Text

Amend 151 to License DPR-65,changing Tech Specs Per Generic Ltr 87-09 Re Applicability of LCO & Surveillance Requirements of Tech Specs 3.0 & 4.0
	ML20070E393
Person / Time
Site:	Millstone
Issue date:	02/26/1991
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; Northeast Nuclear Energy Co (NNECO), Connecticut Light & Power Co, Western Massachusetts Electric Co
Shared Package
ML20070E402	List: ML20070E393;
References
	GL-87-009, DPR-65-A-151 NUDOCS 9103050477
	Download: ML20070E393 (37)
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NORTHEAST NUCLEAR _ ENERGY _C,0MPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE_ WESTERN MASSACHUSETTS ELECTRIC LDAPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR _ POWER STATION, UNIT NO. 2 AMENDMENT _ TO _ FACillTY _ OPERATING _ LICENSE Amendment No.1S1 License No. OPR-65 1.

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

A.

The app (lication for amendnert by Northeast Nuclear Energy Connany, et al.

the licensee), dated August 9,1990, as supplemented y

letter dated January 10, 1991 complies with the standards and requirements of to Atomic Energy Act of 1954, as amended (the Act),

and the Comnission'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 Consission; 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 Conrnission's regulations; i

D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the pubitc; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Connission's regulations and all applicable requirements have been satisfied.

9103050477 910226 DR ADOCK 0500 6

. 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license arendnent, 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 Appendix A, as revised through Amendment No.151, 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 issuance, to be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

. sh

Stolz, Director (i)

Pr et Directorate !.A ision of Reactor Projects - !/11 Office of Nuclear Rc4Cior Regulation Attachnent:

Changes to the Technical Specifications Date of Issuance: February 26, 1991 o.-

. - -,. - ~, -,

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1 ATTACHMENT 70 LICENSE AMENDMENT _ NO.151 FACILITY OPERATING _ LICENSE _NO._DPR-65 DOCKET NO. 50-336 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendnent number and contain vertical lines indicating the areas of change.

Remove Insert 3/4 0-1 3/4 0 1 3/4 0-2 3/4 0-2 3/4 1-25 3/4 1-25 3/4 3-26 3/4 3-26 3/4 3-31 3/4 3-31 3/4 3-32 3/4 3-32 3/4 3-36 3/4 3-36 3/4 3-43 3/4 3-43 3/4 3-46 3/4 3-46 3/4 3-50 3/4 3-50 13/4 3-56 3/4 3-56 3/4 4-3 3/4 4-3 3/4 4-13 3/4 4-13 3/4 4-21a 3/4 4-21a 3/4 4-22 3/4 4-22 3/4 4-23 3/4 4-23 3/4 6-6 3/4 6-6 3/4 7-1 3/4 7-1 3/4 7-4 3/4 7-4 3/4 7 19 3/4 7-19 3/4 7-33 3/4 7-33 3/4 7-37 3/4 7-37 3/4 7-39 3/4 7-39 3/4 7-41 3/4 7-41 3/4 11-2 3/4 11-2 3/4 11-4 3/4 11-4

-3/4 11-5 3/4 11-5 3/4 11-6 3/4 11-6 8 3/4 0-1 B 3/4 0-1 B 3/4 0-2 B 3/4 0-2 B 3/4 0-3 8 3/4 0-3 8 3/4 0-4 83/40-4 8 3/4 0-5 B 3/4 0 6 0 3/4 0-7 yerg

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4 3/4 LIMITING CONDITIONS FOR OPERATION AND SVRYIILLANCE R[fM1EW Mli 3/4.0 APPLICMILlJJ LIMli!NG CONDITION FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding specifications is required during the OPERATIONAL MODES or other conditions specified therein: except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met.

3.0.2 Noncompliance with a specification shall exist when the requirements of the limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals.

If the limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

3.0.3 When a limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within one hour ACTION shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in:

1.

At least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , 2.

At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and 3.

At least COLD SHUTOOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time it is identified that a 1.imiting Condition for Operation is not met.

