ML19331B699

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Amends 44 & 27 to Licenses DPR-53 & DPR-69,respectively, Authorizing Changes in Location Where Samples Are Taken When Safety Injection Tank Level Increases Are Routinely Made
ML19331B699
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 08/01/1980
From: Clark R
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19331B700 List:
References
NUDOCS 8008120617
Download: ML19331B699 (10)


Text

8 UNITED STATES

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~' g NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 yj

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O BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 44 License No. DPR-53 1.

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

A.

The application for amendment by Baltimore Gas & Electric Comparty (the licensee) dated July 14, 1980, conplies with the standards and requirements of the Atomic Energy Act o' 1954, as amended (the Act) and the Comission's rules ant r.:gulations 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 (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 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 satisified, l

,8008120 6/7

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-53 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 44, are hereby incorporated in the license.

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

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

] bu Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing Attacheent:

Changes to the Technical Specifications Date of Issuance: August 1, 1980

ATTACHMENT TO LICENSE AMENDMENT NO. 44 FACILITY OPERATING LICENSE NO. DPR-53 DOCKET NO. 50-317 Replace the following page of the Appendix A Technical Specifications with the. enclosed page as indicated. The revised page is identified by Amendment number and contains vertical lines indicating the area of change.

The corresponding overleaf page is also provided to maintain document completeness.

Page 3/4 5-2 1

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3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

SAFETY INJECTION TANKS LIMITING CONDITION FOR OPERATION 3.5.1 Each reactor coolant system safety injection tank shall be OPERABLE with:

a.

The isolation valve open, b.

A contained borated water volume of between 1113 and 1179 cubic feet of borated water (equivalent to tank levels of between187.and199 inches,respectively),

c.

A boron concentration of between 1720 and 2200 ppm, and l

d.

A nitrogen cover-pressure of between 200 and 250 psig.

APPLICABILITY: MODES 1, 2 and 3.*

ACTION:

a.

With one safety injection tank inoperable, except as a result of a closed isolation valve, restore the inoperable tank to OPERABLE status within one hour or be in H0T SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

With one safety injection tank inoperable due to the isolation valve being closed, either immediately open the isolation valve or be in HOT STANDBY within one hour and be in HOT SHUTOOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.5.1 Each safety injection tank shall be demonstrated OPERABLE:

a.

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by:

I 1.

Verifying the contained borated water volume and nitrogen cover-pressure in the tanks, and 2.

Verifying that each safety injection tank isolation valve is open.

  • With pressurizer pressure > 1750 psia.

CALVERT CLIFFS - UNIT 1 3/4 5-1 Amendment No. 38

_ EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) i b.

At least once per 31 days by verifying the boron concentration of the safety injection tank solution.

c.

At least once per 31 days when the RCS pressure is above 2000 psig, by verifying that power to the isolation valve operator is removed by maintaining the feeder breaker open under administrative control, d.

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to increasing the RCS pressure above 1750 psia by verifying, via local indication at the valve, that the tank isolation valve is open.

At least once per 18 months by verifying that each safety e.

injection tank isolation valve opens automatically under each of the following conditions:

1.

When the RCS pressure exceeds 300 psia, and 2.

Upon receipt of a safety injection test signal.

f.

Within one hour prior to each increase in solution volume of 3.1% of normal tank volume by verifying'the boron concent-ration at the operating high pressure safety injection pump discharge is between 1700 and 2200 ppm.

CALVERT CLIFFS - UNIT 1 3/4 5-2 Ar endment No. 44

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UNITED STATES g

NUCLEAR REGULATORY C6MMISSION p,

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BALTIMORE GAS AND ELECTRIC COMPANY DOCKET N0. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amandment No. 27 License No. DPR-69 1.

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

A.

The application for amendment by Baltimore Gas & Electric Conpany (the licensee) dated July 14, 1980, 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 t

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 satisified.

5066izG

2.

Accordingly, the license is amended hy 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-53 is herehy amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 27, are hereby 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 THE NUCLEAR REGULATORY COMMISSION

-)

Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: August 1, 1980

ATTACHMENT TO LICENSE AMENDMENT NO. 27 FACILITY OPERATING LICENSE NO. DPR-69 DOCKET NO. 50-318 Replace the following page of the Appendix A Technical Specifications with the enclosed page as indicated.

The revised page is identified by Amendment number and contains vertical lines indicating the area of change.

The corresponding overleaf page is also provided to maintain document completeness.

Page 3/4 5-2

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3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

SAFETY INJECTION TANKS LIMITING CONDITION FOR OPERATION 3.5.1 Each reactor coolant system safety injection tank shall be OPERABLE with:

l a.

The isolation valve open, b.

A contained borated water volume of between 1113 and 1179 cubic feet of borated water (equivalent to tank levels of between 187 and 199 inches, respectively),

A boron concentration of between 1720 and 2200 ppm, and l

c.

d.

A nitrogen cover-pressure of between 200 and 250 psig.

APPLICABILITY: MODES 1, 2 and 3.*

ACTION:

l With one scfety injection tank inoperable, except as a result a.

of a closed isolation valve, restore the inoperable tank to OPERABLE status within one' hour or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

With one safety injection tank inoperable due to the isolation valve being closed, either immediately open the isolation valve or be in HOT STANDBY within one hour and be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.5.1 Each safety injection tank shall be demonstrated OPERABLE:

'a.

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by:

1.

Verifying the contained borated water volume and nitrogen cover-pressure in the tanks, and 2.

Verifying that each safety injecticn tank isolation valve is open.

l

  • With pressurizer pressure > 1750 psia.

CALVERT CLIFFS - UNIT 2 3/4 5-1 Amendment No.21

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.

At least once per 31 days by verifying the boron concentration of the safety injection tank solution.

At least ance per 31 days when the RCS pressure is above c.

2000 psig, by verifying that power _to the isolation valve operator is removed by maintaining the feeder breaker open under administrative control.

d.

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to increasing the RCS pressure above 1750 psia by varifying, via local indication at the valve, that the tank tsolation valve is open.

At least once per 18 months by verifying that each safety e.

injection tank isolation valve opens automatically under each of the following conditions:

1.

When the RCS pressure exceeds 300 psia, and 2.

Upon receipt of a safety injection test signal.

i f.

Within one hour prior to each increase in solution volume of > 1% of normal tank volume by verifying the boron concentration at the operating high pressure safety injection pump discharge is between 1700 and 2209 ppm.

I i

l CALVERT CLIFFS - UNIT 2 3/4 5-2 Amendment No. 27 i

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