ML17310A563
| ML17310A563 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 08/19/1993 |
| From: | Murley T Office of Nuclear Reactor Regulation |
| To: | Conway W ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| Shared Package | |
| ML17310A564 | List: |
| References | |
| NUDOCS 9309030060 | |
| Download: ML17310A563 (9) | |
Text
~8 REQII P0 Cy nO IIA IP ++*++
UNITED STATES NUCLEAR REGULATORY COMlVllSSlON WASHINGTON, D.C. 20555-0001 August 19, 1993 Docket Nos. 50-528, 50-529 and 50-530 Mr. William F.
Conway Executive Vice President, Nuclear Arizona Public Service Company P.O.
Box 53999
- Phoenix, Arizona 85072-3999
Dear Mr. Conway:
SUBJECT:
RESTART OF PALO VERDE UNIT NO.
2 AND REQUEST FOR INFORMATION UNDER 10 CFR 50.54(f)
REGARDING STEAM GENERATOR TUBES PALO VERDE NUCLEAR GENERATING STATION, UNIT NOS.
1, 2, AND 3 We have completed our review of your letter of July 18,
- 1993, which provided your Unit 2 Steam Generator Tube Rupture Analysis Report, and information contained in supplemental letters dated July 25 and 30, and August 5
and 9, 1993.
Based on this review, discussed more fully in the enclosed Safety Evaluation (Enclosure 1),
we have concluded that Unit 2 can safely resume operation for six months before the next steam generator tube inspection, as proposed.
After consultation with NRC Region V, we have also concluded that the commitments contained in your letter of June 2,
- 1993, and NRC's confirmation letter of June 4, 1993, regarding NRC concurrence with restart of the facility and other matters, have been satisfied.
The NRC therefore has no objection to the restart of the Unit 2 facility.
The Arizona Public Service Company (APS) letter of July 25, 1993, provided your safety assessment of continued operation of Palo Verde Units 1 and 3 with potentially degraded steam generator tubes.
This assessment included a
comparative assessment of the Palo Verde Unit 1 and 3 steam generators with the Palo Verde Unit 2 steam generators.
Whereas your letter identified several differences between Units 1 and 3 and Unit 2 which may, when considered collectively, provide a basis for a conclusion that tube degradation may not be as severe on these other units, we see substantial similarities among all the units.
Our detailed comments on your July 25, 1993, letter are contained in Enclosure 2.
We have no objection to the continued operation of Unit 1 for the next two weeks because you have implemented the same improvements on Units 1 and 3 as you have on Unit 2, as explained in the enclosed Safety Evaluation for Unit 2.
The NRC staff has no objection to the continued operation of Unit 3, pending the results of the steam generator tube inspection of Unit 1 commencing about September 24, 1993.
This inspection will provide important information regarding the appropriate steam generator tube inspection schedule and scope for Unit 3.
Because of the substantial uncertainties in steam generator tube crack initiation times and crack growth rates, and to determine if any modification of your licenses is appropriate, the NRC needs to review in detail the steam pDR
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Conway generator tube inspection plans for the upcoming Unit 1 inspection, the inspection plans for the Unit 2 mid-cycle inspection, and other items identified in the enclosed Request for Additional Information (Enclosure
- 3) to ensure that steam generator tube integrity will be maintained during operation.
This information is requested pursuant to 10 CFR 50.54(f) of the Commission's regulations, and is sought by the NRC to determine whether or not additional action by NRC is necessary with respect to the operating interval for Unit 1 (after startup from the September 1993 outage),
the operating interval for Unit 2 following the mid-cycle inspection at the end of six months of operation, and continued operation of Unit 3 through its next refueling scheduled for Harch 1994.
In making this request, I have determined that the burden to be imposed in responding is justified in view of the potential safety significance of the issues to be addressed in the requested information.
It must be submitted as specified in Section 50.4, "Written communications,"
and signed under oath or affirmation.
Information regarding the upcoming steam generator tube inspection on Unit 1 must be submitted within 30 days of the date of this letter; the balance of the information must be submitted within 90 days of the date of this letter or as stated in the specific items identified in Enclosure 3.
This requirement affects fewer than ten respondents; therefore, it is not subject to Office of Management and Budget review under Public Law 96-511.
Sincerely, 7/8 Thomas E. Hurley, Director Office of Nuclear Reactor Regulation'nclosures:
- 1. Safety Evaluation 2.
