ML17298B780
| ML17298B780 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 11/28/1984 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| References | |
| NUDOCS 8501040222 | |
| Download: ML17298B780 (6) | |
Text
Docket Nos.:
50-528, 50-529 and 50-530 Mr. E.
E.
Van Brunt, Jr.
Vice President - Nuclear Projects Arizona Public Service Company
'ost Office Box 21666 Phoenix, Arizona 85036
Dear Mr. Van Brunt:
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DISTRIBUTION~ 0=525/529/530 NRC PDR L PDR NSIC PRC System LB¹3 Reading JLee PALicitra
- Attorney, OELD NGrace EJordan
Subject:
Request for Additional Information - Palo Verde Steam Generator Tube Rupture Analysis As a result of our review of the information you submitted by letter dated September 19, 1984, pertaining to the steam generator tube rupture analysis, the staff has determined that additional information is required.
The specific information needed is identified in the enclosed request and has been discussed with Mr. Terry Juan of your staff.
We ask that you provide an expeditious response to this request so that the staff can complete its review in a timely manner.
If you have any questions concerning this letter, you should contact Manny Licitra, the Licensing Project Manger.
Sincerely,
Enclosure:
As stated cc:
See next page George W. Knighton, Chief Licensing Branch No.
3 Division of Licensing DL:LB83Qg DL 3
EALicitra/yt G
ghton 11/pp/84 11/P/84 850i040222 84ii28 PDR ADOCK 05000528 A
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Palo Verde Mr. E.
E.
Van Brunt, Jr.
Vice President
- Nuclear Projects Arizona Public Service Company P. 0.
Box 21666 Phoenix, Arizona 85036 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 Counsel James A. Boeletto, Esq.
Southern California Edison Company P. 0.
Box 800
- Rosemead, California 91770 Ms. Margaret Walker Deputy Director of Energy Programs Economic Planning and Development Office 1700 West Washington Phoenix, Arizona 85007 Mr. Rand L. Greenfield Assistant Attorney General Bataan Memorial Building Santa Fe, New Mexico 87503 Kenneth Berlin, Esq."
Winston 5 Strawn Suite 500 2550 M Street, NW Washington, DC 20037 hl Ms. Lynne Bernabei Government Accountability Project of the Institute for Policy Studies 1901 Que Street, NW Washington, DC 20009 Ms. Jill Morrison 522 E. Colgate Tempi, Arizona 85238 Resident Inspector Palo Verde/NPS U.S. Nuclear Regulatory Commission P. 0.
Box 21324 Phoenix, Arizona 85001 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
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RE(VEST FOR ADDITIONAL INFORMATION PALO VERDE NUCLEAR GENERATING STATION UNITS 1,2, AND 3 STEAM GENERATOR TUBE RUPTURE ANALYSIS In the response to question 1, it states that feeding the affected steam generator is not a deviation from CEN-152.
Our position is that since the Palo Verde SG isolation strategy is different from the approved generic CEN-152 strategy, this is a deviation which should be justified.
For a steam generator tube'upture, initially the secondary side of the affected steam generator will be fed by both the primary-to-secondary side leak and feedwater.
This influx of water creates the potential for overfilling"the steam generator.
Discuss the information available to the operator to, prevent overfilling the steam generator and the sensitivity of the time period from the start of the accident to the time when there could be an overfill problem, assuming the operator does not take any action to prevent overfilling.
Alternately, show that the consequences of SG overfill are not significant.
Eyaluate the sensitivity of the time period the SG tubes could be uncovered to the i'ncrease in radiological consequences.
Relate this study to the amount of tube uncovery without credit for manual SG level control.
In your discussion of the steam generator tube rupture (Appendix), it states that 460 seconds (about 74 minutes) is the earliest possible time that the operator can take an adverse action.
The bases for this statement was given as reference to ANSI Standard N660.
Since the purpose of ANSI Standard N660's not to determine, the earliest time for operator to 'take "adverse" actions, our position is that inadequate bases h
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h ADV earlier than 460 seconds.
Therefore, determine the radiological consequences of the steam generator tube rupture with loss of offsite power assuming the operator opens an ADV on each steam generator at the earliest time possible that would result in the maximum radiological consequences.
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