ML17299A967
| ML17299A967 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 01/17/1986 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR ANPP-34670-EEVB, TAC-59971, TAC-63197, NUDOCS 8601240189 | |
| Download: ML17299A967 (12) | |
Text
REGULATOR NFORtiATION DISTR IBUT'ION 8 EH (RIDS)
ACCESSION NOR: Bb01240189 DOC. DATE: 86/01/24 NOTARIZED:
NO DOCKET 0 FACIE.;.STN-50-528 Palo Verde Nuclear Stationi Unit ii Arizona Pub 1 i 05000528 STN-50-529 Palo Verde Nuc lear Station>
Unit 2i Arizona Pub 1 i 05000529 STN-50-530 Palo Verde Nuclear Stationi Unit 3i Arizona Publi 05000530 AUTH. NANE AUTHOR AFFILIATION VAN BRUNT'. E-Arizona Nuclear Power Pro Ject (formerly Arizona Public Serv REC IP. MANE REC IP IEN I AFFILIATION KNIGHTON> C. W.
PWR Propre'ct Directorate
'7 SUB JECT:
Submits int o in response to 10CFR50. 61'Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events. "
FSAR peak fluence predictions used to calculate ref temp values.
DISTRIBUTION CODE:
A049D COPIES RECEIVED: LTR ENCL SIZE:
TITLE:
OR Submittal:
Thermal Shock to Reactor essel NOTES: Standardized plant.
OL: 12/31/8e Standardized plant.
Standardized p lant.
05000528 05000529 05000530 REC IP IEN1 ID CODE/M."PtE PWR-8 ADTS LEYTE N COPIES LTTR E 'CL 1
1 RECIPIENT ID CODE/NAME PWR-8 PD7 PD 01 LICITRAi E COPIES LTTR ENCL INTERNAL: ACRS ELD/HDS3 NR FRi C REG FILE RGN1 ADNBTR 10 12 05 ADN/LFNB NRR LOISz L NRR VISBING> G04 RES RANGALL>P RGN5 EXTERNAL'4X NRC PDR LPDR NSIC 03 06 QQT acus QKSS g5 Q.R~~
'0 TOTAL NUNBER OF COPIES REQUIRED:
LTTR ENCL
~
v
~
(I 4
Pl
~ll I
v 4
I eF CC v
ll V>>
iL!68 "iQ> llAT, T.F I'TI,4 4 4 P
IVC I "I v
~ =
f."l'. -*',
II Jl 0 CEE Eq yU4'"f T
4"I
/I J'qt>
"jgg f.
I'q l,l I~
4 QI CVC v; 'll I IV>> ~ 'v 4 l.'.
",)"
QECC
)I6 PI/.'
Iz,'.Cf I J ~
'v'II 4.
i~ +~
I' 4 d t I3 I'EPF ll '$
lt vol PC R Cl9'.0 FC,'041 C/P C, C @ P 4
C 'J ll It'.,
~
4'I Cltg $
St< ll 4
I C'F I g
Q 4 0 X'.
3 O'X"-',.)',
I C
F 4
II Iv PI I, b "fGPOCvli~
Ci)4'gJV)"Flit
)Evyi ~
XQ C.'i
~4 I' GJf
(~
s i>>A J
C,:,D.
~
Pili +
'Il
~
EVV I V V
-'l i.j llr>'"Si ~~
4 I
CE IIl HA.>44 g, '."," l I IIXT'iJ -I
">RP t.g JX,~.$j
,) i" PC'j 4 4
Arizona Nuclear Power Project P.o. BOX 52034
~
PHOENIX, ARIZONAB5072-2034 Director of Nuclear Reactor Regulation Attention:
Mr. George W. Knighton, Deputy Director PWR Project Directorate 4'7 Division of Pressurized Water Reactor Licensing B U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2, and 3
Docket Nos.
STN-50-528 (License NPF-41)
STN-50-529 (License NPF-46)
STN-50-530 Pressurized Thermal Shock File: 86-056-026
References:
(1) 10 CFR 50.61 "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events".
(2) CEN-189, Appendix J, Evaluation of Pressurized Thermal Shock Effects for Palo Verde 1, 2, and 3, 1981
Dear Mr. Knighton:
This letter provides the response required by Reference (1) for Palo Verde Units 1, 2, and 3.
Some of this information was previously submitted by Reference (2).
Since there are not yet any surveillance capsule evaluations or other direct measurements of vessel fluence rates for Palo Verde Units 1, 2,
and 3,
FSAR peak fluence predictions were used to calculate the required RT-PTS values.
Calculations were also done with the FSAR fluence increased by a factor of,two (2.0) to conserva-tively bound possible variations in fluence due to uncertainties in actual plant operations and fuel loading strategies.
As a conservative simplification, the peak of the axial and azimuthal fluence profiles was used to calculate a conservative RT-PTS value.
