ML20086Q056

From kanterella
Jump to navigation Jump to search
Amend 210 to License DPR-56,allowing Third Type a Containment ILRT in Second 10 Yr Svc Period to Be Conducted During Refueling Outage 11 Scheduled for Sept 1997
ML20086Q056
Person / Time
Site: Peach Bottom 
Issue date: 07/10/1995
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Atlantic City Electric Co, Delmarva Power & Light Co, PECO Energy Co, Public Service Electric & Gas Co
Shared Package
ML20086Q059 List:
References
DPR-56-A-210 NUDOCS 9507270270
Download: ML20086Q056 (4)


Text

._

t

. I,9' u%I UNITED STATES f

t NUCLEAR RF.GULATORY COMMISSION 3

E wannatow, p.c. acess-coot

  • \\..,*/

PECO ENERGY COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE i

Amendment No. 210 License No. DPR-56 1.

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

A.

The application for amendment by PECO Energy Company, et al. (the licensee) dated November 21, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the' Commission'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 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 such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the i

common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission'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 2.C.(2) of Facility Operating License No. DPR-56 is hereby amended to read as follows:

950727027o 950710 PDR ADOCK 05000278 P

PDR

1 (2) Technical Snecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.210, are hereby incorporated in the license. PECO shall operate the facility in accordance with the 1

Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION ffL2 Jo 'F.

Stolz, Dire r

P ject Directorat

-2 4

ivision of Reactor Projects - I/II Office of Nuclear Reactor Regulation 1

Attachment:

Changes to the Technical Specifications t

Date of Issuance: July 10, 1995 i

t l

i I

I

)

l f

.m

I L

I ATTACHMENT TO LICENSE AMENDMENT NO.210 FACILITY OPERATING LICENSE NO. DPR-56 t

DOCKET NO. 50-278 i

Replace the following page of the Appendix A Technical-Specifications with the enclosed page. The revised areas are indicated by marginal lines.

Remove Insert 167 167 F

L l

i h

s-.-

5 l

?

i a

~

d.

^

Unit 3 PBAPS' i.

. LIMITING C'ONDITIONS FOR OPERATION

- SURVEILLANCE REQUIREMENTS 3.7.A Primary containment'(Cont'd.)

4.7.A Primary Containmant (Cont'd.)

If, = measured ILR at 25 l

Psig (P,)

L

= measured ILR at 49.1 Psig (P.), and i

km k

5 0.7, otherwise L.

= La. (P /P,) UI l

Le t

where La = 0.5 percent of the primary containment i

volume per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 49.1 psig peak accident pressure P,

=

(Psig) appropriately measured

j P,

=

test pressures (psig)

c. The ILRT's shall be prformed at the following minimum l

frequency:

1.

Prior to initial unit operation.

2. After the preoperational' leakage rate tests, a set of three Type A tests shall be performed at approximately equal intervals during each 10 year service period.*

j These intervals may be extended up to eight months if necessary to coincide with re-fueling outage.

d. The allowable leakage rates,
l L

and-L shall be less tEan 0.7f,Ig and 0.75 L, for the reduced pressure tests and peak pressure tests, respectively.

  • Except for third Type A test in the second 10 year service period, which will be performed during the PBAPS, i

Unit 3 refueling outage 11 currently scheduled for J

September 1997.

-167-Amendment No. idf, 210 i

,,.I