Comments on July 25, 1993 letter
- 3. Request for Additional Information cc w/enclosures:
See next page
'Nr. William F. Conwa~
generator tube inspection plans for the upcoming Unit 1 inspection, the inspection plans for the Unit 2 mid-cycle inspection, and other items identified in the enclosed Request for Additional Information (Enclosure
- 3) to ensure that steam generator tube integrity will be maintained during operation.
This information is requested pursuant to 10 CFR 50.54(f) of the Commission's regulations, and is sought by the NRC to determine whether or not additional action by NRC is necessary with respect to the operating interval for Unit 1 (after startup from the September 1993 outage),
the operating interval for Unit 2 following the mid-cycle inspection at the end of six months of operation, and continued operation of Unit 3 through its next refueling scheduled for March 1994.
In making this request, I have determined that the burden to be imposed in responding is justified in view of the potential safety significance of the issues to be addressed in the requested information.
It must be submitted as specified in Section 50.4, "Written communications,"
and signed under oath or affirmation.
Information regarding the upcoming steam generator tube inspection on Unit 1 must be submitted within 30 days of the date of this letter; the balance of the information must be submitted within 90 days of the date of this letter or as stated in the specific items identified in Enclosure 3.
This requirement affects fewer than ten respondents; therefore, it is not subject to Office of Management and Budget review under Public Law 96-511.
Sincerely, Original signed b'g Thomas E. Hurley, Director Office of Nuclear Reactor Regulation
Enclosures:
- 1. Safety Evaluation 2.
Comments on July 25, 1993 letter 3.
Request for Additional Information cc w/enclosures:
See next page DISTRIBUTION:
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Conway generator tube inspection plans for the upcoming Unit 1 inspection, the inspection plans for the Unit 2 mid-cycle inspection, and other items identified in the enclosed Request for Additional Information (Enclosure
) to ensure that, steam generator tube integrity will be maintained during operation.
This information is requested pursuant to 10 CFR 50.54(f) of the Commission's regulations, and is sought by the NRC to verify compli ce with the current licensing basis of the Palo Verde facility. It must b
submitted as specified in Section 50.4, "Written communications,"
and sign under oath or affirmation.
Information regarding the upcoming steam gener tor tube inspection on Unit 1 must be submitted within 30 days of the g te of this letter; the balance of the information must be submitted wi ti'in 90 days of the date of this letter or as stated in the specific items ide ified in Enclosure 3.
This requirement affects fewer than ten re
- ondents, therefore, is not subject to Office of Management and Budget revie under Public Law 96-511.
Sincerely, Jack W.
Roe
- Director, Division o Reactor Projects III/IV/V Office o Nuclear Reactor Regulation
Enclosures:
- 1. Safety Evaluation 2.
Comments on July 25, 1993 letter
- 3. Request for Additional Informatio cc w/enclosures:
See next page DISTRIBUTION:
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Mr. William F.
Conway Arizona Public Service Company Palo Verde CC:
Hr. Steve Olea Arizona Corporation Commission 1200 W. Washington Street
- Phoenix, Arizona 85007 James A. Beoletto, Esq.
Southern California Edison Company P. 0.
Box 800
- Rosemead, California 91770 Senior Resident Inspector Palo Verde Nuclear Generating, Station 5951 S. Wintersburg Road
- Tonopah, Arizona 85354-7537 Regional Administrator, Region V
U. S. Nuclear Regulatory Commission 1450 Maria Lane Suite 210 Walnut Creek, California 94596 Hr. Charles B. Brinkman, Hanager Washington Nuclear Operations ABB Combustion Engineering Nuclear Power 12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 Hr. Aubrey V. Godwin, Director Arizona Radiation Regulatory Agency 4814 South 40 Street
- Phoenix, Arizona 85040 Chairman Haricopa County Board of Supervisors ill South Third Avenue
- Phoenix, Arizona 85003 Jack R.
- Newman, Esq.
Newman 5 Holtzinger, P.C.
1615 L Street, N.W., Suite 1000 Washington, D.C.
20036 Hr. Curtis Hoskins Executive Vice President and Chief Operating Officer Palo Verde Services 2025 N. 3rd Street, Suite 220
- Phoenix, Arizona 85004 Roy P.
Lessey, Jr.,
Esq.
Bradley W. Jones, Esq.
Akin, Gump, Strauss, Hauer and Feld El Paso Electric Company 1333 New Hampshire Ave., Suite 400 Washington, D.C.
20036 Hr. Thomas R. Bradish, Manager Nuclear Regulatory Affairs Arizona Public Service Company P. 0.
Box 52034
- Phoenix, Arizona 85072-2034
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