Exceptions to these requirements are stated in the individual specifications.

3.0.4 Entry into an OPERATIONAL H0DE '>r other specified condition shall not be made when the conditions for the timiting Condition for Operation are not met and the associated ACTION requires a shutdown if they are not met within a specified time interval.

Entry into an OPERATIONAL MODE or specified condition may be made in accordance with ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.

3.0.5 When a system, subsystem, train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided: (1) its corresponding normal or emergency power sourca is OPERABLE: and (2) all of its redundant system (s),

subsysted '

'ain(s), component (s) and device (s) are OPERABLE, or likewise satisfy u,,equirements of this specification.

Unless both conditions (1) and (2) are satisfied within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , ACTION shall be initiated to plate the unit in a H00E in which the applicable Limiting Condition for Operation does i

not apply by placing it, as applicable, in:

MILLSTONE - UNIT 2 3/4 0 1 Amendment Nos. (22,151

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APPllCABILITY 1

LIMITING CONDITION FOR OPERATION (Continued) l 1.

At least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .-

.2.

At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and g

_3.

At _least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

This specification is not appli_ cable in MODES 5 or 6.

I SVRVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES or-other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within that'specified time interval with:

I a.

A maximum allowable extension not to exceed 25% of the surveillance time interval, and b.

The combined time interval for any 3 consecutive surveillance k

intervals not to exceed 3.25 times the specified surveillance

-interval.

-4.0.3

Failure to perform a Surveillance Requirement within the allowed surveillance interval. defined by Specification 4.0.2, shall constitute a failure to meet the OPERABILITY requirements for a limiting Condition for Operation. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed.

The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the ccmpletionlof the surveillance when the allowable outage-time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Surveillance Requirements do not have to be_ performed on inoperable equipment.

4.0.4 Entry isto an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Requirement (s) associated with the

-Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.-

4.0.5 Surveillance' Requirements for inservice inspection and-testing of l

ASME Code Class 1,12 and 3-components shall be applicable as follows:

a.

Inservice: inspection of-ASME Code Class-1, 2 and 3 components-and inservice-testing ASME Code Class 1, 2,- and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required oy 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10-CFR 50, Section 50.55a(g)(6)(i).

MILLSTONE --UNIT 2-'

3/4 0-2 Amendment Nos. 62,70,151 l

RE ACTIVITY CONTROL SYSTEMji EQSITION INDICATOR CHANE LS (Continuedl LIMITING CONDITION FOR OPERATION (Continued) b)

The CEA group (s) with the inoperable indicator is fully

inserted, and subsequently maintained fully

inserted, while maintaining the withdrawal sequence and THERMAL POWER level required by Specification 3.1.3.6 and when this CEA group reaches its f Jlly inserted position, the " Full In* limit of the CEA with the inoperable position indicator is actuated and verifies this CEA to be fully inserted.

Subsequent operation shall be within the ilmits of Specification 3.1.3.6.

4.

If the failure of the position indicator channel (s) is during

STARTUP, the CEA group (s) with the inoperable position indicator channel must be moved to the " Full Out" position and verified to be fully withdrawn via a " Full Out" indicator within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

c.

With a maximum of one reed switch position indicator channel per group or one pulse counting position indicator channel per group inoperable and the CEA(s) with the inoperable position indicator channel at either its fully inserted position or fully withdrawn position, operation may continue provided:

1.

The position of this CEA is verified immediately and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereaf ter by its " Full in" or " Full Out" limit (as applicable).

2.

The fully inserted CEA group (s) containing the inoperable position channel is subsequently maintained fully inserted, and 3.

Subsequent operation is within the limits of Specification 3.1.3.6.

d.

With one or more pulse counting position indicator channels inoperable, operation in H0 DES I and 2 may continue for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months provided all of the reed switch position indicator channels are OPERABLE.

