ML18139A239
| ML18139A239 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/16/1980 |
| From: | Ferguson J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18139A240 | List: |
| References | |
| 413, NUDOCS 8005190411 | |
| Download: ML18139A239 (4) | |
Text
e l1tHoa19 o 1-/ 1 I VIRGINIA ELECTRIC AN:0 POWER COMPANY RICHMOND,VIRGINJ:A 23261 May 16, 1980 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:
Mr. Steven A. Varga, Chief Serial No. 413 LQA/WRM:rab p
Operating Reactors Branch No. 1 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Docket No. 50-280 LicenseNo. DPR-32
Dear Mr. Denton:
PROPOSED AMENDMENT TO OPERAl'ING,-LICENSE*DPR-32 SURRY. POWER. STA';rION
- UNJT. NO. : 1.
Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company hereby requests an amendment to Operating License DPR-32 for the Surry Power Station Unit No. 1.
The proposed change is to extend operation for an additional six months from the completion of the recently completed steam generator inspection with the same conditions and limitations as issued in Amend-ment No. 55, dated February 4, 1980.
Amendment No. 55 allows the unit to operate for six months equivalent full power operation from October 25, 1979.
To date, approxi-mately.100 days of equivalent full power operation have been completed of the six months permitted by Amendment No. 55; therefore, start-up from the current outage can be made under the provisions of Amendment No. 55.
In our letter dated April 16, 1980 (Serial No. 325), we provided the results of the recently completed Surry Power Station Unit No. 1 steam generator inspection.
The total number of tubes plugged in Surry No. 1 is now 2558 or approximately 25.1%; therefore, existing analyses regarding safe operation under normal and accident conditions are applicable.
The Station Nuclear Safety and Operating Committee and the System Nuclear Safety and Operating Committee have reviewed and approved this request~* It has been determined that this request does not pose an unreviewed safety question.
A 00 /
s,/,
Wk~E.cA:
IJ vooo.oo
e e
VrnornIA ELECTRIC AND PowER CoMPANY To Mr. Harold R. Denton 2
This request has been evaluated in accordance with the.criteria in 10 CFR 170.22.
The requested amendment represents a single safety issue; therefore, a Class III license amendment fee is required.
- A~cordingly, a voucher check in the amount of $4,000.00 is enclosed in payment of the required fee.
Very truly yours,*
J. H. Ferguson Executive Vice President-Power Attachments:
- 1. Proposed Amendment to License No. DPR-32
- 2.
Voucher Check No.
for $4,000.00 cc:
Mr. James P. O'Reilly, Director Office of Inspection and Enforcement Region II
COMMONWEALTH OF VIRGINIA
)
. )
S. So CITY OF RICHMOND
)
Before me, a Notary Public, in and for the City and Common-wealth aforesaid, today personally appeared J. H. Ferguson, who being duly sworn, made oath and said (1) that he is Executive Vice President-Power of the Virginia Electric and Power Company, (2) that he is 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 his knowledge and belief.
m Given. under my hand and notarial seal this \\ bili day of
_O~
, tlli.!L-My Connnission expires. ~()\\J,~ do 1 1'18 I (SEAL)
~**
8005190 ~/~.
Replace paragraph 3.E in its entirety with the following:
E.
Steam Generator Inspection (1)
Unit No. 1 shall be brought to the cold shutdown condition in order to perform an inspection of the steam generators within six months of equivalent operation from (date of Amendment issuance)
Nuclear Regulatory Commission (NRC) approval shall be obtained before resuming power operation following this inspection.
Equivalent operation is defined as operation with the reactor coolant at or above 3500F.
(2)
Reactor Coolant leakage from the reactor coolant system (RCS) to the secondary system (SS) through the steam generator tubes shall be limited to 0.3 gpm per steam generator, as described in the NRC Safety Evaluation of May 6, 1977. With any steam generator tube leakage greater than this limit the reactor shall be brought to the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
NRC approval shall be obtained before resuming reactor operation.
(3)
Reactor operation shall be terminated if RCS to SS leakage which is attributable to 2 or more steam generator tubes occurs during a 20 day period.
NRC approval sh~ll be obtained before resuming reactor operation.
(4)
The concentration of radioiodine in the reactor coolant shall be limited to 1 uCi/gram DOSE EQUIVALENT Iodine-131 during normal operation a.nd to 10 uCi/gram DOSE EQUIVALENT Iodine-131 during power transients as defined in Appendix A-1.to the Technical Specifications of the license.. Appendix A-1 was issued with the May 6, 1977 Order and shall remain in effect for six equivalent months from (date of Amendment issuance).