ML17303A206
| ML17303A206 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/30/1986 |
| From: | Licitra E Office of Nuclear Reactor Regulation |
| To: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| Shared Package | |
| ML17303A207 | List: |
| References | |
| REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR NUDOCS 8701080149 | |
| Download: ML17303A206 (12) | |
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:
OEc s0)MN DISTRIBUTION PD7 Reading NRC PDR LPDR JLee EALicitra MDavis EJordan BGrimes
SUBJECT:
FRACTURE TOUGHNESS REQUIREMENTS FOR PALO VERDE REACTOR PRESSURE VESSEL By letter dated January 17, 1986, you submitted information on the material properties and the fast neutron fluence for the three Palo Verde reactor pressure vessels in compliance with the requirements of 10 CFR 50.61.
The staff has completed its review of your submittal and has determined that each of the reactor pressure vessels for Palo Verde, Units 1, 2 and 3 meets the toughness requirements of 10 CFR 50.61 for 32 effective full power years of operation.
The details of the staff's evaluation are presented in the following enclosures.
Enclosures 1 and 2 provide the evaluation of the fast neutron fluence for Palo Verde Unit 1 and for Palo Verde Units 2 and 3, respectively.
Enclosure 3
provides the evaluation of the material properties for all three units.
As stated in Enclosures 1 and 2, we request that at the time you submit future pressure-temperature operating limits for each reactor pressure
- vessel, as required by Appendix G to 10 CFR Part 50, you include a re-evaluation of the RT and a comparison to the prediction in your January 17, 1986 submittal.
lt Bould be noted that this reevaluation is a requirement of 10 CFR 50.61, whenever core loadings, surveillance measurements, or other information indicate a significant change in projected values.
If you have any questions regarding this letter, please let me know.
Sincerely,
, 870i080i49 861230 PDR ADOCK 05000528 P
Enclosures:
As stated cc:
See next page Bg>>pj5s P07f/'B DI 'PD7 EALicitra/yt DC ield GWKnighton 12/P/86 12//$ /86 12/tgt/86 E. A. Licitra, Project Manager PWR Project Directorate No.
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Mr. E. E.'an Brunt, Jr.
Arizona Nuclear Power Project Palo Verde CC:
Arthur C. Gehr, Esq.
Snell 8 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. Hark Ginsberg Energy Director Office of Economic Planning and Development 1700 West Washington - 5th Floor Phoenix, Arizona 85007 Mr. Wayne Shirley Assistant Attornev 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 Coranission 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 Que 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 1330
- Bethesda, Maryland 20814
L C,
C I
Fnclosure 1
PALO VERDE UNIT 1, FAST NEUTRON FLUENCE FOR FRACTURE TOUGHNESS REQUIREMENTS FOR PROTECTION AGAINST PRESSURIZED THERMAL SMOCK EVENTS (10 CFR 50.61)
The equation specified in 10 CFR 50.61, as applicable for the Palo Verde Unit 1
plant is:
RTPTS I+M+( 10+470xCu+350xCuxNi)xf 0.27 where:
I = Initial RTN >
= 30'F M = Uncertaintv margin
= 48'F Cu
= w/o Copper in Plate M-6701-1 0.07 Ni
= w/o Nickel in Plate M-6701-1
= 0.66 f = peak azimuthal fluence for 32 effective full pgwer years (E 01.0 MeV) in units of 10 n/cm
= 6.3 Therefore:
RTPTS 30+48+(
10+470x0. 07+350x0 ~ 07x0 ~ 66) x6 ~ 30.27
= 78+39x1.64
= 78+64.2
= 142.2'F By letter dated January 17, 1986, Arizona Public Service
- Company, licensee for the Palo Verde Unit 1 plant, submitted information on the material properties and the fast neutron fluence (E >1.0 MeY) of the reactor pressure vessel in compliance with the requirements of 10 CFR 50.61.
The staff reviewed the pressure vessel material properties and found them acceptable (Enclosure 3)
The following evaluation concerns the estimation of the fluence to the pressure vessel for 32 effective full power years of operation and the corresponding value of RTPTS.