SURVEILLANCE REQUIREMENTS 4.1.3.3 Each position indicator channel shall be determined to be OPERABLE by verifying the pulse counting position indicator channels and the reed switch position indicator channels agree within 6 steps at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except uuring time intervals when the Deviation circuit is inoperable, then compare the pulse counting position indicator and reed switch position indicator channels at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , t

MILLSTONE - UNIT 2 3/4 1-25 Amendment No. 151 I

INSTRUMENTATION 3.4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING LIMITING CONDITION FOR OPERATION 1

3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm / trip setpoints within the specified limits.

APPLICABlulyY.t As shown in Table 3.3 6.

ACTION:

a.

With a radiation monitoring channel alarm / trip setpoint exceeding the value shown in Table 3.3 6, adjust the setpoint to within the limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or declare the channel inoperable.

b.

With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS A.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the modes and at the frequencies shown in Table 4.3-3.

MILLSTONE - UNIT 2 3/4 3-26 Amendment No. 151

INSTRUMENTATION LIMITING CONDITION FOR OPERATION (Continued)

An OPERABLE quadrant symetric incore detector segment group shall consist of i

a minimum of three OPERABLE rhodium incore detectar segments in 90'F symmetric fuel assemblies, j

APPLICABILITY: When the incore detection system is used for:

a.

Monitoring the AZIMUTHAL POWER TILT, b.

Recalibration of the excore neutron flux detection system, or c.

Monitoring the UNR000E0 INTEGRATED RADIAL PEAKING FACTOR or the linear heat rate.

EllQH:

With the incore detection systou inoperable, do not use the system for the above applicable monitoring or calibration functions.

The provisions of specifications 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENT 4.3.3.2 The ir. core detection system shall be demonstrated OPERABLE:

a.

By performance of a CHANNEL CHECK within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to its use and at least once per 7 days thereafter when required for:

1.

Monitoring the AZIMUTHAL POWER TILT.

2.

Recalibration of the excore neutron flux detection system.

3.

Monitoring the UNR000E0 INTEGRATED RADIAL PEAKING FACTOR or the linear heat rate.

b.

At least once per 18 months by performance of a CHANNEL CALIBRATION operation which exempts the neutron detectors but includes all electronic components.

The neutron detectors shall be calibrated prior to installation in the reactor core.

l-MILLSTONE ONIT 2 3/4 3 31 Amendment No. /5, l#, '51

INSTRUMENTATION i

l SEISMIC INSTRUMENTATION LIMITING CONDITION FOR OPERATION l

3.3.3.3 The seismic monitoring instrumentation channels shown in Table 3.3 7 shall be ODERABLE.

APPLICABillTY:

ALL MODES.

AC. TION:

I a.

With the number of OPERABLE seismic monitoring channels less than required by Table 3.3-7 restore the inoperable channel (s) to OPERABLE status within 30 days.

The provisions of Specification 3.0.3 are not applicable.

b.

With one or t.. ore seismic monitoring channels inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the system to OPERABLE status.

SURVEILLANCE REQUIREMENTS 4.3.3.3 Each of the above seismic monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CilANNEL L

CAllBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-4.

t i

MILLSTONE - UNIT 2 3/4 3-32 Amendment No. 151

1 INSTRUMENTATION METEOROLOGICAL INSTRUMENTATION 1

LIMITING CONDITION FOR OPERATION 3.3.3.4 The meteorological monitoring instrumentation channels shown in Table 3.3-8 shall be OPERABLE.

APPllCABillTY:

ALL MODES a.

With the number of CPERABLE meteorological monitoring channels less than required by Table 3.3 8, suspend all release of gaseous radioactive material from the radwaste gas decay tanks until the inoperable channel (s) is restored to OPERABLE status.

The provisions of Specification 3.0.3 are not applicable.

b.

With one or more required meteorological monitoring channels inoperable for more than 7 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status.

SURVEILLANCE RE0VIREMENTS 4.3.3.4 Each meteorological monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CAllBRATION operations at the frequencies shown in TABLE 4.3-5.

7 MILLSiONE - UNIT 2 3/4 3-36 Amendment No. 151

l INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.7 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3 10 shall be OPERABLE.

APPllCABillfY: Whenever equipment in that fire detection zone is required to be OPERABLE.

