG-0578 and the staff's Emergency Preparedness Studies. Those requirements have been the subject of an extensive review on the part of Georgia Power Company, its consultants, and the nuclear industry since their issuance. We hereby submit, pursuant to your request, our commitment to the implementation of those requirements as described in Attachment 1 of this letter.
Georgia Power Company is proceeding to implement those actions which are applicable to Plant Hatch on the schedule specified by Enclosures 6 and 8 of your letter of September 13, 1979, as permitted by existing technology and restraints. The criteria by which many of the requested actions are to be achieved have not been clearly identified. Georgia Power Company is working with the BWR Owner's Group to develop suitable implementation criteria. Certain of these criteria have been developed, and were submitted to the NRC by the BWR C.:ner's Group on October 17, 1979. The remaining criteria are scheduled to be submitted on November 15, 1979. Georgia Power Company expects to utilize these criteria to implement the required actioni as oatlined in Attachment 1. to this letter provides additional plant specific information concerning the capabilities for high point venting which was requested by the NRC during the recent topical meetings of Jctober 10 through 12.
It is anticipated that further correspondence may be required for amplifi-cation or clarification of these matters.
Should you have any questions or comments on our efforts in this regard, please contact this office.
Yours very truly, R. J. Kell-;
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l Attachments xc:
Mr. Ruble A. Thomas 39.-
George F. Trowbridge, Esquire i
R. F. Rogers, III 70103003
a ATTACHMENT 1 NEAR TERM REQUIREMENTS OF NUREG-0578
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2.1.1 Emergency Power Supply Georgia Power Company concurs with the BWR Owner's Group implementa-tion criteria.
2.1.2 Relief and Safety Valve Test Georgia Power Company concurs with the BWR Owner's Group implementa-tion criteria.
2.1.3.A Direct Position Indication of Relief and Safety Valves for PWR's and BWR's Plant Hatch Units 1 and 2 presently utilize valve position indication systems similar to that described in the BWR Owner's Group Implementa-tion criteria. A design review of the systems are currently being conducted.
If the design of the systems do not meet the implementa-tion criteria, the systems will either be modified or justification for not modifying the system will be provided.
2.1.3.8 Instrumentation For Inadeauate Core Cooling Georgia Power Company concurs with the BWR Owner's Group implementa-tion criteria and will resolve this request accordingly.
2.1.4 Containment Isolatio-Georgia Power Company concurs with the BWR Owner's Group implementa-tion criteria and will resolve this request accordingly.
2.1.5.A Dedicated Hp Control Penetrations Georgia Power Company has reviewed the desic. of the penetrations for the Hatch Unit 1 purge system and the Hatch Unit 2 Hydrogen Recombiner System and concludes that it meets the staff positions contained in NUREG-0578.
2.1.5.C Recombiners Plant Hatch Unit 1 does not utilize hydrogen recombiners; therefe.~e, this concern is not applicable to Unit 1. Unit 2 utilizes permantntly installed redundant hydrogen recombiners that are remotely operated from the control room; therefore, the concern for shielding is not applicable. A review of the procedures for using the Unit 2 hydrogen recombiners will be made.
2.1.6.A Integrity of Systems Outside Containment Likely to Contain Radioactive Materials The BWR Owner's Group Implementation Criteria for this item will be submitted to the NRC by November 15, 1979. A leak reduction program and preventive maintenance program are currently being developed for Plant Hatch.
ATTACHMENT 1 (Continued)
NEAR TERM REQUIREMENTS OF NUREG-0578 2.1.6.B Design Review of Plant Shielding The BWR Owner's Group Implementation Criteria for this item will be submitted to the NRC by November 15, 1979. A shielding design review is currently being conducted.
2.1.7.A Auto Initiation of the Auxiliary Feedwater System (AP45)
This item is not applicable to BWR.
2.1.7.B Auxiliary Feedwater Flow Indication to Steam Generators This item is not applicable to BWR.
2.1.8.A Post Accident Sampling Capability The BWR Owner's Group Implementation Criteria for this item will be submitted to the NRC by November 15, 1979. A design review of post accident sampling capability is currently being conducted.
