ML20134P376

Amend 133 to License NPF-49,revising TS to Extend Surveillance Schedule from 18 Months to Each Refueling Interval

ML20134P376
Person / Time
Site:	Millstone
Issue date:	02/19/1997
From:	Mckee P NRC (Affiliation Not Assigned)
To:
Shared Package
ML20134P379	List: ML20134P376 ML20134P380
References
NUDOCS 9702250402
Download: ML20134P376 (8)

Text

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1 UNITED STATE 8 g

j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30seHem os.,...../

NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.

DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.133 License No. NPF-49 1.

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

A.

The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated July 18, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, i

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 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 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 1

requirements have been satisfied.

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9702250402 970219 PDR ADOCK 05000423 P

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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, i

and paragraph 2.C.(2) of Facility Operating License No. NPF-49 is hereby amended to read as follows:

(2)

Tachnical snecifications The Technical Specifications contained in Appendix A, as revised

,through Amendment No. 133

.tand the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. The licensee shall l

operate the facility in accordance with the Technical l

Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance, to be implemented within 90 days of issuance.

FOR THE NUCLEAR REGULATORY COMISSION

/

F/7/u Phillip F.

cKee Deputy Director for Licensing Special Projects Office Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: February 19,.1997 g

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ATTACMENT TO LICENSE AMENDMENT NO.133 FACILITY OPERATING LICENSE NO. NPF-49 l

DOCKET NO. 50-423 l

Replace the following pages of the Append'ix A,' Technical Specifications, with the attached pages. The revised pages are identified by amendment number and i

contain vertical lines indicating the areas of change.

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Insert i

3/4 4-13 3/4 4-13 i

l 3/4 4-21 3/4 4-21 3/4 4-23 3/4 4-23 i

i 3/4 4-39 3/4 4-39 3/4 4-43a 3/4 4-43a

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1 REACTOR C00UWT SYSTDI i

l RELIEF VALVE 5

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I SURVEILLANCE REQUIRDWITS 4.4.4.1 In addition to the roovirements of Specification 4.0.5, each PORV j

shall be demonstrated OPERABLE at least once each REFUELING INT,ERVAL by:

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j a.

Performance of a CHANNEL CALIBRATION, and l

b.

Operating the valve through one complete cycle of full travel during MODES 3 or 4.

4.4.4.2 Each block valve shat 1 be demonstrated OPERA 8LE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed with power removed in order to meet the requirements of ACTION b. or c. in Specification 3.4.4.

4.4.4.3 The emergency power supply for the PORVs and block valves shall be i

demonstrated OPERABLE at least once each REFUELING INTERVAL by operating the l valves through a complete cycle of full travel.

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a NI.L.LSTONE - WIT 3 3/4 4-13 Amendment No. pp.133

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3/4.4.5 REACTOR C001. ANT SYSTEM LEAKARE i

LEAKAAE DETECT 11HI SYSTEMS l

LINITING COM ITION POR OPERATION l

j 3.4.6.1 The following Reactor Coolant System Leakage Detection Systems shall be OPERABLE:

l a.

Either the Containment Atmosphere Saseous or Particulate Radioactivity Monitoring System, and

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b.

The Containment Drain Sump Level or Pumped Capacity Monitoring l

System i

j APPLICABILITY: MODES 1, 2, 3, and 4.

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With both the Containment Atmosphere Gaseous and Particulate a.

i Radioactivity Monitors IN0PERA8LE, operation may continue for up to l

30 days provided the Containment Drain Sump Level or Pumped Capacity j

Monitoring System is OPERABLE and gaseous grab samples of the i

containment atmosphere are obtained at Isast once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and i

analyzed for gross noble gas activity within the subsequent 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />; j

otherwise, be in at least NOT STAND 8Y 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 />.

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With the Containment Drain Sump Level or Pumped Capacity Monitoring System INDPERABLE, operation may continue for up to 30 days provided either the Containment Atmosphere Gaseous or Particulate i

Radioactivity Monitoring System is 0PERABLE; otherwise, be in at least NOT STAlW8Y 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 j

within the folloung 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

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SURVEILLANCE REQUIREMENTS 1

1 4.4.6.1 The Leakage Detection Systems shall be demonstrated OPERABLE by:

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a.

Containment Atmosphere Gaseous and Particulate Radioactivity i

Monitoring Systems-perfonsance of CHANNEL CHECK, CHANNEL CALIBRATION, and ANALOG CHANNEL OPERATIONAL TEST at the frequencies j

specified in Table 4.3-3, and

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b.

Containment Drain Sump Level and Pumped Capacity Monitoring System-j perfomance of CHANNEL CALIBRATION at least once each REFUELING j

INTERVAL.