The controlling material chemistry and initial (i.e.,
pre-irradiation) toughness properties of the reactor vessel beltline materials for each of the three Palo Verde units are provided in Table
- 1. In each
- case, the controlling materials are the base plate properties, not the welds.
The highest copper-nickel combination is 0.07X Cu and 0.66X Ni in PVNGS Unit 1. Using the CESSAR-F maximum 'design fluence of 3.15 X 1019 n/cn 2 (E>1 MeV) at the inside surface of the reactor vessel and the RT-PTS prediction equation from 10 CFR 50.61 results in a projected shift of 54'F, and a projected RT-PTS of 132'F. If the actual fluence were a factor of two greater (i.e., 6.3 X 1019 n/cn2) then the projected shift and RT-PTS would be 65 F and 143'F, respectively.
These results conservatively bound calculations for PVNGS Units 2 and 3.
860i240iES 860i24%
PDR ADOCK 05000528 P
PDR I
AB - B. CRVTCHPIELD (ltr only)
EB (N. JOIIIISION)
RSB (TIIONAS)
EICSB (PARR)
FOB (If+ RECAN)
II/f (jII
c>
, ~
I
Mr. George V. Knighton Pressurized Thermal Shock ANPP-Page 2
As can be seen
2, and 3 are projected to remain well below the 10 CFR 50.61 screening criterion of 270'F, even for twice the maximum design fluence. In accordance with the requirements of paragraph (b)(1) of 10 CFR 50.61, we will inform you if future changes in core loadings, surveillance measurements or other information indicate a significant change in the projected values.
Ne believe this satisfies the requirements of 10 CFR 50.61 for PVNGS 1,
2, and 3.
Very truly
- ours, E. E.
Van Brunt, Jr Executive Vice Presa. dent Project Director EEVB/VFQ/PGN/rw cc:
A. C. Gehr E. A. Licitra R. P.
Zimmerman
I J ~
v, /
e JAN 2D gD6 DOCKET NO(S). 50 528 Mr. E. E.
Van Brunt, Jr.
Executive Vice President Arizona Nuclear Power Project P. 0.
Box 52034 Pheonix, Arizona 85072-2034 ARIZONA PUBLIC SERVICE COMPANY - PALO VERDE NUCLEAR GENERATING STATION, UNIT 1 D'
BUTION
'De et-File~
PDR LPDR PBD7 Reading PRC System JLee (2)
The following documents concerning our review of the subject facility are transmitted for your information.
CI Notice of Receipt of Application, dated Cl Draft/Final Environmental Statment, dated D Notice of Availabilityof Draft/Final Environmental Statement, dated C3 Safety Evaluation Report, or Supplement No.
, dated Cj Notice of Hearing on Application for Construction Permit> dated O Notice of Consideration of Issuance of Facility Operating License, dated Bi-weekly I4I gggggy Notice; Applications and Amendments to Operating Licenses Involving no Significant Hazards Considerations, dated a e 1883)
D Application and Safety Analysts Report, Volume CI Amendment No.
to Application/SA R dated D Construction Permit No. CPPR-CI Facility Operating License No.
, Amendment No.
, Amendment No.
dated
, dated C) Order Extending Construction Completion Date, dated O Other (SpecifyJ Office of Nuclear Reactor Regulation
Enclosures:
As stated cc:
See next page OFFICE~
SURNAME~
DATE+
BD..
es
~i'" )86""
~ ~ ~
~
~ ~
\\
~
~ ~
~
~ tt
~
NRC FORM 318 {1/84) NRCM 0240
J' l
I eI
\\ ~
~ ~
~
gN
Mr. E.
E.
Van Brunt, Jr.
Arizona Nuclear Power Pro,iect Palo Verde qcc:
Arthur C. Gehr, Esq.
Snell 5 Wilmer 3100 Valley Center Phoenix, Arizona 85073 Mr. James M. Flenner, Chief Counsel Arizona Corooration Commission 1200 West Washinqton 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 Planninq 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 5 Strawn Suite 500 2550 M Street, NW Washington, DC 20037 Ms. Lynne Bernabei Government Accountability Prniect of the Institute for Policy Studies 1901 gue Street, NW Washinatnn, DC 20009 Ms. Jill Mnrrisnn 572 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
f, I,
f'
Chairman Arizona Corporation Commission P.
0;-
Box 6019 Phoenix, Arizona 85003 Arizona Radiation Regulatory Agency ATTN:
Hs. Clara Palovic, Librarian 925 South 52nd Street Tempe, Arizona 85238 Nr. Charles Tedford, Director Arizona Radiation Regulatory Agency 924 South 52nd Street, Suite 2
Tempe, Arizona 85281 Chairman Naricopa County Board of Supervisors 111 South Third Avenue Phoenix, Arizona 85003
r
'\\