ML17300A629
| ML17300A629 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 11/13/1986 |
| From: | Licitra E Office of Nuclear Reactor Regulation |
| To: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| References | |
| NUDOCS 8611180081 | |
| Download: ML17300A629 (5) | |
Text
Docket No.:
50-530 NOV 3.8@/
DI RIBUTION 4.
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:
oc et 1
e NRC PDR LPDR NSIC PD7 Reading JLee MDavis EALicitra EJordan BGrimes
NThompson
SUBJECT:
REQUEST FOR SUPPLEMENTAL INFORMATION - PALO VERDE UNIT 3, FOR RCS PRESSURE-TEMPERATURE LIMITS DURING HEATUP AND COOLDOWN Submittal of the Unit 3 Technical Specifications is expected in the near future.
To facilitate the staff's review of the TS concerning RCS Pressure-Temperature limits during heatup and cooldown some supplemental information will be required.
The specific information needed by the staff to complete the evaluation is identified in the attached enclosure.
We ask that you provide the requested information by December 31, 1986.
If you have any questions regarding this letter please contact Michael Davis at (301)-492-8897.
Sincerely,
/~/
E. A. Licitra, Project Manager PWR Project Directorate No.
7 Division of PWR Licensing-B
Enclosure:
As stated cc:
See next page PD7 MDavis yt ll/io/ 6 PD7 D
D7 EALicitra ighton 11//~/86 11 i~86 8bl1180081 8b1113 PDR ADOCK 05000530 PDR
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, Cali fornia 91770 Mr. Mark Ginsberg Energy Director Office of Economic Planning and Development 1?00 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 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 Mr. Ron Rayner P. 0.
Box 1509
- Goodyear, AZ 85338 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations Combustion Engineering, Inc.
7910 Woodmont Avenue Suite 1310
- Bethesda, Maryland 20814 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
gr Encl osur e RE VEST FOR ADDITIONAL INFORMATION PALO VERDE UNIT 3 REACTOR PRESSURE VESSEL PRESSURE-TEMPERATURE LIMITS TECHNICAL SPECIFICATIONS 3/4.4.8 ENGINEERING BRANCH DIVISION OF PWR LICENSING-B 1.
Please provide the data with regard to the reactor pressure vessel (RPV) Pressure-Temperature Limits.
a.
Is the limiting material a base metal, a circumferential weld or a longitudinal weld?
I b.
Identify the limiting (controlling) material and its Cu and Ni content.
c.
What inside surface neutron fluence (E>1MeV) at 10 EFPY and EOL was used with the limiting material?
d.
What is the actual initial RTNDT for the limiting material.
e.
What is the standard deviation of the initial RTNDT (aI) for the limiting material?
f.
What is the standard deviation of 6 RTNDT (o<) for the limiting material?
g.
What value of temperature measurement error was used?
h.
What is the hydrostatic head at the location of the limiting material?
i.
What value of pressure measurement error was used?
j.
What is the actual initial RTNDT for the reactor vessel flange?
k.
What are the calculated values of the adjusted reference temperature for the limiting (controlling) material at the 1/4t and 3/4t locations?
1.
What are the calculated values of the neutron fluence at the I/4t and 3/4t locations?
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t
2.
Please confirm the validity of the following values, used by the staff in the calculation of the reactor vessel Pressure-Temperature Limits:
a.
Reactor pressure vessel (RPV) inner diameter of 91.125 inches, outer diameter of 100. 1875 inches and thickness of 9.0625 inches.
b.
C.
d.
e.
An RPV design pressure of 2500 psia.
An RPV operating pressure of 2250 psia.
A boltup temperature of 68OF.
A lowest service temperature of 180 F.
A maximum service pressure of 500 psia.