ML20210T250

Requests Addl Info Re Util 851014 Description of Plans for Implementing Requirements of 10CFR50.62.Plan Acceptable.Addl Info Re Proposed Design & Endorsement of Design Presented in NEDE-31906-P Also Requested

ML20210T250
Person / Time
Site:	Grand Gulf
Issue date:	02/11/1987
From:	Kintner L Office of Nuclear Reactor Regulation
To:	Kingsley O SYSTEM ENERGY RESOURCES, INC.
References
NUDOCS 8702180129
Download: ML20210T250 (5)

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February 11, 1987 Docket No. 50-461 -DISTRIBUTION j 46- JPartlow I Mr. Oliver D. Kingsley, Jr.

NRC"PDR*~" NThompson' l

.Vice President, Nuclear Operations LPDR LKintner '

System Energy Resources, Inc. PDf4 Rdg. M0'Brien

.P. O. Box 23054 .

RBernero ACRS(10)

Jackson, Mississippi 39205 Young, OGC

. EJordan

Dear'Mr. Kingsley:

BGrimes

SUBJECT:

ANTICIPATED TRANSIENTS WITHOUT SCRAM - RESPONSE TO 10 CFR 50.62 Re: Grand Gulf Nuclear Station, Unit 1 (GGNS-1) t The NRC staff has completed its review of topical report NEDE-31096-P,

" Anticipated Transients without Scram; Response to NRC ATWS Rule, 10 CFR 50.62".

-The staff's safety evaluation of NEDE-31096-P was transmitted to Mr. Terry A.

Pickens, Chaiman, BWR Owners Group by letter dated October 2,1986 from Mr. Gus Lainas, Assistant Director, Division of BWR Licensing, NRC. The staff found the report to be acceptable for referencing by licensees who participated in the BWR Owners Group topical report. Since Mississippi Power & Light Company was a participant, the plant specific submittal for GGNS-1 may reference NEDE-31096-P as the basis for conformance to 10 CFR 50.62.

By letter dated October 14, 1985, Mississippi Power &. Light Company submitted a description of its plans for implementing the requirements of 10 CFR 50.62 in GGNS-1. The staff has reviewed this submittal and concludes that the proposed schedule for implementation (prior to startup following the second refueling) is acceptable. However, additional information as described in the enclosure is needed regarding the proposed design. In addition,'you should provide a specific endorsement of the design presented in NEDE-31906-P and a commitment to meet the applicable conditions in the staff's safety evaluation of NEDE-31906-P. An application for a license amendment to add technical specifications for the ATWS related components should also be provided.

In order to meet our review schedule, you should provide the information requested above by March 30, 1987. If you cannot meet this date or have questions regarding the requested information, please contact me.

Sincerely, Odginal s;gned by Lester L. Kintner, Project Manager BWR Project Directorate No. 4 Division of BWR Licensing

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Enclosure:

As stated T

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-e p.0 s LEC UNITED STATES o NUCLEAR REGULATORY COMMISSION y ;p WASHINGTON, D. C. 20555

'% , , , , , # February 11, 1987 Docket No. 50-461 Mr. Oliver D. Kingsley, Jr. .

Vice President, Nuclear Operations System Energy Resources Inc.

P. O. Box 23054 Jackson, Mississippi 39205

SUBJECT:

ANTICIPATED TRANSIENTS WITHOUT SCRAM - RESPONSE TO 10 CFR 50.62 Re: Grand Gulf Nuclear Station, Unit 1 (GGNS-1)

The NRC staff has completed its review of topical report NEDE-31096-P,

" Anticipated Transients without Scram; Response to NRC ATWS Rule, 10 CFR 50.62".

The staff's safety evaluation of NEDE-31096-P was transmitted to Mr. Terry A.

Pickens, Chairman, BWR Owners Group by letter dated October 2,1986 from Mr. Gus Lainas, Assistant Director, Division of BWR Licensing, NRC. The staff found the report to be acceptable for referencing by licensees who participated in the BWR Owners Group topical report. Since Mississippi Power & Light Company was a participant, the plant specific submittal for GGNS-1 may reference NEDE-31096-P as the basis for conformance to 10 CFR 50.62.

By letter dated October 14, 1985, Mississippi Power & Light Company submitted a description of its plans for implementing the requirements of 10 CFR 50.62 in GGNS-1. The staff has reviewed this submittal and concludes that the proposed schedule for implementation (prior to startup following the second refueling) is acceptable. However, additional information as described in the enclosure is needed regarding the proposed design. In addition, you should provide a specific endorsement of the design presented in NEDE-31906-P and a commitment to meet the applicable conditions in the staff's safety evaluation of NEDE-31906-P. An application for a license amendment to add technical specifications for the ATWS related components should also be provided.

