ML19289D353
| ML19289D353 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 02/27/1979 |
| From: | Whitmer C GEORGIA POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7903050383 | |
| Download: ML19289D353 (6) | |
Text
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na cna r. vcHen. r February 27, 1979 Georgia Power wr o no v fto sard'> m o n P.
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[,,)oco-2 Director of Nuclear Reactor Regulation Nuclear Regulatory Commission Washington, D. C.
20555 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN 1. HATCH NUCLE *,R PLANT UNIT 2 CORE SPRAY SYSTEM OPERABILITY Gentlemen:
In accordance with the provisions of 10 CFR 50.90, as required by 10 CFR 50.59, Georgia Power Company hereby proposes an amendment to Operating License NPF-5.
The proposed amendment consists of a change to the Technical Specifications (Appendix A to the Operating License) to incorporate a change in the Technical Specificaticns definition of OPERABILITY of the Core Spray System.
The cristing Core Spray specification (3.5.3.1) requires an operable core spray pump and an operable flow path from the suppression chamber to the reactor vessel in each loop in ordcr to meet the definition of operability. The proposed change to the Technical Specifications would add an alternate flow path from the condensate storage tank to the reactor vessel to the limiting conditions for operability which would fulfill the operability definition in lieu of the flow path from the suppression chamber.
The specifD ation is further modified to allow the alternate flow path only s
when the reactor is in cold shutdown or refuel modes (conditions 4 and 5) only for the rurpose of draining the suppression chamber and only provided that no work is in progress which would have the potential for draining the reactor vessel.
In additfor., the Surveillance Requirements specification associated with the Core Spray LC0 would also be modified to require verification of valve lineup and filled pipes once per shift rather than once per 31 days when the system is aligned with suction from the condensate storage tank.
The proposed change does not affect the RHR system's capability to operate in the shutdown cooling mode.
In addition, several alternate sources of cooling water remain available during the period of time when core spray is aligned to the condensame storage tank.
As a result, the Plant Review Board and the Safety Review Board have determined that margins of safety are not reduced because the node of operation contemplated utilizes the existing core spray system piping and because work which has the potential for draining the reactor vessel will be prohibited during periods utilizing the alternate 7903050383
k Georgia Power h Director of Nuclear Reactor Regulatinn Nucicar Regulatory Commission February 27, 1979 Page 2 flow path. The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety has not been increased and no new accidents or malfunctions have been created.
The Review Boards have therefore determined that the proposed change to the Technical Speci-fications is not an unreviewed safety question.
The proposed change to the Technical Specifications has been evaluated and is determined to be a Category III amendment; a single safety issue is involved - the availability of sources of cooling water to the reactor in conditions 4 and 5 when core spray is aligned to the condensate storage tank. Therefore, a check for $4,000 is attached.
Your early attention to this proposed change is requested.
Yours very truly, Q
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Chas. F. Whitmer x
RDB/mb Attachment d worn to and subscribed before me this 27th day of February, 1979.
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Notary PuNic, cemria. C'.E t g Public t
M Cammission Expires Sept. 29,1981
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xt: Ruble A. Thomas George F. trowbridge, Esquire
ATTACHMENT 1 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 PROPOSED CdANGES TO TECHNICAL SPECIFICATIONS Pursuant to 10 CFR 170.12 (c), Georgia Power Company has evaluated the attached proposed amendment to Operating License 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 amendment 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, it adds another condition when the Core Spray System can be considered
- operable, c)
The proposed amendment is therefore a Class III amendment.
4
ATTACllMENT 2 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN 1. IIATCll NUCLEAR PLANT UNIT 2 PROPOSED C11ANCES TO TECIINICAL SPECIFICATIONS The proposed change to the Technical Specifications (Appendix A to Operating License NPF-5 would be incorporated as follows:
Remove Page Insert Page 3/4 5-4 3/4 5-4 3/4 5-5 3/4 5-5
EMERGEliCY CORE C00LIrlG SYSTEMS 3/4.5.3 L0h PRESSURE CORE C00 lit!G SYSTEMS CORE SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.5.3.1 Two independent Core Spray System (CSS) subsystems shall be OPERABLE with each subsystem comprised of:
a.
An OPERABLE flow path capable of taking suction from the suppression chamber and transferring the water through the spray sparger to the reactor vessel, or c.** An OPERABLE flow path capable of taking suction from the con-densate storege tank and transferring the water through the spray sparger to the reactor vessel.
APPLICABILITY: CONDITIONS 1, 2, 3, 4, and 5*.
ACTION:
a.
'In CONDITION 1, 2 or 3; 1.
With one CSS subsystem inoperable, POWER OPERATION may continue provided both LPCI subsystems are OPERABLE; restore the inoperable CSS subsystem to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD S!!UTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
With both CSS subsystems inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.
In the event the CSS is actuated and injects water into the reactor coolant system, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the cir-cumstances of the actuation and the total accumulated actuation cycles to date.
- The core spray system and the suppression chamber are not required to be OPERABLE proviced that the reactor vessel head is removed and the cavity is flooded, the spent fuel pool gates are removed, and the water level is maintained within the limits of Specificatin 3.9.9 and 3.9.10.
- The Core Spray System shall be aligned to the condensate storage tank only for the purpose of draining the suppression chamber in CONDITIONS 4 or 5, provided that no work is being done which has the potential for draining the reactor vessel.
HATCH - UNIT 2 3/4 5-4
EMERGEflCY CORE COOLING SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)
ACTION (Continued) b.
In CONDITION 4 or 5*;
1.
With cne CSS subsystem inoperable, operation may continue provided that at least one LPCI subsystem is OPERABLE within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; otherwise, suspend all operations that have a potential for draining the reactor vessel.
2.
With both CSS subsystems inoperable, operation may continue provided that at least one LPCI subsystem is OPERABLE and both LPCI subsystems are OPERABLE within 4 hou rs. Otherwise, suspend all operations that have a potential for draining the reactor vessel and verify that at least one LPCI subsystem is OPERABLE within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
3.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.5.3.1 Each CSS subsystem shall be demonsteated OPERABLE:
a.
At least once per 31 days *** Sy:
1.
Verifying that the system piping from the pump discharge valve to the system isolation valve is filled with water, and 2.
Verifying that each valve (manual, power operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
b.
At least once per 92 days by:
1.
Verifying that each CSS pump can be started from the control room and develops a flow of at least 4625 gpm on recirculation flow against a system head corresponding to a reactor vessel pressure of > 113 psig, and
- 0nce per shift when the Core Spray System is aligned to the condensate storage tank.
HATCH - UNIT 2 3/4 5-5