ML20236H071
| ML20236H071 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf |
| Issue date: | 10/30/1987 |
| From: | Kintner L Office of Nuclear Reactor Regulation |
| To: | Kingsley O SYSTEM ENERGY RESOURCES, INC. |
| References | |
| NUDOCS 8711030415 | |
| Download: ML20236H071 (4) | |
Text
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October 30, 1987 4
i Docket No. 50-416 DISTRIBUTION tDocketfilE J.Partlow Mr. Oliver D. Kingsley, Jr.
.Vice President Nuclear Operations PD22 Reading Gray File System Energy Resources, Inc.
S. Varga E. Jordan-P. O. Box 23054 G. Lainas OGC-Beth Jackson, Mississippi 39205 D. Miller L. Kintner
Dear Mr. Kingsley:
SUBJECT:
GRAND GULF NUCLEAR STATION (GGNS), UNIT 1 - REQUEST FOR l
ADDITIONAL INFORMATION REGARDING EXCEPTIONS TO TECHNICAL SPECIFICATION-3.0.4 By [[letter::AECM-87-0190, Application for Amend to License NPF-29,changing Standby Liquid Control Sys (SLCS) Pump Relief Valve Setpoint from Present within 3% of 1,400 Psig to Actuate within 3% of SLCS Design Pressure.Fee Paid|letter dated October 23, 1987]], System Energy Resources, Inc., requested changes to the GGNS Unit 1 Technical Specifications to allow one-time excep-tions to Specification 3.0.4 for the second refueling outage. The NRC staff is reviewing this submittal and finds that additional information as identified in the enclosure is needed to complete its review.
The requested inferrration was discussed by telephone with your representatives on October 27, 1987.
Please provide information as requested in the enclosure.
In order to maintain our review schedule, the information should be provided by November 16, 1987.
The reporting arid /or recordkeeping requiren,ents of this letter affect fewer than 10 respondents; therefore, CMB clearance is not required under P.L.96-511.
Sincerely, i
original signed by Lester L. Kintner, Project Manager Project Directorate II-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation J
Enclosure:
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j Docket No. 50-416 Mr. Oliver D. Kingsley, Jr.
Vice President, Nuclear Operations System Energy Resources, Inc.
P. O. Dox 23054 Jackson, Mississippi 39205
Dear Mr. Kingsley:
SUBJECT:
GRAND GULF NUCLEAR STA110N (GGNS), UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING EXCEPTIONS TO TECHNICAL SPECIFICA110N 3.0.4 By [[letter::AECM-87-0190, Application for Amend to License NPF-29,changing Standby Liquid Control Sys (SLCS) Pump Relief Valve Setpoint from Present within 3% of 1,400 Psig to Actuate within 3% of SLCS Design Pressure.Fee Paid|letter dated October 23, 1987]] System Energy Resources, Inc., requested changes to the GGNS Unit 1 Technical Specifications to allow one-time excep-tions to Specification 3.0.4 for the second refueling outage. The NRC staff is reviewing this submittal and finds that additional infonnation as identified in the enclosure is needed to complete its review.
The requested infontation was discussed by telephone with your representatives on October 27, 1987.
Please provide information as requested in the enclosure.
In order to maintain our review schedule, the information should be provided by November 16, 1987.
The reporting and/or recordkeeping requirements of this letter affect fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely.
Lester L. Kintner, Project Manager Project Directorate II-2 Division of Reactor Projects-I/II Office of Nuclear P.eactor Regulation
Enclosure:
As stated l
cc:
See next page l
/
r l
Mr. Oliver D. Kingsley, Jr.
System Energy Resources, Inc.
Grand Gulf Nuclear Station (GGNS)
-CC:
Mr. Ted H. Cloninger Mr. C. R. Hutchinson Vice President, Nuclear Engineering GGNS General Manager and Support System Energy Resources, Inc.
System Energy Resources, Inc.
Post Office Box 756 Post Office Box ?3054 Port Gibson, Mississippi 39150 Jackson, Mississippi 39205 Robert B. McGehee, Esquire The Honorable William J. Guste, Jr.
Wise, Carter, Child, Steen and Caraway Attorney General P.O. Box 651 Department of Justice Jackson, Mississippi 39205 State of Louisiana Nicholas S. Reynolds, Esquire Bishop Liberman, Cook, Purcell Office of the Governor and Reynolds State of Mississippi 1200 17th Street, N.W.
Jackson, Mississippi 39201 Washington, D. C.
20036 Attorney General Mr. Ralph T. Lally Gartin Building Manager of Quality Assurance Jackson, Mississippi 39205 Middle South Utilities System Services Inc.
P.O. Box 61000 Mr. Jack McMillan, Director New Orleans, Louisiana 70161 Division of Solid Waste Management Mississippi Department of Natural Mr. John G. Cesare Resources Director, Nuclear Licensing System Energy Resources, Inc.
Post Office Box 10385 P.O. Box 23054 Jackson, Mississippi 39209 l
Jackson, Mississippi 39205 Alton B. Cobb, M.D.
i Mr. R. W. Jackson, Project Engineer State Health Officer I
Bechtel Power Corporation State Board of Health 15740 Shady Grove Road P.O. Box 1700 Gaithersburg, Maryland 20877-1454 Jackson, Mississippi 39205 1
Mr. Ross C. Putcher President Senior Resident Inspector Claiborne County Board of Supervisors U.S. Nuclear Regulatory Conxnission Port Gibson, Mississippi 39150 l
Route 2, Box 399 i
Port Gibson, Mississippi 39150 1
Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 Mr. James E. Cross GGNS Site Director System Energy Resources, Inc.
P.O. Box'756 l
Port Gibson, Mississippi 39150 L_.-_---_--.-----
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1.
Define " functional" as used in the attachnient to the October 23, 1987 submittal.
For example, Paragraph C.2 states "....the intent of the SERI outage policy is to traintain at least one ECCS system and one Fuel Pool Cooling and Cleanup systeni functional at all tines."
'2.
With respect to the alternate meiheds capable of decay heat removal and reactor coolant circulation:
(a)
Identify the specific alternate methods that are planned to be used in the second refueling outage, including the times when exceptions to Technical Specification 3.0.4 may be used.
(b) Describe the results of the analyses to demonstrate adequate cooling of spent fuel while using these alternate methods, including spent fuel in the reactor vessel, upper containment pool and spent fuel pool.
Include a description of the assumptions and methods of analysis, including decay heat loads, water circulation paths within the reactor vessel and core, and the criterion for adequate cooling.
(c) Describe the tests planned to demonstrate the adequacy of these alternate methods, including the location and acceptable value for the measurement of those test parameters which will demonstrate adequacy. Relate acceptance parameters to the analyses identified in (b) above. Describe the reactor and refueling conditions when the tests will be run (e.g., reactor head on, reactor flooded, reactor drained, spent fuel in upper containment pool).
3.-
For each alternate method of decay heat removal, describe the steps that would be taken in the event the alternate nethod fails during the time it is being used in the outage (e.g., loss of offsite power) assuming the residual heat removal system is not operable.
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