ML17299A918
| ML17299A918 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 01/07/1986 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| References | |
| GL-83-28, TAC-59169, TAC-59170, NUDOCS 8601150578 | |
| Download: ML17299A918 (11) | |
Text
Docket los.:
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:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - PALO VERDE RESPONSES TO ITEMS 4.1, 4.2. 1 and 4.2.2 IN GENERIC LETTER 83-28 Your response to Generic Letter 83-28 was provided by letter dated November 3, 1983.
As a result of the staff's review of your responses to Items 4.1, 4.2.1 and 4.2.2 in the generic letter, we require additional information to complete our evaluation of these items.
The specific information required is identified in the enclosed request for additional information.
We ask that you respond to this request by Feburary 28, 1986.
If you have any questions regarding this letter, you should contact Mr.
E. Licitra, the Licensinq Project Manager.
Sincerely,
Enclosure:
As stated cc:
See next page Distribution Docket-Fi:le 50-528/529/530 NRC PDR Local PDR PD7 Reading G.
W. Knighton OELD PD7 g PD7
'EAL ci"t a/es GWKnig ton 1/g /86 1/ (/86 George W. Knighton, Director PWR Project Directorate No.
7 Division of PWR Licensing-B E. Jordan B. Grimes J. Partlow E. A. Licitra J.
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Mr. E. E.
Van Brunt, Jr.
Arizona Nuclear Power Project Palo Verde CC:
Arthur C. Gehr, Esq.
Snell 5 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, California 91770 Mr. Mark 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 8 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
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4
ENCLOSURE PALO VERDE NUCLEAR GENERATING STATION PVNGS UNITS 1
2 AND 3 RE VEST FOR ADDITIONAL INFORMATION GL 83-28 ITEMS 4. 1 4.2. 1 AND 4.
2.2 INTRODUCTION
Arizona Public Service
- Company, the applicant for Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3, submitted their response to Generic Letter 83-28 on November 3, 1983.
That response has been reviewed with respect to Items 4. 1, 4.2. 1 and 4.2.2 of the Generic Letter.
The applicant response was not sufficiently detailed to permit an evaluation of the adequacy of the periodic maintenance and trending programs for the breakers.
The following additional information is required to evaluate compliance with Items 4. 1, 4.2. 1 and 4.2.2.
I.
Item 4. 1 - Reactor Trip System Reliability (Vendor-Related Modifications)
The applicant should address his position with regard to the ball bearing change as recommended by General Electric Service Advice 9.20, dated March 21, 1984
'I.
Item 4.2. 1 - Periodic Maintenance Program for Reactor Trip Breakers.
Criteria for Evaluatin Com liance with Item 4.2. 1 Palo Verde Nuclear Generating Station Reactor Trip Systems utilize General Electric AK-2A circuit breakers.
The primary criteria for an acceptable maintenance program for this breaker are contained in Maintenance Instruction GEI-50299EI*, "Power
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Circuit Breakers, Types AK-2/2A-15, AK-2/3/2A/3A-25, AKU-2/3/2A/3A-25," and Service Advices 9.3S and 9.20, by General Electric.
The NRC Staff, Equipment gualification Branch, has reviewed these items and endorsed the maintenance program they describe.
More specifically, the criteria used to evaluate compliance include those items in the General Electric instructions and advisories that relate to the safety function of. the breaker, supplemented by those measures that must be taken to accumulate data for trending.
The acceptable maintenance activity interval is six months.
Issues Relatin to Item 4.2. 1 The applicant response states that his maintenance and surveillance programs for the reactor trip breakers are being developed and should be approved by December 1,
1983.
The NRC 1
has not received these programs as of April 1985.
The applicant periodic maintenance program for the reactor trip breakers should include, on a six month basis:
1.
Verification of breaker cleanliness and insulation structure; all foreign materials, such as paint, dust, or oil, should be removed to prevent electrical'reakdown between points of different potential; 2.
Verification of breaker, physical condition, including wiring insulation and termination, all retaining r
- rings, pole bases, arc quencher, stationary and movable contacts, and tightness of nuts and bolts; Verification of proper manual operation of the
- breaker, including checks for excessive friction, trip bar freedom, latch engagement, operating mechanism alignment and freedom, and undervoltage trip (UVT) device armature freedom;
4.
Verification of the optimum freedom of the armature as specified in General Electric Service Advice 175-9.3S, Item ¹Sl; 5.
Verification of proper trip latch engagement as specified in Service Advice 175-9.3S, Item ¹S2; 6.
Verification of undervoltage pick-up setting, as specified in Service Advice 175-9.3S, Item ¹S3, and dropout voltage; 7.
Verification that the trip torque required on the trip shaft is less than 1.5 pound-inches, as specified in Service Advice 175-9.3S, Item ¹S4; "Before" and "After" maintenance torque values should be recorded; 8.
Verification of positive tripping by checking the adjustment between the UVT device and trip paddle as specified in Service Advice 175-9.3S, Item ¹SS; 9.
Verification of proper trip response time as specified in Service Advice 175-9.3S, Item ¹S6; 10.
Shunt Trip Attachment (STA) operation verification; 11.
Examination and cleaning of breaker enclosure;,
12.
Functional test of the breaker prior to returning it to service.
The applicant is to confirm that the periodic maintenance program includes these 12 items at the specified interval or commit to their inclusion.
L
III.
Item 4.2 '
Trending of Reactor Trip Breaker Parameters to Forecast Degradation of Operability.
Criteria for Evaluatin Com liance with Item 4.2.2 Four parameters have been identified as trendable and are included in the criteria for evaluation.
These are (I) undervoltage trip attachment dropout voltage, (2) trip
- torque, (3) breaker response time for undervoltage trip, and (4) breaker insulation resistance.
Issues Relatin to Item 4.2.2 The applicant states in his submittal that the Maintenance Engineering Department has the responsibility for review of 1
Reactor Trip Breaker maintenance and surveillance results for the purpose of forcasting operability degradation by trending measured parameters..
The applicant is to commit to inclusion of trip torque, breaker response time and dropout voltage for undervoltage trip and breaker insulation resistance as trending parameters.
The applicant should also identifyhow often the analysis will be performed and how the information derived from the'nalysis will be used to affect periodic maintenance.
37449
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