MJJDS:

With the number of OPERABLE fire detection instrument (s) less than the minimum number of OPERABLE requirements of Table 3.310:

a.

Within I hour establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour unless the instrument (s) is located inside the containment, then inspect the containment at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the containment air temperatures at least once per hour at the locations listed in Specification 4.6.1.5.

b.

Restore the inoperable instrument (s) to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.6.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the ir,strument(s) to OPERABLE status, c.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.3.3.7.1 Each of the above required fire detection instruments which are accessible during plant operation shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST.

Fire detectors which are not accessible during plant operation shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the previous 6 months.

4.3.3.7.2 The circuitry associated with the supervisio. of the above fire detection instruments and circuits, per NFPA 72 0, shall be demonstrated OPERABLE at least once per 6 months.

4.3.3.7.3 The nonsupervised circuits, associated with detector alarms, between the instrument and the control room shall be demonstrated OPERABLE at least once per 31 days.

MILLSTONE UNIT 2 3/4 3 43 Amendment No. U, JJD, JJJ,151

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l INSTAllATLQ!i ACCIDENT MONITORING LIMITING CONDITION FOR OPERATION 3.3.3.8 The accident monitoring instrumentation channels shown in Table 3.3 11 shall be OPERABLE.

l APFLICABILITY: MODES 1, 2, and 3.

PC1.LQ!i:

a.

Actions per Table 3.3 11.

i SURVEILLANCE REQUIREMENTS 4.3.3.8 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CAllBRATION operations at the frequencies shown in Table 4.3-7.

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l MILLSTONE - UNIT 2 3/4 3 46 Amendment No. H, 151 l

i INSlF<UMENTATIM RADIDACTIVE L10VID EHLUENT MONITORING _INSTRUMENTAUM LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.312 shall be OPERABLE with applicable alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.

The setpoints shall be determined in accordance with methods and parameters as described in the ODCH.

APPLICABillTY: As shown in Table 3.3 12.

ACTION:

a.

With-a radioactive liquid ef fluent monitoring instrumentation channel alarm / trip wipoint less conservative than required by the above specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b.

With the number of channels less than the minimum channels operable requirement, take the ACTION shown in Table 3.3-12.

Exert best efforts to restore the inoperable monitor to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Effluent Report why thu inoperability was not corrected in a timely

manner, Releases need not be terminated after 30 days provided the specified actions e.re continued, c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAllBRATION. and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3412.

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-MILLSTONE - UNIT 2 3/4 3 50 Amendment No. R4,151 l

1 INSTRUMENTATIM i

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION QMITINGCONDITIONFOROPERATION 3.3.3.10 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.313 shall be OPERABLE with applicable alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded.

The setpoints shall be determined in accordance with methods and parameters as descrit,ed in the ODCM.

APPLICABILITY: As shown in Table 3.3-13.

ACllM:

a.

With a radioactive gaseous ef fluent monitoring instrumentation l

channel alarm / trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, or l

declare the channel inoperable, or changa the setpoint so it is acceptably conservative.

b.

With the number of channels less than the minimum channels (OPERABLE requirement, take the ACTION shown in Table 3.3-13.

Exert best efforts to restore the inoperable monitor to OPERABLE status within 30 days and, if nnsuccessful, explain in the next Semiannual Effluent Report why the inoperability was not corrected in a timely manner.

Releases need not be terminated after 30 days provided the specified actions are continued.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel l

shall be demonstrated OPERABli by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3 13.

l i

MILLSTONE - UNIT 2 3/4 3-56 Amendment No. R4.151

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:

a.

With one or more PORV(s) inoperable, within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUT 00WN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With one or more block valve (s) inoperable, within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months either restore the block valve (s) to OPERABLE 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE0VIREMENTS 4.4.3.1 Each PORV shall be demonstrated OPERABLE:

a.

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

Once per 18 months by performance of a CHANNEL CAllBRATION.

4.4.3.2 Each block valve shall be demonstrated OPERABLE once per 92 days by operating the valve through one complete cycle of full travel.

