ML19105A836
| ML19105A836 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/26/1977 |
| From: | Stallings C Virginia Electric & Power Co (VEPCO) |
| To: | Case E, Reid R Office of Nuclear Reactor Regulation |
| References | |
| Download: ML19105A836 (5) | |
Text
NRC FORM 195 U.S. NUCLEAR REGULATORY COMMISSION
,2-76)
~-*
.'f\\
.~.
e NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL e TO:
Edson G~ Case
('.]LETTER
!iif'oR JG INAL OcoPY DESCRIPTION
~NOTORIZED
. i7uNCL.ASSIFIED FROM:
Virginia Elec & Power Co Richmond.:;Va.
. C. M. Stallings PROP INPUT FdRM ENCLOSURE DO&,/ ;~Btr;ll i'f:P.
FILE NUMBER.
DATE OF DOCUMENT 8-26-77 DATE RECEIVED 8-29-77 NUMBER OF COPIES RECEIVED 3 519/A,leO Ltr notarized 8-26-77..*.. furnishing Supplemental Information to.Arndt to OL Tech Specs Change No. 57.... trans:
Report, "Large Break LOCA-ECCS Reanalysis dtd 8-26-77 PLANT NAME: Surry 1 & 2 retype Per LML 8~31-77 f'
' ~
Dil?.*TRlBUTION AFTER ISSUAL'lCE OF OPERATING LICENSE
-~
OOCKET NUMBS~
- )
NRC FORM 195 U.S. r.;ucLEAR REGULATORY MISSION (2-76)
.-S-A-1iff:;ff/ZS' /
FILE NUMBER /l\\_
~
NAC DISTRIBUTION FOR PART 50 DOCKET MATERIAL I TO:
FROM:
CATE OF OOCUMENT I
Virginia Electric & Pwr. -Comp.iny 8/26/77 I
Mr. Edson G. Case C. M. Sta 11 i ng s /Richmond, Va.
CATE RECEIVEO 8/29/77 l@'t.ETTER 9°NOTORIZEO PROP INPUT FORM NUMBER OF COPIES RECEIV!:O
@15RIGINAI.
i2CJNCLASS1F1EO 3.,S/61Jt..P I
OcoPv I I OESCRIPTION ENCLOSURE Report Entitled:
I Large Break LOCA-ECCS DO NOT RE~10VE Reanalysis Surry Power Station Units No. 1 and 2 I
Notarized August 26, 1977 ******* with 1~CKNOWLEDGED associated changes. to tech specs No. 57 for license No. DPR-32 and DPR-37******
I PLANT NAME: Surry Units 1 & 2 (2-P)
(3/811 )
0 RJL 8/29/7.7.
¥tJ EJJc.L..
SAFETY FOR ACTION/INFORMATION I
BRANCH CHIEF: (7)
P~/.f.J
-~-
~
INTERNAL DISTRIBUTION Ir R"R~ F;cr-
~-R<}*::PDR.
i I & E (2)
I i
OELD I
HANAUER CHECK STELLO L?-~
- I EISENHUT SHAO I
BAER BUTLER GRIMES J. COLLINS
~ 0.S.S/(!,lft.
EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR:./1 1*
1 I - --~ *~
f/R, TIC 77;>.'I/ Ofr">--1 NSIC 16 CYS ACRS SENT CATE G01 y 1/!l5 I.
. **-----~---* -- *- -
i-f
-~
I
~
f e
e VIRGINIA ELECTRIC.A.Ni;> POWER COMPANY RICHMOND, VIRGINIA 23261 August 26, 1977 Mr. Edson G. Case, Acting Director Office of Nuclear Reactor Regulation Attn: Mr. R. w. Reid, Chief Operating Reactors Branch No. 4 U. s. Nuclear Regulatory Connnission Washington, D. C.
20555
Dear Mr. Case:
Serial No. 372 FR/MLB/RWC/EJL:krb Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37
~* lll/
SUPPLEMENTAL INFORMATION TO AMEND TO THE OPERATING LICENSE TECHNICAL SPECIFICATIONS CHANGE NO. 57 SURRY POWER STATION UNITS 1 AND 2 Pursuant to 10 CFR 50.59, the Virginia Electric and Power Company, in our letter of August 9, 1977 {Se.rial No. 344), requested an amendment to Opera-ting Licenses DPR-32 and DPR-37 for the Surry Power Station, Units No. 1 and 2.
The amendment requested was a change to the Technical Specifications, designated as Change No. 57, which was based on an evaluation of the impact of higher steam generator tube plugging levels on the currently applicable non-LOCA safety ana-lyses.
However, the amendment did not include any Technical Specifications changes or reanalysis associated with the impact of higher steam generator tube plugging on LOCA-ECCS performance.
This was to be sent in as supplemental infor-mation at a later date.
Accordingly, transmitted herewith as Attachments 1 and 2 are (1) a reanalysis of the i.Ip.pact of higher steam generator tube plugging, up to a level of 25%, on the limiting break LOCA-ECCS case (Cn=0.4), and (2) the associated changes to the Teclmical Specifications (including, for completeness the changes already transmitted in the August 9, 1977 amendment).
The results of the nor-mally non-limiting break cases (Cn=0.6 and 1.0) will be provided as supplementary information in the near future.
However, it is not anticipated that this infor-mation will necessitate additional changes to the Teclmical Specifications.
- ~
The LOCA-ECCS analysis provided in our letter of March 4, 1977, Serial No. 219/082776 remains applicable for steam generator tube plugging up to a level of 19% for Unit No. 1 and 20% for Unit No. 2.
The a~tual steam generator tube plugging level as of this.date is less than the above limits of the currently applicable analysis.
The reanalysis and associated changes in the Technical Speci-fications provided. in the Attachments along with our previously referenced sub-mittal for the non-LOCA analysis justifies operation with up to 25% of the steam generator tubes being plugged.
All changes have been reviewed by both the Station Nuclear Safety and Operating Committee and the System Nuclear Safety and Operation Committee.
Fur-ther, it has been determined that these changes do not involve an unreviewed safety question as defined in 10 CFR 50.59.
f
~~-~
I e
VIBOlNIA EuCTRJC AND PoW?:B CoMPA:h~ TO Mr. Edson G. Case, Acting Director Page 2 Should you have any questions or comments, we would be most* happy to meet with you at your.earliest convenience.
Attachments Very truly yours,
- u. J?J..Ji;:.za~ ;7:J/.
C. M. Stallings Vice Pres~dent-Power Supply and Production Operations cc:
Mr. James P._ O'Reilly, Director_
Office of Inspection and Enforcement
,,*',r 9-
- e (SEAL)
Attest:
D. A.
COMMONWEALTH OF VIRGINIA)
) s.s.
CITY OF RICHMOND
)
Before me, Robert M. Neil, a Notary Public, in and for the City and Commonwealth aforesaid, on the 26th day of August, 1977, personally appeared C. M. Stallings and D. A. Hillsman, Jr., who being duly sworn, made oath and said (1) that they are Vice President - Power Supply and Production Operations and Assistant Secretary, respectively, of the Virginia Electric and Power Company, (2) that they are duly authorized to execute and file the foregoing Amendment in behalf of that Company, and (3) that the statements in the Amendment are true to the best of their knowledge and belief.
(SEAL)
Given under my hand and notarial seal this 26th day of August, 19770 My Commission expires January 20, 1981 *
&~&P/~/
Robert M. Neil Notary Public