In order to meet our review schedule, you should provide the information requested above by March 30, 1987. If you cannot meet this date or have questions regarding the requested information, please contact me.

Sincerely, i l

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er .K tner, Project Manager L

BWR Project Directorate No. 4 Division of BWR Licensing

Enclosure:

As stated cc: See next page i

v 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 23054 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 Baton Rouge, Louisiana 70804 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 i New Orleans, Louisiana 70161 Division of Solid Waste Management Mississippi Department of Natural Mr. John G. Cesare Resources Director, Nuclear Licensing and Safety Bureau of Pollution Control System Energy Resources, Inc. Post Office Box 10385 '

P.O. Box 23054 Jackson, Mississippi 39209 Jackson, Mississippi 39205' Alton B. Cobb, M.D.

Mr. R. W. Jackson, Project Engineer State Health Officer Bechtel Power Corporation State Board of Health 15740 Shady Grove Road P.O. Box 1700 Gaithersbiing, Maryland 20877-1454 Jackson, Mississippi 39205 t Mr. Ross C. Butcher President Senior Resident Inspector Claiborne County Board of Supervisors U.S. Nuclear Regulatory Commission Port Gibson, Mississippi 39150 Route 2. Box 399 Port Gibson, Mississippi 39150 j Regional Administrator, Region II U.S. Nuclear Regulatory Connission 101 Marietta Street, N.W., Suite 2900 t

Atlanta, Georgia 30323 i Mr. James E. Cross GGNS Site Director System Energy Resources, Inc.

P.O. Box 756 Port Gibson, Mississippi 39150

.3; j's

P Enclosure.

l REQUEST FOR ADDITIONAL INFORMATION ON ATWS REVIEW The information provided in your submittal dated October 14, 1985, "GGNS ATWS:

Rule Compliance Schedule", is not sufficient.for the staff to determine that

. the Grand Gulf design is in compliance with the Commission's regulations.

Provide the following information as supporting documentation of your method of compliance with 10 CFR 50.62:

1. The documentation to describe the analysis 'and/or tests to verify that .

the Alternate Rod Injection (ARI) system function time will begin within 15 seconds and be completed within 25 seconds from ARI initiation.

2. The documentation including the detailed electrical schematic diagrams for the ARI system from the sensors to' the. solenoid coil of the ARI

! valves to demonstrate that no single failure will prevent the ARI <

initiation, and inadvertent actuation is minimized.

3. The electrical one line diagram to demonstrate the electrical indepen-l dence between the ARI system and the reactor trip system (RTS).

j 4. The qualification information on isolation devices:

a. For the type of device used to accomplish electrical isolation, i describe the specific testing performed to demonstrate that the

device is acceptable for its application (s). This' description should include elementary diagrams when necessary to indicate the i

test configuration and how the maximum credible faults were applied to the devices.

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b. Data to verify that the maximum credible faults applied during the test were the maximum voltage / current to which the device could be -

exposed. In addition define how.the maximum voltage / current was determined.

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c. Data to verify that the maximum credible fault was applied to the output of the device in the transverse mode (between signal and return) and other faults were considered (i.e. open and short 4

circuits).

l d.- Define the pass / fail acceptance criteria for each type of device.

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e. Provide a connitment that the isolation devices comply with the environmental qualifications (10 CFR 50.49) and with the seismic qualifications which were the basis for plant licensing.

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f. Provide a description of the measures taken to protect the safety systems from electrical interference (i.e., Electrostatic Coupling, EMI, Common Mode and Crosstalk) that may be generated by the ATWS circuits.

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, . --s l g. Provide information to verify that the Class IE isolator is powered from a Class IE source. 4

5. The information readout to the control room operator for the ART and the RPT systems.

6. Describe the system design to permit maintenance repairs and test or calibration of the system logic.

7. The documentation. including the detailed electrical schematic diagrams for the Recirculation Pump Trip (RPT) system to demonstrate that no single failure will prevent the RPT initiation and that inadvertent actuation is minimized.

8. Complete the " Checklist for Plant Specific Review of Alternate Rod Inspection System (ARI)" in Appendix A to the staff's safety evaluation of NEDE-31096-P.

j 9. Provide the following information regarding the proposed manual two pump standby liquid control system (SLCS):

a. Describe how the equivalent flow requirement will b m increasing concentration of solution or enriching B T0)et(e.g.by

b. Describe initial and periodic testing to verify flow capability.

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