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NILLSTONE - UNIT 3 3/44-21 Amendment No.17, 77. JM,133 ses

REACTgg coo m t sysTag i

GPERATI51AL LEAKARE 1

l NEVEILLA11CE REQUIRDENS l

i 4.4.5.2.1 Reactor Coolant S each of the above limits by:ystem leakages shall be demonstrated to be within i

i a.

Monitoring the containment atmosphere (<paseous or particulate) radioactivity monitor at least once per 12 w urs; I

b.

Monitoring the containment drain i mp inventory and discharge at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; l

Measurement of the CONTROLLED LEAKAGE to the reactor coolant pump c.

1 seals when the Reactor Coolant System pressure is 2250 1 20 l

least once per 31 days with the modulating valve fully open. psia at The i

provisions of Specification 4.0.4 are not applicable for entry into i

MODE 3 or 4; i

d.

Performance of a Reactor Coolant System water inventory balance at j

least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; and Monitoring the Reactor Head Flange Leakoff System at least once per e.

i 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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. 4.4.6.2.2 Each Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1 shall be demonstrated OPERABLE by verifying leakage to be within j

its limit:

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At Just once c3{n REFUELING INTERVAL, l

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i b.

Prior to enterinil MODE 2 whenever the plant has been in COLD i

SHUTDOWN for 7 c sys or more and if leakage testing has not been j

performed in the previous g months, i

c.

Prior to returning the valve to service following maintenance, l

repair or replacement work on the valve, d.

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following valve actuation due to automatic or manual l

action or flow through tae valve, and i

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As outlined in the ASME Code Section XI, paragraph IW-3427(b).

l The provisions of Specification 4.0.4 are not applicable for entry into MODE ~3 or 4.

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NI.LLSTONEIst!T 3 3/4 4 23 Amendment 110. JPP.133

am;m cootm sYsm NERPRESMEE PERTECTIM SYSTEN LINITIM COMITION POR OPERATION i

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ETION (Continued)

I In the event the PORVs, the RHR suction relief valves, or the RCS e.

vent (s) are used to mitigate an RCS pressure transient, a Special i

Report shall be prepared and submitted to.the Comnission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs, the l

RHR suction relief valves, or RCS vent (s) on the transient, and any j

corrective action necessary to prevent recurrence.

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f.

Entry into an 0PERATIONAL MODE is permitted while subject te these i

ACTION requirements.

SEVEILLANCE REQUIRDENTS i

j 4.4.9.3.1 Each PORV shall be demonstrated OPERABLE by:

a.

Performance of an ANALOG CHAMEL OPERATIONAL TEST on the PORV i

actuation channel, but excluding valve operation, within 31 days prior to entering a condition in which the PORV is required OPERABLE j

and at least once per 31 days thereafter when the PORV is required OPERA 8LE; l

b.

Performance of a CHANNEL CALI8 RATION on the PORV actuation channel at least once each REFUELING INTERVAL; and l

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c.

Verifying the PORV isolation valve is open at least once per j

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the PORV is being used for overpressure protection.

i 4.4.9.3.2 Each RHR suction relief valve shall be demonstrated OPERABLE when i

the RHR suction relief valves are being used for cold overpressure protection i

as follows:

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a.

For RHR suction relief valve 3RHS*RV8708A, by verifying at least j

once per,12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> f. hat 3RHS*MV8701A and 3RHS*NV8701C are open; b.

For IDE suction relief valve 3RHS*RV87088, by verifying at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that 3RHS*MV8702B and 3RHS*MV8702C are open; and i

c.

Testing pursuant to Specification 4.0'.5.

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4 NILLSTONE - WIT 3 3/44-39 Amendment No. 77, pp, Jpp.133 enes 1

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SWVEILLANCE REQUIRDWIT (Continued) i 4.4.11.2 Each train of the reactor vessel head vent shall be i

demonstrated OPERABLE at least once each REFUELIM INTERVAL by: pathl Verifying all annual isolation valves in each vent path are locked a.'

j in the open position, b.

Cycling each vent valve through at least one complete cycle of full j

travel from the control room, and c.

Verifying flow through the Reactor Coolant System vent paths during j

vaating.

l 4.4.11.3 Each train of the pressurizer steam space vent path shall be demonstrated OPERABLE per the app'icable requirement of i

Specifications 4.4.4.1 through 4.4.4.3 and 4.4.g.3.1.

In addition, flow shall be verified through the pressurizer steam space vent path during venting at least once each REFUELIM INTERVAL.

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J NILLSTelE - 4381T 3 3/44-43a Amendment No. 77, M.133 eau

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