The fluence estimate in the FSAR was used for this evaluation.
That estimate was performed with a discrete ordinates code.
- However, because of the extremely low content of Cu in the plates and the welds of the Palo Verde pressure vessel and the resulting very large margin for the PTS limit,the initial flux estimate was doubled to account for potential uncertainties.
In addition, the amounts of Cu and Ni used were the bounding values of the chemical analyses (Enclosure
- 3) which adds conservatism.
The fluence estimate is very conservative and acceptable.
which is much lower than 270'F, the applicable 10 CFR 50.61 screening criterion~
and is acceptable.
e'L I
In view of:
(a>
The Pressure-Temperature updatinq requirements for the fracture touahness of the beltline material in 10 CFR 50 Appendix G, and (b) the fact that the RT T value is readily available from the calculation of the Pres s ure Temp Vr)ture limits, a nd (c) the staff desire to be informed on the current value of the RTPTS for all
comparison to the prediction of its January 17, 1'986 suhmittaPalono with the future Pressure-Temperature operating limits which are required by 10 CFR 50 Appendix G.* It should be noted that this reevaluation is a requirement by 10 CFR 50.61, whenever core loadinqs, surveillance measurements, or other information indicate a significant change in pro,iected values.
- This request for information is covered under OMB clearance No. 3150-0011.
Enclosure 2
PALO VERDE UNITS 253, FAST NEUTRON FLUENCE FOR FRACTURE TOUGHNESS RE(UIREMENTS FOR PROTECTION AGAINST PRESSURIZED THERMAL SHOCK EVENTS (10 CFR 50.61)
By letter dated January 17, 1986, Arizona Public Service
- Company, licensee an'd applicant for Palo Verde Units 253, submitted information on the material properties and the fast neutron fluence (E) 1.0 MeV) of the reactor pressure vessel in compliance with the requirements of 10 CFR 50.61.
The staff reviewed the pressure vessel material properties and found them acceptable (Enclosure 3).
The following evaluation concerns the estimation of the fluence to the pressure vessel for 32 effective full power. years of operation and the, corresponding value R
pTS'he fluence estimate in the FSAR was used for this evaluation.
That estimate was performed with a discrete ordinates code.
- However, because of the extremely low content of Cu in the plates and the welds of the Palo Verde pressure vessel and the resulting very large margin for the PTS limit,the initial flux estimate was doubled to account for potential uncertainty.,
In addition, the amounts of Cu and Ni used were the bounding values of the, chemical analyses (Enclosure
- 3) which adds more conservatism.
The fluence estimate is very conservative and acceptable.
The values used in the evaluation of Unit 1 are bounding and have been proposed for Units 2 and 3.
The equation specified in 10 CFR 50.61, as applicable for palo Verde Units 283 is:
RTPTS I 6+(
10+470xCu+350xCuxNi )xfOe27 where:
I Initial RT D
n UncertatntPkargln Cu w/o Copper Ni w/o Nickel f
peak azimuthal fluence for 32 effective full ~~wer years (E > 1.0 MeV) in units of 10 n/cm'herefore:
RTPTS
~ 30+48+(-10+470x0.07+350x0.07x0.66)x6.3 78<39x1.64
~ 78+64.2 =142.2'F
~ 30'F 8oF
~ 0.07
~ Oe66 which is much lower than 270'F, the applicable 10 CFR 50.61 screening criterion, and is acceptable.
I t
In view of:
(a>
The Pressure-Temperature updatinq requirements for the fracture touohness of the beltline material in 10 CFR 50 Appendix G, and (b) the fact that the RT T value is readily available from the calculation of the Pressure Temp)r)ture limits, and (c) the staff desire to be informed on the current value of the RTPT> for all
comparison to the prediction of its January 17, 1986 submittaPalonu with the future Pressure-Temperature operating limits which are required by 10 CFR 30 Appendix G.* It should be noted that this reevaluation is a requirement by 10 CFR 50.61, whenever core loadinqs, surveillance measurements, or other information indicate a significant change in proiected values.
- This request for information is covered under ONB clearance No. 3150-0011.
jf