ML20206E140
| ML20206E140 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 11/16/1988 |
| From: | Kintner L Office of Nuclear Reactor Regulation |
| To: | Cottle W SYSTEM ENERGY RESOURCES, INC. |
| References | |
| TAC-69403, NUDOCS 8811170416 | |
| Download: ML20206E140 (4) | |
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Novembar 16, 1988 DISTRIBUTION D E R T T ITe'il NRC'PDR' ~
Local PDR PD21 r/f S. Varga (14E4)
G. Lainas Docket No. 50-416 E. Adensam P. Anderson L. Kintner Mr. W. T. Cottle OGC Vice President, Nuclear Operations E. Jordan (MNBD3302)
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System Energy Resources, Inc.
ACRS(10)(9A2)
B. Grimes P. O. Box 23054 Jackson, Mississip,'
39205
Dear Mr. Cottle:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION. GRAND GULF NUCLEAR STATION (GGNS), UNIT 1 (TAC NO. 69403)
By letter dated September 23, 1988, System Energy Resources, Inc. requested a review of its proposed alternate decay heat removal system. The NRC staff is reviewing this submittal and finds that additional information is needed to complete our review.
The request for additional information is enclosed.
In order to support our review schedule, you are requested to respond to the enclosed request by November 30, 1988.
This request was discussed with your representatives in a meeting on November 10, 1988.
The reporting and/or recordkeeping requirements of this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P. L.96-511.
Sincerel.t,
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Lestor L. Kintner, Senior Project Manager i
Project Directorato 11-1 Division of Reactor Projects I/II
Enclosure:
Request for Additional Information
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0FFICIAL RECORD COPY 8911170416 881116 PDR ADOCK 05000416 p
PDC 4
F Mr. W. T. Cottle System Energy Re:aurces, Ir.c.
Grand Gulf Nuclear Station (GGNS) cc:
Mr. T. H. Cloninger fir. C. R. Hutchinson Vice President. Nuclear Engineering GGNS General Manager and Suppbrt System Energy Resources, Inc.
System Ensegy Resources, Inc.
Post Office Box 756 P. O. Box 23054 Port Gibson, Mississippi 39150 Jackson, Mississippi 39205 Robert B. McGehee, Esquire The Honorable William J. Guste, Jr.
Wise, Carter, Child, Steen and Attorney General Caraway Department of Justice P. O. Box 651 State of Louisiana Jackson, Mississippi 39205 Baton Rouge, Louisiana 70804 Nicholas S. Reynolds, Esquire Office of the Governor Bishop, Liberman, Cook, Purcell State of Mississippi and Reynolds Jackson, Mississippi 39201 1400 L Street, N.W.
Washington, D.C.
20005-3502 Attorney General Gartin Building Mr. Ralph T. Lally Jackson, Mississippi 39205 Manager of Quality Assurance Middle South Utilities System Mr. Jack McMillar., Director Services, Inc.
Division of Solid Waste Management 639 Loyola Avenue, 3rd Floor Mississippi Department of Natural New Orleans, Louisiana 70113 Resources Post Office Box 10385 Mr. John G. Cesare Jackson, Mississippi 39209 Director, Nuclear Licensing System Energy Resources, Inc.
Alton B. Cobb, M.D.
P. O. Box 23054 State Health Officer Jackson, Mississippi 39205 State Board of Health P.O. Box 1700 Mr. C. B. Hogg, Project Manager Jackson, Mississippi 39205 Bechtel Power Corporation P. O. Box 2166 President Houston, Texas 77252-2166 Claiborne County Board of Supervisors Port Gibson, Mississippi 39160 Mr. H. O. Christensen Senior Resident Inspector Regionai Administrator, Region 11 U.S. Nuclear Regulatory Comission U. S. Nuclear Regulatory Comission Route 2. Box 399 101 Marietta Street Port Gibson, Mississippi 39150 Suite 2900 Atlanta, Georgia 30323
7 ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION ALTERNATE DECAY HEAT REMOVAL SYSTEM (ADHRS)
GRAND GULF NUCLEAR STATION, UNIT 1 (GGNS-1)
The following information is needed for the staff's review of the ADHRS in addition to that provided in the September 23, 1988 submittal. These. aspects were discussed in the November 10, 1988 meeting with the licensee.
Include references to the September 23 submittal, where appropriate.
1.
Describe and justify the seismic design criteria for the ADHRS piping and componentsincludingtheplantservicewater(PSW)pipingtobeaddedin this modification.
Include a description of the criteria tn be used for non-Seismic Category I piping and components where such piping and components could damage Seismic Category I piping or components.
2.
Describe and justify the quality group classification for ADHRS and PSW piping and components to be added in this modification.
3.
Describe and justify the pipe break criteria and evaluations.
Include an 4
evaluation of the potential for flooding the RHR "C" pump room due to a ruptured PSW pipe or components.
4.
Describe and justify the ASME Code year and addenda used in the design of the ADHRS piping and components. Reconcile the use of any code editions or addenda which differ from the licensing (NUREG-0831, Safety Evaluation basis codes approved by the NRC staff in the operating license review Report and Supplements 1 through 7).
Justify the code editions and addenda specified for components of the ADHRS that were designed for use in the Unit 2 spent fuel pool cooling system, and describe any modifi-cations made to such components for use in the ADHRS.
5.
Describe the components of the ADHRS that will be included in the GGNS-1 Inservice Testing Program and the GGNS-1 Inservice Inspection Program.
Describe and justify all deviations from ASME Code,Section XI, Subsections IWP and IWV regarding testing of pumps and valves, if any.
6.
On Page P-56 of the September 23, 1988 submittal, a statement is made that LOCA and Loss of Offsite Power (LOP) are not considered.
In Operational Condition 4 and 5, automatic isolation of certain valves are required in the event of draining the reactor to a certain low leycl.
These isolation valves are required to function with a loss of offsite power. Describe and justify criteria for isolation of valves to prevent draining when the ADHRS is in operation.
l 7.
On Page P-85 through P-87, a number of procedural and other actions are w
given as conditions for acceptable interactions of the ADHRS with existing systems. Describe how these conditions will be implemented in plant procedures or administrative controls and how operations personnel will be trained to use the ADHRS.
2 8.
Describe the outage activities for which the ADHRS will be used and any limitations on its use, such as a fraction of the outage time.
9.
In order to provide the ability for remote-manual alignment of RHR "A" or "B" loops during ADHRS operation, Class 1E motor operators are being added to valves E12F066A and B with controls in the control room.
Since these valves are powered from the Class 1E buses, demonstrate that the corresponding diesel generator has adequate capacity to accommodate these additional loads.
In addition, provide control wiring diagrams for these valves.
10.
It is stated in the September 23, 1988 submittal that valves E12F066A and B are locked closed during norral plant operation and administratively controlled during Operational Conditions 4 and 5.
Describe how these manually controlled electrically-operated valves meet Branch Technical Position.8 contained in the standard P.<iew Plan (NUREG-0800), Appendix 8A.
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