ML20062A086

From kanterella
Jump to navigation Jump to search
Amends 144 & 141 to Licenses DPR-32 & DPR-37,respectively, Extending Operation of Units 1 & 2 to Cycle 11 W/ Pressurizer Safety Valve Setpoint
ML20062A086
Person / Time
Site: Surry  
Issue date: 10/05/1990
From: Berkow H
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20062A090 List:
References
NUDOCS 9010190072
Download: ML20062A086 (6)


Text

!(p* **euq'g UNITED STATES NUCLEAR REGULATORY COMMISSION n

s i

nAswiwatom, p. c. nees

\\e....)

VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 144 License No. DPR-32 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Virginia Electric and Power Company (the licensee) dated June 25, 1990 complies with the standards and requirements of the AtomicEnergy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

Thereisreasonableassurance(1)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; 1;

and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirement:

have been satisfied.

I 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License i

No. DPR-32 is hereby amended to read as follows:

3 j

P

l c

i (B) Technical Specifications

(

The Technical Specifications contained in A)pendix A, as revised through Amendment No. 144, are mereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR TliE NUCLEA REGULATORY COMMISSION f

lY

/ILv

'g w.erbert(D rectorate 11-2 Berkow, Director Project Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

t Changes to the Technical Specifications Date of Issuance: October 5, 1990 e

.m

!-r.

!(f.sh UMTES sTAits NUCLEAR REGULATORY COMMISSION n

5.

.f waswiwovow,p.c. noses

  • \\...* g '

i i

VIRGIN 1A ELECTRIC AND POWER COMPANY l-DOCKET NO. 50-281 SURRY POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE j

1 Amendment No. 141 i

License No. DPR-37 1.

The Nuclear Regulatory Comission (the Commission) has found that:

A.

The application for amendment by Virginia Electric and Power Company (the licensee) dated June 25, 1990 complies with the standards and requirements of the Atomic Energy Act of 1954, as anended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of t1e Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that sur.h activities will be

. conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security.or to the health and safety of the'public; and E.

The issuance of this anendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license

. amendment, and paragraph 3.B of Facility Operating License No. DPR-37 is hereby amended to read as follows:

l

j (B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.141, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, i

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEA REGULATORY COMMISSION f

d' 4/ 'Gu M erbert N Berkow, Director 3

Project Mrectorate II-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications

.Date of Issuance: October 5, 1990 7

9 w

ATTACHNENT TO LICENSE AMENDMENT AMENDMENT NO. 144 FACILITY OPERATING LICENSE NO. DPR-32_

AMENDMENT NO 141 FACILITY OPERATING LICENSE NO. OPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:

Remove Page Insert Page TS 3.1-4 T5 3.1-4 b

r i

l l

o r

TS 3.14 b.

Three valves shall be operable when the reactor coolant average temperature is greater than 350'F, the reactor is critical, or the l

Reactor Coolant System is not connected to the Residual Heat Removal System.

1 Valve lift settings shall be maintained at 2485 psig ?,' percent.'

c.

4.

Reactor Coolant Loops Loop stop valves shall not be closed in more than one loop unless the Reactor Coolant System is connected to the Residual Heat Removal System and the Residual Heat Removal System is operable, 5.

Pressurizer

't a.

The reactor shall be maintained subcritical by at least 1% until the steam bubble is established and the necessary sprays and at least 125 KW of heaters are operable, b.

With the pressurizer inoperable due to inoperable pressurizer heaters, restore the inoperable heaters within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least hot shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and the reactor coolant system 7

temperature and pressure less _than 350 F and 450 psig, respectively, within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

I For the remainder of Cycle 10 and Cycle 11 operation for both units, the valve lift settings shall be maintained at 2485 psig (4s.1 percent.)

Amendment Nos.144 and 141, f