2.1.8.B Interim Procedures for Ouantifying Hich Level Accidental Radioactivity Releases Georgia Power Company concurs with the BWR Owner's Group implementa-tion criteria and will resolve this request accordingly.
2.1.8.C Inplant Iodine Instrumentation Georgia Power Company concurs with the BWR Owners' Group implementa-tion criteria and will resolve this request accordingly.
2.1.9 Transient and Accident Analysis Georgia Power Company concurs with the BWR Owner's Group implementa-tion criteria and will resolve this request accordingly.
ACRS Containment Pressure, Water Level, and Hydrogen Indica' tion Design reviews of the containment pressure, water level, and hydrogen indication systems are currently being made.
If the design of the systems do notmeet the BWR Owner's Group Implementation Criteria, the systems will either be modified or justification for not modifying the systems will be provided.
ACRS Reactor Coolant System Venting Georgia Power Com1any concurs with the BWR Owner's Group implementa-tion criteria.
2.2.1.A Shif t Supervisor Responsibility Following the accident of TMI-2, a review of the procedures goyerning the shif t supervisors' responsibilities at Plant Hatch was conducted.
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ATTACHMENT 1(Continued)
NEAR TER'i REQUIREMENTS OF NUREG-0578 Georgia Power Company agrees with the intent of the staff's position.
However, exception is taken to item 2.b of the staff's position in Appendix A of NUREG-0578. There may be special circumstances in accident situations where the shift supervisor may most effectively control the activities of the plants' operators from other than the control room. While it is recognized that the most effective location for the supervisor is the control room in all but the rare case, we reserve the option of allowing the shift supervisor to conduct his supervisory efforts from the most advantageous position after adequate provision for control room coordination has been made.
2.2.l.B Shift Technical Advisor Georgia Power Company concurs with the BWR Owner's Group implementa-tion criteria and will resolve this request accordingly.
2.2.1.C Shif t and Relief Turnover Procedures Following the accident at TMI-2, a review was conducted of the shift and relief turnover procedures at Plant Hatch.
It is also Georgia Power Company's intent to implement the BWR Owner's Group Criteria.
2.2.2.A Control Room Access Georgia Power Company concurs with the BWR Owner's Group implementa-tion criteria and will resolve this request accordingly.
2.2.2.8 Onsite Technical Suoport Center Georgia Power Company concurs with the BWR Owner's Group implementa-tion criteria and will resWe this request accordingly.
2.2.2.C Onsite Operational Support Center Georgia Power Company concurs with the BWR Owner's Group impir.menta-tion criteria and will resolve thS recupet accordingly.
NEAR TERM REQUIREMENTS FOR IMPROVING EMERGENCY PREPAREDNESS (1) The Pl!.it Hatch Emergency Plan was developed with Regulato y Guide 1.101 as a guideline and no further action should be requi ed.
(2) The implementation of the related recomendations of the Lc: sons Learned Task Force is discussed elsewhere in this letter.
(3) Establishment of emergency operations center for Federal, State and Local personnel will be implemented upon the action of these agencies.
Comunications and other requirements will be provided per future discussions and agreements with the responsible agencies.
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ATTACHMENT 1 (Continued)
NEAR TERM REQUIREMENTS FOR IMPROVING EMERGENCY PREPAREDNESS (4) The required offsite monitoring capabilities will be provided when appropriate criteria are established and agreed upon.
(5) The Plant Hatch Emergency Plan has been approved and is in place.
It is compatible with the State of Georgia's Emergency Plan now under review by the NRC.
(6) Such test exercise.e are conducted periodically, on a schedule con-sistent with requirements.
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ATTACHMENT 2 DESCRIPTIVE INFOR"ATION FOR REACTOR COOLANT SYSTEM VENTING Each of the Hatch units is provided with eleven safety relief valves, remotely operable from the Main Control Room. The SRV's are connected to the main steam lines and are within the primary containment. The valves and their operators are qualifici for the LOCA environment. The air supply to seven (the ADS valves) of th > SRV's have backup air accumulators.
The RPV head vent valves :*e remotely operable from the main control room.
The valves are normally closed with solenoids that are normally de-energized.
The head vent line discharges to the drywell sump.
The HPCI and RCIC pumps ar? steam driven.
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