ML20141F074

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Amend 99 to License DPR-66,changing Tech Specs to Remove Specs for Iodine Sampler Cartridge
ML20141F074
Person / Time
Site: Beaver Valley
Issue date: 12/23/1985
From: Rubenstein L
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20141F080 List:
References
NUDOCS 8601080594
Download: ML20141F074 (8)


Text

D UNITED STATES 8

N NUCLEAR REGULATORY COMMISSION 5

j WASHINGTON. D. C. 20555 s.

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DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.99 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 June 17, 1985, complies with the standards and requirements of the Atomic Energy 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.

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:

8601000594 051223 PDR ADOCK 05000334 P

PDR

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(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 99, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This amendment is effective on issuance, to be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

([

Lester S. Rubenstein Director PWR Project Directorate #2

Attachment:

Changes to the Technical Specifications Date of Issuance: December 23, 1985 i

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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 99 TO FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Revise Appendix A as follows:

Remove Pages Insert Pages 3/4 3-60 3/4 3-60 3/4 3-61 3/4 3-61 3/4 3-65 3/4 3-65 3/4 3-66 3/4 3-66 3/4 3-68 3/4 3-68' l

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TABLE 3.3-13 E

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION h

MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY PARAMETER ACTION m

I e5 1.

Gaseous Waste / Process Vent

[

System (RM-GW-108A & B)

Radioactivity Rate 27, 30 ***

a.

Noble Gas Activity Monitor (1)

Measuia int I

32 b.

Particulate' Activity Monitor (1) c.

System Effluent Flow Rate (1)

System Flow Rate 28 Measurement Measuring Device (FR-GW-108) b d.

Sampler Flow' Rate Measuring (1)

Sampler Flow Rate 28 Measurement Device 2.

Auxiliary Building Ventilation System (RM-VS-101A & B)

Radioactivity Rate 29, 30 ***

a.

Noble Gas Activity Monitor (1) g Measurement 32 b.

Particulate Activity Monitor (1) c.

System Effluent Flow Rate (1)

System Flow Rate 28 Measurement j

Measuring Device (FR-VS-101) d.

Sampler Flow Rate Measuring (1)

Sampler Flow Rate 28 Measurement 2

Device 8

During Releases via this pathway

      • During purging of Reactor Containment via this pathway.

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l TABLE 3.3-13 (Continued) i E

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION f

g c

i l

t M

l M

MINIMUM CHANNEL' l

E INSTRUMENT OPERABli_

APPLICABILITY PARAMETER ACTION l

I 3.

Reactor Building / Supplementary Leak Collection and Release System (RM-VS-107A & B) i Radioactivity Rate 29, 30.***

Noble Gas Activity Monitor (1)

I a.

32 e

b.

Particulate Activity Monitor (1)

O c.

System Effluent Flow Rate (1)

System Flow Rate 28 l

Y' Measurement l

Measuring Device (FR-VS-112) d.

Sampler Flow Rate Measuring (1)

Sampler Flow Rate 28 Measurement Device t

F Ee 5

During Releaes via this pathway During purging of Reactor Containment via this pathway.

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TABLE 4.3-13 E3 RADIDACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 9

CHANNEL h

CHANNEL SOURCE CHANNEL FUNCTIONAL M

INSTRUMENT CHECK CHECK CAllBRATION TEST e

  • z Q

1.

Gaseous Waste / Process Vent System (RM-GW-108A & B) a.

Noble Gas Activity Monitor P

P(5)

R(3)

Q(1) b.

Particulate Activity Monitor W

N/A N/A R/A c.

System Effluent Flow Rate P

N/A R

Q g

Measuring Device (FR-GW-108).

Y d.

Sampler Flow Rate Measuring Device D*

N/A R

Q

?,

2.

Auxiliary Building Ventilation System (RM-VS-101A&B) a.

Noble Gas Activity Monitor D

M(5),

R(3)

Q(2) i P(5)***

l b.

Particulate Activity Monitor W

N/A N/A N/A c.

System Effluent Flow Rate D

N/A R

Q k

Measurement Device (FR-VS-101)

'D N/A R

Q k

d.

Sampler Flow Rate 5

3.

Reactor Building / Supplementary Leak Collec-tion and Release System (RM-VS-107A & B) a.

Noble Gas Activity Monitor D

M(5),

R(3)

Q(2)

P(5)***

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TABLE 4.3-13,(Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

h CHANNEL r-0 CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST E*

l b.

Particulate Activity Monitor.

W N/A N/A N/A c.

System Effluent Flow Rate D

N/A R

Q Measuring Device (FR-VS-112) d.

Sampler Flow Rate Measuring Device D

N/A R

Q R

y 4.

Waste Gas Decay Tanks Monitor a.

Oxygen Monitor D

N/A Q(4)

M (0 -AS-GW-110-1,2) 2 b.

Radiation Monitor (RM-GW-101)

D**

M(5)

R(3)

Q(2) c.

Sampler Flow Rate Measuring Device D**

N/A R

Q E

lit

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TABLE 4.3-13(Continued)

TABLE NOTATION The CHANNEL CALIBRATION shall include the use of standard gas (4) samples containing a nominal:

One volume percent oxygen, balance nitrogen, and 1.

Four volume percent oxygen, balance nitrogen 2.

A source check may be performed utilizing the (5) increase in the existing count rate to verify channel response.

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  • 3/4 3-68 i

BEAVER VALLEY - UNIT 1 Amendment No. 99

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