ML20147B730
| ML20147B730 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 10/04/1978 |
| From: | Whitmer C GEORGIA POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7810110135 | |
| Download: ML20147B730 (5) | |
Text
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October 4, 1978 Q
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Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN 1. HATCH NUCLEAR PLANT UNIT'2 PRIt!ARY CONTATNMENT INTERNAL PRESSURE Gentlemen:
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 Operating License).
The proposed change would allow operation with drywell pressure above 0.75 psig for the duration of the Safety Relief Valve Discharge Capacity Startup Test.
Specification 3.6.1.6 requires that the Primary Containment Internal Pressure be maintained below 0.75 psig.
In order to perform complete and meaningful testing of SRV loading on the torus structure, it is necessary to operate the dryeell at a positive pressure of 1." to 1.6 psig to establish an appropriate pressure differential between the drywell and wetwell.
Establishment of a 1.5 psig pressure in the drywell for this tes:ing would be a viola-tion of Technical Specification 3.6.1.6.
The limitations on primary containment internal pressure ensure that the containment peak pressure of 57.5 psig does not exceed the maximum allowabic internal pressure of 62 psig during LOCA conditions or that the external pressure does not exceed the design maximum external pressure of 2 psig.
The current limit of 0.75 psig for initial positive containment pressure has been used in accident analysis and it has been so determined that such a pressure in the drywell and wetwell will limit the total pressure, under LOCA conditions to 57.5 psig.
Operation above 0.75 psig for a limited period for testing purpose is felt to be justified without an extensive reanalysis based on the following points:
e Original accident analysis assumed a drywell and wetwell volume at 0.75 psig.
Recognizing that the free air volume of the drywell and wetwell are approximately equal, it can be deternined that the initial quantity of a
air contained in the combined drywell and wetwell " system" is the same for the conditions of drywell at 1.5 psig and wetwell at 0 psig as the condition of drywell at 0.75
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Director of Nuclear Reactor Regulation October 4, 1978 Page 2 psig and wetwell at 0.75 psig. Thus, it can be seen that the total initial. starting energy contained in the " system" is the same for these two conditions and the end point pressure of the " system" post-LOCA will not be significantly different.
e The exemption of the primary containment internal pressure jech spec limit of.75 psig is only temporary for purposes of testing SRV loading and is not expected to be in effect for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
e The information which will be determined from this testing la significant to the overall SRV-Torus Long Term Program and the role that a AP system, such as is operational on P.lant Hatch Unit 1, will play in that long term solution.
j The reactor is expected to operate at maximum conditions e
of approximately 1000 psig and less than 55% power during the period of this temporary technical specification change.
e Other BWRs of similar design operates without a limitation at 0.75 psig containment pressure.
The Plant Review Board and the Safety Review Board have reviewed I
the proposed change and have determined that it does constitute an unroviewed safety question. However, for the reasons listed above, the Review Boards have determined that temporary operation above the technical specification limit of.75 psig for the duration of the SRV discharge test is justified without a complet.e reanalysis of the applicabic accidents.
We request your early review and approval of the proposed change.
Yours~very truly, m
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Chas. F. Whitmer WEB / JAB /mb Enclosure i
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Sworn te.a subscribed befo me
- sis 4th day of October'at targe 1978.
Notary Pt.blic, Georgia, State idy Commission Expires Jan. 6,1981 Notary Public l
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Mr. Ruble A. Thomas i
George F. Trowbridge, Esquire I
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ATTACHMENT 1
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NRC-DOCKET 50-366-OPERATING LICENSE NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2
.. PROPOSED DETERMINATION OF AMENDMENT CLASS i
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:
l a)
The proposed amendment does not require the evaluation of a new.
Safety Analysis Report or rowrit'e 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 the addition of a special provision to allow operation with drywell pressure above the current limit of 0.75 psig for the duration of the Safety Relief Valve Discharge Capacity Startup Test.
e)
The proposed amendment is therefore a Class III amendment.
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' ATTAC1DIENT 2
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NRC. DOCKET 50-366~
OPERATING-LICENSE NPF-5 4
EDWIN I. HATCH NUCLEAR PLANT' UNIT 2 PROPOSED ~ CHANGES TO TECHNICAL SPECIFICATIONS 1
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The proposed' changes'to the Technical Specifications-(Appendix A to
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Operating License NPF-5 would be incorporated as follows:
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REMOVE PAGE INSERT PAGE 3/4 6-9 3/4 6-9 I
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-CONTAINMENT SYSTEMS, PRIMARY: CONTAINMENT ' INTERNAL. PRESSURE
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-LIMITING' CONDITION FOR OPERATION' r
i 3.6.1.6 Primary containment internal' pressure shall not exceed 0.75 psig.*
APPLICABILITY:
CONDITIONS'1,'2 and 3.
-ACTION:
?
With the primary. containment internal pressure in excess' of the 'specified.
' limit, restore the internal pressure to within the limit'within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> i
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 SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
1 I
1 SURVEILLANC~ REQUIREMENTS 4.6.1.6 The. primary containment internal. pressure shall be determined
' to 'tue less than or. equal to 0.75 ~ at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- Except when performino the test required by Specification 4.6.4.1.b.
and for duration ~ of the SRV Discharge Capacity Startup Test.
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