ML20008F854

Amend 68 to License DPR-65,changing Channel Check Requirement & Indicating Cycling of PORV Block Valve Not Required If Block Valve Closed to Meet Spec 3.4.3a or B

ML20008F854
Person / Time
Site:	Millstone
Issue date:	05/06/1981
From:	Clark R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20008F855	List: ML20008F854 ML20008F858
References
NUDOCS 8105120192
Download: ML20008F854 (8)

Text

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b UNITED STATES U S 5,p,,. (Ik NUCLEAR REGULATORY COMMISSION

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%, a.....f NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND F0WER COMPANY THE HARTFORD ELECTRIC LIGHT COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 68 License No. DPR-65 1.

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

A.

The application for amendment by Northeast Nuclear Energy Company (the licensee) dated May 5, 1981, 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,

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the provisions of the Act, and the rules and regulations of the Commission; t

C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangerino the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; l

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; i

l and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements l

have been satisfied.

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2.

Accordingly, tne 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-65 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 68, 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 s

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

Attachment:

Changes to the Technical Specifications Date of Issuance:

ATTACHMENT TO LICENSE AMENDMENT NO. 68 FACILITY OPERATING LICENSE NO. DPR DOCKET NO. 50-336 Replace the following pages of the Appendix A Technical Specifications.

with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

Pages I.

3/4 3-48 3/4 3-49 3/4 4-3 t

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s TABLE 3.3-11 (Continued)

ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels less than required by Table 3.3-11, either restore the inoperable channel (s) to OPERABLE status within 30 days or be in HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 2 - With the subcooling margin monitor INOPERABLE, determine l

the subcooling margin once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 3 - With any individual valve position indicator inoperable, obtain quench tank temperature, level and pressure infor-mation, and monitor discharge pipe temperature once per shift to determine valve position. This action is not required if the PORV block valve is closed with power removed in accordance with Specification 3.4.3.a or 3.4.3.b.

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l MILLSTONE - UNIT 2 3/4 3 48 Amendment No. f,68

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TABLE 4.3-7 F

S; ACCIDENT fl0NITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS S

CilANNEL CHANNEL INSTRUl1ENT CllECK CALIBRATION E

ri 1.

Pressurizer Water Level M

R m

2.

Auxiliary feedwater Flow Rate ti R

3.

Reactor Coolant System Subcooling fiargin lionitor M

R 4.

PORV Position Indicator (Acoustic Monitor)

M R

5.

PORV Block Valve Position Indicator N.A.

R 1"

6.

Safety Valve Position Indicator (Acoustic Monitor)

M R

u (J

0 R

R 3-(

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REACTOR COOLANT SYSTEM RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.3 Two power operated relief valves (PORVs) and their associated block valves shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

4 a.

With one or more PORV(s) inoperable, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> either restore the PORV(s) to OPERABLE status or close the associated block valve (s) and remove power from the block valve (s); otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

b.

With one or more block valve (s) inoperable, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> either.

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restore the block valve (s) to OPCRABLE status or close the block valve (s) and remove power from the block valve (s); otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

c.

The provisions of Specification 3.0.4 are not applicable.

l SURVEILLANCE REQUIREMENTS

4. 4. 3.1 Each PORY shall be deconstrated CPERABLE:

a.

Once per 31 days by performance of 1 CHANNEL FUNCTIONAL TEST, excluding valve operation, and b.

Once per 18 months by performance of a CHANNEL CALIBRATION.

4.4.3.2 Each block valve shall be demonstrated OPERABLE ance per 92 days by operating tne valve through one complete cycle of full travel. This demonstration is not required if a PORV block valve is closed and power removed to meet Specification 3.4.3 a or b.

MILLSTONE - UNIT 2 3/4 4-3 Amendment No. l7 /i% 68

REACTOR COOLANT SYST'EM

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PRESSURIZER LIMITING CONDITION FOR OPERATION 3.4.4 The pressurizer shall be OPERABLE with a steam bubble and witn at least 130 kw of pressurizer heater capacity capable of being supplied by emergency power. The pressurizer level shall be within 5% of its programmed value.

APPLICABILITY: MODES 1, 2 and 3.

ACTI,0N:

A.

With the pressurizer inoperable due to an inoperable emergency power supply to the pressurizer heaters either restore the inoperable emergency power supply 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 STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

B.

With the pressurizer otherwise inoperable, be in at least HOT STANDBY with the reactor trip breakers open within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.4 The pressurizer water level shall be determined to be within : 5% of its programmed value at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

MILLSTONE'- UNIT 2 3/4 4-4 Amendment No. 66-

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