ML20057F903
| ML20057F903 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/12/1993 |
| From: | Link B WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-93-112 VPNPD-93-182, NUDOCS 9310190322 | |
| Download: ML20057F903 (4) | |
Text
.
y-4 M Wisconsin ~
' Electac.
1 POWER COMPAtN I
231 w Mcngon. Po Bor 204$. wwoukee. wi 53201-2046
-(414) 221-2345 VPNPD-93-182 NRC 112 October 12, 1993 f
Document Control Desk 10 CFR 50.63 i
U.S.
NUCLEAR REGULATORY COMMISSION i
Mail Station Pl~137 Washington, DC 20555 Gentlemen:
DOCKETS 50-266 AND 50-301 SUPPLEMENT TO 10 CFR 50.63. TAC. NOS. 68586 AND 68587 LOSS OF ALL ALTERNATIEG CURRENT POWER POINT BEACH NUCLEAR PLANTS. UNITS 1 AND 2 On August 16, 1993, Wisconsin Electric Power Company (WE)_ received' a letter from the NRC dated August 12, 1993, which states,
"...the staff concludes that [ Gas Turbine] G-05 appears to be capable,of achieving the required 95% reliability level."
This conclusion provides closure of the only remaining open item for compliance with 10 CFR 50.63, " Loss of All Alternating Current Power," for Point Beach Nuclear Plant.
The August 12 letter also requests a response within 60 days.regarding the implementation of Wisconsin Electric's commitments to satisfy the requirements of 10 CFR 50.63.
This letter provides the status of those commitments.
j The original SER was provided to WE in a letter from the NRC dated October 3, 1990.
The Station' Blackout' rule (10 CFR 50.63) required the licenses to respond to the original SER within 30 days.
That-response was provided to the NRC in Letter NRC-90-110, dated November 8, 1990.
A supplemental Station Blackout safety;evalu-ation report (SER) was provided in a letter to Mr. C.
W.. Fay. (WE) from Mr.
R..B.
Samworth (NRC) dated March 22, 1991.
This supple-mental SER provided the NRC's acceptance of Wisconsin Electric's response to the original SER.
The supplemental SER stated that it may be beneficial to plan another meeting with NRC technical staff as our final design of the diesel generator installation nears completion.
The meeting should also address qualification of the gas turbine generator.
Accordingly, meetings with NRC staff were held on June 25, 1992, i
and May 3, 1993.
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l Document Control Desk-October 12, 1993 Page 2 i
I We have reviewed the status of implementation of our commitments to satisfy the requirements of 10 CFR 50.63.
A summary of our' review is provided in an attachment to this letter.
The documentation of the baseline assumptions, analyses, and related information used~1n the coping evaluations for Point Beach are available for NRC review i
as required by 10 CFR 50.63 (a) (2).
We would be pleased to answer any questions you may have.
l Sincerely, C
/
Bob Link Vice President Nuclear Power CAC/jg Attachment cc:
NRC Regional Administrator; Region III NRC Resident Inspector
Attachment to Letter Page 1 of 2 Evaluation of the SER and Supplemental SER for Station Blackout Wisconsin Electric Power Company Point Beach Nuc3 ear Plant Units 1 and 2 Docket Nos. 50-266 and 50-301 Note:
The section numbers in this evaluation correspond to the section numbers in the supplemental SER.
I i
2.1 Proposed AAC Power Source T'he supplemental SER states that no information was provided as to what loads are being powered from the AAC power source.
Additionally, the NRC stated that the loads being I
powered during the tests are representative of or envelope the loads required for an SBO and it should be demonstrated i
that the operator actions required during an SBO are enveloped by the test.
During Test Precedure PC-29, G-05 is loaded on the grid at approximately 2 MW for about 15 minutes.
After that, the unit is base loaded at about 17 MW for at least one hour.
The unit was on-line for about 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> during a Station g
Blackout duration test.
The total SBO loading does not i
exceed about 2.8 MW, which is the EDG load rating.
Therefore, the SBO loading is enveloped.
l The gas turbine is loaded by synchronizing it onto the grid.
This method of loading the gas turbine is different than the manual control method that would be used in a blackout.
The steps used to start and load the gas turbine including preparing to start, starting, and placing the unit "on-line" are very similar to the operator actions which would be required during an SBO and as such are considered to be enveloped by the test.
2.2 Condensate Inventory for Decay Heat Removal The Technical Specification change to raise the minimum CST inventory to 13,000 gallons per operating unit was implemented as Amendment Number 130 for Unit 1 and 134 for Unit 2, effective April 8,
1992.
I 2.3 Class 1E Batterv i
Battery capacity calculations prove the adequacy of the l
station batteries for one hour of Station Blackout.
_l l
i
Attachment to Letter Page 2 of 2 l
2.4 Effects of Loss of Ventilation The calculations for the effects of loss of ventilation are complete.
The computer room and control room' ceilings were modified to reduce the temperature r aes in these areas.
The calculation for the computer room was re-performed as required by the SER using a higher initial temperature.
2.5 Procedures and Trainina There are no special SBO commitments for this issue.
2.6 Proposed Modification The supplemental SER reiterates that the SBO coping evaluations and analyses will be amended for plant configuration changes.
The installation of two additional emergency diesel generators is proceeding for Point Beach Nuclear Plant.
A supplemental submittal for Station Blackout will be sent prior to completion of the installation.
1 OA Proaram for Eauipment Used to Cope with an SBO l
The NRC accepted the commitment in the original SER response.
A t
QA program has been established and implemented for equipment used during a station blackout that wasn't already covered by the existing QA program.
j EDG Reliability Proaram The NRC accepted the commitment in the original SER response to i
establish an EDG reliability program that conforms to the guidance of RG 1.155, Position 1.2.
An EDG reliability program has been established and implemented.
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