ML20106D792

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Amend 81 to License DPR-66,revising Tech Spec Tables 3.3-6 & 4.3-3 Re Radiation Monitoring Instrumentation by Deleting Purge & Exhaust Isolation
ML20106D792
Person / Time
Site: Beaver Valley
Issue date: 10/15/1984
From: Varga S
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20106D793 List:
References
NUDOCS 8410260163
Download: ML20106D792 (5)


Text

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NUCLEAR REGULATORY COMMISSION.

1 wasaisoToN. o. c. 20sss

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%; %Af DUQUESNE LIGHT COMPANY-CHIO EDIS0N COMPANY

-PENNSYLVANIA POWED COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO.1 ANENDMENT TO FACILITY OPERATING LICENSE Amendment No.81 License-No. DPR-66 1.

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

A.

The application for amendment by Duquesne Light Company, Ohio Edison Company, and Pennsylvania Power Company (the licensees) dated May 21, 1984, complies with the standards and requirements of the-Atomic Energy Act of 1954, as. amended (the Act) and the Comission's rules and r,egulations set forth in 10 CFR Chapter -I; B.

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

There is reasonable assurance (i) 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon 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 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 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended to read as follows:

8410260163 841015 PDR ADGCK 05000334 P-PDR

(2) Technical Specifications The Technical Specifications contained'in Appendices A and B, as revised through Amendment No. 81, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective on issuance, to be implemented no later than 30 days after issuance.

FOR THE NUCLEAR REGULATORY COMMISSION t

teven A.

arga, Ch1 Operating Reactors' ch #1 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

October 15, 1984 m

E l

ATTACHMENT TO LICENSE-AMENDMENT AMENDMENT NO. 81 TO FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Revise Appendix A as follows:

Remove Pages Insert Pages 3/4 3-34 3/4 3-34 3/4 3-36 3/4 3-36

~

g TABLE 3.3-6

)

RA0lATI0ll ilulilTORING INSTRUMEtlTATION t

x HlitIHUH CilANNELS APPLICABLE MEASUREMENT E

lilSTRilitEllT OPERA 3LE H0 DES SETP0lNT#

RANGE ACTION A

1.

AREA infilTORS SIS mR/hr 10-I - 10 d/ht-19 4

a.

Fuel Storage Pool Area 1

(Rti-207) b.

Conla insiienL i.

Purge & Exhaust 3

6 Isolation (RilVS 1

6

$1.6 x'10 cpm 10 - 10 cpi 22 104 A & B) t'.

7 li. Area (lui-Ril-219 A & B) 2 1,2,3,&4

$_30 R/hr 1 - 10 R/lir 36 c,a i

'il 2.

PROCESS HorilTORS a.

Cont a isisitent i.

Gaseous Activity RCS Leakage Detection (Ril2158) 1 1, 2, 3, & 4 N/A 10 - 10 cpi 20 F

m li, l' articulate Activity

{

RCS Leakage Detection 6

g (Rtl215A) 1 1, 2, 3, & 4 N/A 10 - 10 cpm 20 e

4

-6 b.

fuel Storage Building 1

$4.0 x 10 cpm 10 - 10 cpm 21

=

tiross Activity (RilVS -

103 A & 11) m uith fuel in the storage pool or building a

Ulth irradiated fuel iii the storage pool

^

  1. Aliove background

T TAllLE 4.3-3 h

RADIAT10ft 110illTORING IllSTRilHENTATION SilRVEllLANCE REQtilREMENTS 5

g CllANNEL H0 DES IN WillCil p

CilAHilEL CilANilEL FUNCTIONAL SURVEILLANCE Q

lilSTRilHEllT CilECK CAllBRATION TEST REQUIRED h

I.

APEA 110111 TORS

?.

a.

Fuel Storage Pool Area S

R H

(Ril207)

~

h.

Conta irment 1.

Iharge & Exhaust Isola tion S

R H

6 (RilVS 104 A & 0) 11.

Area (RH-Ril-219 A & B)

S R

H 1, 2, 3 & 4 t'

s a.,

h 2.

PROCESS tl0lllTORS a.

Contairment i.

Caseous Activity RCS leakage l

Detection (RH 2150)

S R

H 1, 2, 3 & 4 E

11.

Particulate Activity RCS leakage l

lietection (RH 215A)

S R

H 1, 2, 3 & 4 h.

fuel Storage Building S

R H

Gross Activity o

"g (RitVS 103 A & B) llfTIIfuel in the storage pool or leuilding

^ ^ lil th irradia ted fisel lit tlie storage l col i

-