ML19257A971

From kanterella
Jump to navigation Jump to search

Forwards Safety Evaluation Approving Preliminary Design for safety-grade Anticipatory Reactor Trip on Loss of Feedwater & Turbine Trip.Requests Addl Info for Final Design Approval
ML19257A971
Person / Time
Site: Oconee, Arkansas Nuclear, Crystal River, Rancho Seco  
Issue date: 12/20/1979
From: Reid R
Office of Nuclear Reactor Regulation
To: Mattimoe J
SACRAMENTO MUNICIPAL UTILITY DISTRICT
References
TASK-2.K.2.10, TASK-TM TAC-45188, NUDOCS 8001110627
Download: ML19257A971 (3)


Text

{{#Wiki_filter:. ~ ~ yr o ~,, UNITED STATES 8 NUCLEAR REGULATORY COMMISSION n { .,I wasHWGTON,D C.20888

  • ..../

December 23, 1979 Docket No. 50-312 Mr. J. J. Mattimoe Assistant General Manager and Chief Engineer Sacramento Municipal Utility District 6201 S Street P. O. Box 15830 Sacramento, California 95813

Dear Mr. Mattimoe:

SUBJECT:

PRELIMINARY DESIGN APPROVAL FOR THE SAFETY-GRADE ANTICIPATORY RIACTOR TRIP (ART) ON LOSS OF FEEDWATER /JD TUR8INE TRIP We have reviewed your submittals of May 21 and October 5,1979, in which you forwarded a preliminary design for upgrading the present control-grade ART for loss of feedwater and turbine trip to safety-grade. A copy of the-staff safety evaluation (SE) approving your preliminary design is included as an enclosure to this letter. As sumarized in Attachment 1 of this evaluation, additional information will need to be submitted prior to the final design approval. Therefore, insure that this information is submitted for staff review in sufficient time to allow staff approval prior to system operation. If you have any questions in this matter, please contact the NRR Operating Reactor Project Manager, Mr. Daniel Garner at (301) 492-7435. Sincerely, ( ./. b l l. Y' Robert W. Peid, Chief Operating Reactors Branch #4 Division of Operating Reactors

Enclosure:

SE cc w/ enclosure: See next page }[4h 29l E' q [ i,I 8001110627

Sacrame..to Municipal Utility District ecw/ enclosure (s): Christopher Ellisen, Esq. David S. Kaplan, Secretary and Dian Grueufch, Esc. General Counsel California Energy Ccmission 6201 S Street lill Howe Avenue P. O. Box 15830 Sacramento, Califerr.ia 95825 Sacramento, California 95813 / Ms. Eleanor Schwartz Sacramento County California State Cffice Board of Supervisors 600 Pennsylvania Avenue, S.E., Rm. 201 827 7th Street, Room 424 Washington, D.C. 20C33 Sacramento, California 95814 Office of the Secretary Business and Municipal Department U. S. Nuclear Reg;1a.tcry Comission Sacramento City-County Library Washington, D.C. 20555 828 I Street Sacramento, California 95814 Director, Technical Assessment Division Office of Radiation Programs Dr. Richard F. Cole (AW-459) Atomic Safety and Licensing Board U. S. Environmental Protection Agency Panel Crystal Mall #2 U. S. Nuclear Regulatory Comission Arlington, Virginia 20460 Washington, D.C. 20555 U. S. Environmental Protection Agency Mr. Fred trick J. Shon Region IX Office Atomic 1,*ety and Licensing Board ATTN: EIS COORDINATOR Panel 215 Fremont Street U. S. Nuclear Reculatory Comission San Francisco, California 94111 Washington, D.C.' 20555 Mr. Robert B. Borsum Elizabeth S. Bowart, Esq. Babcock & Wilcox Chairman, Atomic Safety and Nuclear Power Generation Division Licensing Boar: Patel Suite 420, 7735 Old Georgetown Road U. S. Nuclear Regulatory Comission !.cthesda, Maryland 20014 Washington, DC 20555 James S. Reed, Esq. Thomas Baxter*, Esq. Michael H. Remy, Esq. Shaw, Pittman, Potts & Trowbridge Reed, Samuel & Remy 1800 M Street, 't.H 717 K Street, Suite 425 3ashington, D. C. 2003G Sacramento, California 95814 Herbert H. Brown, Esq. Mr. Michael 8.. Esten Lawrence Coe Lanpher, Esq. Energy Issues Cocrcicator Hill, Christo:,her and Phillips, P. C. Sierra Club Legislative Office 1900 M St, 1107 9th St., Ro:- IC20 Washington),(NWDh Cd (p r t20036 Sacramento, CA 35514 s 1746 292

~ Sacramento Municipal Utility District cc w/ enclosure (s): Atomic Safety and Licensing Board Panel U. S. Nuclear Regulatory Comission Washington, D.C. 20555 Atomic Safety and Licensing Appeal Board Panel U. S. Nuclear Reguletory Comission Washington, D.C. 20555 Mr. Richard D. Castro 2231 K Street Sacramento, California 95814 Mr. Gary Hursh, Esq. 520 Capital Mall Suite 700 Sacramento, California 95814 California Department of Health ATTN: Chief. Environmental Radiation Control Unit Radiological Health Section 714 P Street,-Room 498 Sacramento, California 95814 1746 293

/ o UNITED STATES g 8 yg NUCLEAR REGULATORY COMMISSION wasmooroa.o.c.acess y g / SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION OF PRELIMINARY DESIGN FOR SAFETY-GRADE ANTICIPATORY REACTOR l TRIPS (ARTS) ON LOSS OF MAIN FEE 0 WATER AND/OR TURBINE TRIP FOR DUKE POWER COMPANY OCOREE RUCLEAR STATION, UNITS N05,1, 2 AND 3 DOCKETS NOS. 50-269, 270 AND 287 SACRAMENTO MUNICIPAL UTILITY DISTRICT RANCHO SECO NUCLEAR GENERATING STATION l DOCKET NO. 50-312 ARKANSAS POWER & LIGHT COMPANY i ARKANSAS NUCLEAR Ot1E, UNIT 1 l DOCKET NO. 50-313 ? FLORIDA POWER CORPORATION CRYSTAL RIVER NUCLEAR GENERATING STATION UNIT NO. 3 DOCKET N0. 50-302 I. BACKGROUND Following the accident at Three Mile Island Unit 2, an assessment of feedwater transientsfin' the Babcock and Wilcox (B&M) designed pressurized water reactors i was perfcrmed. The results of that review were reported in HUREG-0560, Th% report highlighted a concern regarding the challenges to the power-operated relief valves (PORV) in the B&W design. In response to I&E Bulletin 79-05B, the licensees lowered the existing setpoint for the high pressure reactor trip and raised the setpoint of the PORV. By inverting these setpoints the challenge rate to the PORV and thus the chance of it not reseating following actuation was reduced. To provide additional margin to the automatic opening setpoint, the licensees pmposed design provisions for direct reactor trip on loss of main feedwater or turbine trip. This design modification was approved and inco-, orated as part of the required actions of the Comission's Confinnatory Shutdown Orders issued in May 1979. In order to achieve mined that a " control-grade" design was short-term the licensees implemented har pendent of the reactor protection system were to be upgraded to safety-grade and DUPLICATE DOCUMENT As part of the long-term requirements, Entire document previously l designs for safety-grade reactor trips entered into system under: 1746 294 ^"o M /// # M No. of es: =_ _ _ _ _ _ _ _ _ _ _ _ _.. _ _ _ _ _ _. _.. _. _ _...}}