ML17300A318
| ML17300A318 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 07/30/1986 |
| From: | Licitra E Office of Nuclear Reactor Regulation |
| To: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| References | |
| NUDOCS 8608110197 | |
| Download: ML17300A318 (8) | |
Text
Docket Nos.:
50-528, 50-529 and 50-530 Mr. E.
E.
Van Brunt, Jr.
Executive Vice President Arizona Nuclear Power Project Post Office Box 52034 Phoenix, Arizona 85072-2034
Dear Mr. Van Brunt:
JUL 30586 DISTRIBUTION LPDR NRC PDR PD7 Reading EALicitra JLee JPartlow BGrimes EJordan
LBeltracchi REckenrode
Subject:
Request for Additional Information - Safety Parameter Display System for Palo Verde By letter dated March 14, 1986, you provided information relating to isolation devices that separate the Safety Parameter Display System and safety grade sensors.
The staff's technical evaluation of this information is enclosed.
As noted in the enclosure, the technical evaluation is incomplete since the test data presented to demonstrate the functional performance of the isolation devices were determined to be inadequate.
The specific information needed by the staff to complete the evaluation is identified in the enclosure.
We ask that you provide the requested information by September 1,
1986. If you have any questions regarding this letter, please let me know.
Sincerely, ORlGlRALSlG~qEO gy E. A. Licitra, Project Manager PWR Project Directorate No.
7 Division of PWR Licensing-B
Enclosure:
As stated cc:
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Mr. E.
E.
Van Brunt, Jr.
Arizona Nuclear Power Project Palo Verde CC:
Arthur C. Gehr, Esq.
Snell
& Wilmer 3100 Valley Center Phoenix, Arizona 85073 Mr. James M. Flenner, Chief Counsel Arizona Corporation Commission 1200 West Washington Phoenix, Arizona 85007 Charles R. Kocher, Esq. Assistant Council James A. Boeletto, Esq.
Southern California Edison Company P. 0.
Box 800
- Rosemead, Ca 1 iforni a 91770 Mr. Yiark Ginsberg Energy Director Office of Economic Planning and Development 1700 West Washington - 5th Floor Phoenix, Arizona 85007 Mr. Wayne Shirley Assistant Attorney General Bataan Memorial Building Santa Fe, New Mexico 87503 Mr. Roy Zimmerman U.S. Nuclear Regulatory Commission P. 0.
Box 239 Arlington, Arizona 85322 Ms. Patricia Lee Hourihan 6413 S. 26th Street Phoenix, Arizona 85040 Regional Administrator, Region V
U. S. Nuclear Regulatory Commission 1450 Maria Lane Suite 210 Walnut Creek, California 94596 Kenneth Berlin, Esq.
Winston 5 Strawn Suite 500 2550 M Street, NW Washington, DC 20037 Ms. Lynne Bernabei Government Accountability Project of the Institute for Policy Studies 1901 gue Street, NW Washington, DC 20009 Ms. Jill Morrison 522 E. Colgate Tempi, Arizona 85238 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations Combustion Engineering, Inc.
7910 Woodmont Avenue Suite 1310
- Bethesda, Maryland 20814 Mr. Ron Rayner P. 0.
Box 1509
- Goodyear, AZ 85338
TECHNICAL EVALUATION REPORT PALO VERDE NUCLEAR GENERATING STATION SAFETY PARAMETER DISPLAY SYSTEM ENCLOSURE I.
BACKGROUND All operating reactors are required to have a Safety Parameter Display System (SPDS).
The Commission-approved requirements for the SPDS are defined in NUREG-0737, Supplement
'1.
These requirements and the staff's review of the SPDS were discussed in the Regional workshops on Generic Letter 82-33 held during March 1983.
The Arizona Nuclear Power Project (ANPP), the licensee for the Palo Verde Nuclear Generating Station, Units 1, 2, and 3
submitted a letter (Reference
- 1) in response to staff concerns and questions forwarded to the licensee in a letter dated January 10, 1986 (Reference 2).
II.
EVALUATION ANPP responded to six questions from the NRC staff.
This response was incomplete, and addressed only a Hi-Pot test and a Surge Withstand Capability (SWC) test, which were performed on both their analog and their digital isolators.
The response did not address a test involving application of the maximum credible fault (MCF) in the transverse mode to the non-1E ou'tput of the isolator.
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~ The staff requires that an MCF test, using the MCF voltage and current, be conducted on all electrical isolators used to isolate the SPDS from safety-related systems.
The MCF voltage/current is to be applied in the transverse mode to, the plus and minus output terminals of the isolator while the Class 1E input to the isolator is monitored for evidence of degradation.
The.transverse mode test using MCF voltage and current is addressed in IEEE 279-1971 and IEEE 384-1981.
Because ANPP did not address the MCF test in their earlier submittal, their responses to the six questions posed by the NRC must be re-submitted.
This new submittal must address appli-r cation of the MCF to the output of the isolation device.
III.
CONCLUSION The licensee ghoul'd adequately demonstrate that.all of.the different types of isolators used in Units 1, 2, and 3 have been tested with the MCF voltage/current and submit supporting data to the NRC. In addition, the licensee rhymed supplement the answers to the six questions posed in Reference 7.,
and address the application of MCF.
IV.
REFERENCES 1.
E. E. VanBrunt, Jr.,
ANPP, letter to G.
W. Knighton, NRC, dated March 14, 1986.
2.
E.. 'A.. Licitra, NRC, letter to E.
E. VanBrunt, Jr.,
ANPP, dated January 10, 1986.
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