ML13326A839
| ML13326A839 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/12/1992 |
| From: | Kalman G Office of Nuclear Reactor Regulation |
| To: | Ray H Southern California Edison Co |
| References | |
| TAC-M82616 NUDOCS 9202190221 | |
| Download: ML13326A839 (5) | |
Text
February 12, 1992
- ,Docket No. 50-206 Mr. Harold B. Ray DISTRIBUTION:
Senior Vice President Docket File NRC/Local PDRs ACRS(10)
Southern California Edison Company PDV r/f BBoger GPA/PA Irvine Operations Center MVirgilio TQuay OC/LFMB 23 Parker Street DFoster JBradfute PDV p/f Irvine, California 92718 GKalman OGC(15B18)
RegionV(4)
DHagan RZimmerman,RV GHill(4)
Dear Mr. Ray:
WJones CGrimes
SUBJECT:
CHANGES TO THE BASES SECTION OF THE UNIT 1 TECHNICAL SPECIFICATIONS (TAC No. M82616)
By letters dated October 4, 1991, and December 4, 1991, you proposed changes to the bases of the San Onofre Unit 1 Technical Specifications. We have reviewed the proposed changes and agree that the changes are desirable, they are administrative in nature, and do not change the requirements of the specifications.
Proposed changes included in the October 4, 1991,.letter consist of an addi tion to the basis section of Specification 4.1.9, "Auxiliary Feedwater System Surveillance."
The addition summarizes several operationally significant auxiliary feed pump testing requirements. The basis additions are testing requirements that are included in the existing Unit 1 inservice testing (IST) program.
Proposed changes included in the December 4, 1991, letter consist of an addi tion of a paragraph to the basis section of Specification 4.12, "Miscellaneous Radioactive Materials Sources."
The added paragraph clarifies requirements applicable to sealed sources that are enclosed within a shielded mechanism.
The paragraph had been part of the Technical Specifications previously but was inadvertently deleted during the processing of Amendment Request No. 168.
We have changed the basis sections of Specifications 4.1.9 and 4.12 as requested. The enclosed are copies of pages 4.1-29 and 4.12-1 with the revisions incorporated.
Sincerely, Original signed by George Kalman George Kalman, Sr. Project Manager Project Directorate V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/enclosure:
77--77)
See next page
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SBASESTS 9202190221 920212 PDR ADOCK 05000206 P __PDR
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 February 12, 1992 Docket No. 50-206 Mr. Harold B. Ray Senior Vice President Southern California Edison Company Irvine Operations Center 23 Parker Street Irvine, California 92718
Dear Mr. Ray:
SUBJECT:
CHANGES TO THE BASES SECTION OF THE UNIT 1 TECHNICAL SPECIFICATIONS (TAC No. M82616)
By letters dated October 4, 1991, and December 4, 1991, you proposed changes to the bases of the San Onofre Unit 1 Technical Specifications. We have reviewed the proposed changes and agree that the changes are desirable, they are administrative in nature, and do not change the requirements of the specifications.
Proposed changes included in the October 4, 1991, letter consist of an addi tion to the basis section of Specification 4.1.9, "Auxiliary Feedwater System Surveillance."
The addition summarizes several operationally significant auxiliary feed pump testing requirements. The basis additions are testing requirements that are included in the existing Unit 1 inservice testing (IST) program.
Proposed changes included in the December 4, 1991, letter consist of an addi tion of a paragraph to the basis section of Specification 4.12, "Miscellaneous Radioactive Materials Sources."
The added paragraph clarifies requirements applicable to sealed sources that are enclosed within a shielded mechanism.
The paragraph had been part of the Technical Specifications previously but was inadvertently deleted during the processing of Amendment Request No. 168.
We have changed the basis sections of Specifications 4.1.9 and 4.12 as requested. The enclosed are copies of pages 4.1-29 and 4.12-1 with the revisions incorporated.
Sincerely, George Ka man, Sr. Project Manager Project Directorate V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/enclosure:
See next page
Mr. Harold B. Ray San Onofre Nuclear Generating Southern California Edison Company Station, Unit No. 1 cc:
Mr. Phil Johnson Mr. Richard J. Kosiba, Project Manager U.S. Nuclear Regulatory Commission Bechtel Power Corporation Region V 12440 E. Imperial Highway 1450 Maria Lane, Suite 210 Norwalk, California 90650 Walnut Creek, California 94596 Mr. Robert G. Lacy Manager, Nuclear Department San Diego Gas & Electric Company P. 0. Box 1831 San Diego, California 92112 Resident Inspector/San Onofre NPS c/o U.S. Nuclear Regulatory Commission P. 0. Box 4329 San Clemente, California 92674 Mayor City of San Clemente 100 Avenida Presidio San Clemente, California 92672 Chairman, Board of Supervisors County of San Diego 1600 Pacific Highway, Room 335 San Diego, California 92101 Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Mr. John Hickman Senior Health Physicist Environmental Radioactive Mgmt. Unit Environmental Management Branch State Department of Health Services 714 P Street, Room 616 Sacramento, California 95814 Mr. Don J. Womeldorf Chief, Environmental Management Branch California Department of Health Services 714 P Street, Room 616 Sacramento, California 95814
4.12 MISCELLANEOUS RADIOACTIVE MATERIALS SOURCES APPLICABILITY: Applies to the leakage of radioactive source materials.
OBJECTIVE:
To verify the physical integrity of portable and fixed radioactive calibration sources.
SPECIFICATION: A. Byproduct material sealed sources which exceed the quantities listed in 10 CFR 30.71. Schedule B, and all other sealed sources containing greater than 0.1 microcuries shall be leak tested in accordance with Specification B, C and D below.
Exception:
Not withstanding the periodic leak test required by this specification, any licensed sealed source is exempt from such leak tests when the source contains 100 microcuries or less of beta and/or gamma emitting material or 10 microcuries or less of alpha emitting material.
B. Each sealed source containing radioactive material, other than Hydrogen 3, with a half life greater than thirty days and in any form other than gas, shall be tested for leakage and/or contamination prior to use out of storage and prior to transfer to another person and thereafter at intervals not to exceed six months. This test does not apply to sealed sources that are stored and not in use.
C. The leakage test shall be capable of detecting the presence of.005 microcuries of radioactive material.
The test sample shall be taken from the sealed source or from the surfaces of the device in which the sealed source is permanently mounted or stored on which one might expect contamination to accumulate.
D. If testing reveals the presence of.005 microcuries or more of removable contamination, it shall immediately be withdrawn from use, decontaminated, and repaired, or disposed of in accordance with applicable regulatory requirements and reported in the subsequent annual report filed pursuant to Specification 6.9.1.4.
BASIS:
This Specification assures that leakage from radioactive material sources does not exceed allowable total body or organ limits. In the unlikely event that those quantities of radioactive byproduct materials of interest to this Specification which are exempt from leakage testing are ingested or inhaled, they represent less than one maximum permissible body burden for total body irradiation. The limits for all other sources (including alpha emitters) are based upon 10 CFR 70.39 (c) limits for plutonium.
Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
SAN ONOFRE -
UNIT 1 4.12-1 AMENDMENT NO:
91, 130 REVISED BY NRC LETTER DATED:
FEBRUARY 12, 1992
pressure above 500 psig. The flow tests shall be conducted with the auxiliary feedwater system valves in their emergency alignment. Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after entering MODE 3, the steam driven auxiliary pump shall be similarly tested.
E. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 for the steam driven auxiliary feedwater pump. However, the steam driven AFW pump must be OPERABLE in all other respects.
BASIS:
The OPERABILITY of the auxiliary feedwater system ensures that the Reactor Coolant System can be cooled down to less than 350*F from normal operating conditions in the event of a total loss of offsite power.
The design of the auxiliary feedwater system further ensures sufficient AFW flow into the intact feedwater lines without exceeding pump run-out or water hammer limits for any applicable design basis event with or without concurrent loss of offsite power and a single active failure.(2,3)
Specification 4.1.9.A demonstrates the operability of the AFW pumps by testing requirements of the Seciton XI IST program.(4)
During normal power operation, pump G-10W is substantial flow tested and pumps G-10 and G-1OS are tested on minimum flow.
During this test differential pressure, pump speeds, and bearing vibration are measured for all 3 pumps. Pump discharge flow is measured for AFW pump G-10W. At each return from a MODE 3, 4, or 5 shutdown following power operations, pumps G-10 and G-10S are full flow tested unless tested in the previous 92 days. G-10S is tested prior to MODE 3. G-10 is tested in MODE 1 at about 20%
power.
REFERENCES:
(1) NRC letter dated July 2, 1980, from D. G. Eisenhut to all pressurized water reactor licensees.
(2) SCE letter dated November 6, 1987, from M. 0. Medford to NRC Document Control Desk.
(3) SCE letter dated November 20, 1987, from M. 0. Medford to NRC Document Control Desk.
(4) SCE letter dated January 3, 1991, from F. R. Nandy to NRC Document Control Desk.
SAN ONOFRE - UNIT 1 4.1-29 AMENDMENT NO: 65, 82, 125, 130 REVISED BY NRC LETTER DATED:
FEBRUARY 12, 1992