This demonstration is not required if a PORY 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. f5, Ef, JE 151

t REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY llMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to:

a.

s 1.0 pCi/ gram DOSE EQUIVALENT l-131, and b.

$ 100/E #Ci/ gram.

APPLICABILITY: MODES 1, 2, 3, 4, and 5.

ACTION:

MODES 1, 2, and 3*:

a.

With the specific activity of the primary coolant > 1.0 pCi/ gram DOSE EQUIVALENT l-131 but within tie allowable limit (below and to

+

the lef t of the line) shown on Figure 3.41, operation may continue for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Entry into an OPERATIONAL H0DE or other specified condition is permitted pursuant to Specification 3.0.4 when subject to this ACTION statement.

b.

With the specific activity of the primary coolant > 1.0 sti/ gram DOSE EQUIVALENT l-131 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval or exceeding the limit line shown on Figure 3.41, be in HOT STANDBY with T,yg < 515'F within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , c.

With the specific activity of the primary coolant > 100/t pci/ gram, be in HOT STANDBY with T,,,9 < 515'F withtn 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

MODES 1, 2, 3, 4 and 5:

d.

With the specific activity of the primary coolant > 1.0 pCi/ gram DOSE EQUIVALENT l-131 or > 100/E #Cl/ gram, perform the sampling and analysis requirements of item 4 a) of Table 4.4-2 until the specific activity of the primary coolant is restored to within its limits.

With T,yg > 515'p, HILLSTONE - UNIT 2 3/4 4 13 Amendment No. 7, JJJ, J15,151

... =. - -

_ - _ - -~

i REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LlHITING COND: TION FOR OPERATION 3.4.9.3 At least one of the following overpressure protection systems shall be OPERABLE-1

)

Two power operated relief valves (PORVs) with a lift setting of a.

i 450 psig, or

]

b.

A reactor coolant system vent of 1 1.3 square inches.

APPLICABillTY: When the temperature of one or more of the RCS cold legs is 1 275'F, except when the reactor vessel head is removed.

ACTION:

a.

With one PORV inoperable, either restore the inoperable PORV to OPERABLE status within 7 days or depressurize and vent the RCS through a 1 1.3 square inch vent (s) within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; maintain the RCS in a vented condition until both PORVs have been restored to OPERABLE status, b.

With both PORVs inoperable, depressurize and vent the RCS through a 1 1.3 square inch vent (s) within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; maintain the RCS in a

^

vented condition until both PORVs have been restored to OPERABLE

status, c.

In the event either the PORVs or the RCS vent (s) are used to mitigate a RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days.

The report shall describe the circumstances initiating the transient, the effect of the PORVs or vent (s) on the transient and any corrective action necessary to prevent recurrence.

HILLSTONE - UNIT 2 3/4 4-21a Amendment No. 50, 151

i REACTOR COOLANT SYSTEM STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.4.10 The structural integrity of ASME Code Class 1, 2, and 3 components shall be maintained in accordance with Specification 4.4.10.

APPLICABILITY: ALL MODES AtI10N:

a.

With the structural integrity of any ASME Code Class 1 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature more than 50'F above the minimum temperature required by NOT considerations.

b.

With the structural integrity of any ASME Code Class 2 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature above 200'F.

c.

With the structural integrity of any ASME Code Class 3 component (s) not conforming to the above requirements, restore the structural integrity of the affected component to within its limit or isolate the affected component from service.

SURVEILLANCE REQUIREMENTS 4.4.10 In addition to the inspection requirements for ASME Code Classes 1, 2, and 3 components delinaated in Specification 4.0.5, each Reactor Coolant Pump flywheel shall be inspected per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.

1 MILLSTONE UNIT 2 3/4 4 22 Amendment No. 79,151

i REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM VENTE LIMITING CONDITION FOR OPERATION 1

3.4.11 At least one reactor coolant system vent path consisting of at least two valves in series capable of being powered from emergency buses shall be OPERABLE and closed at each of the following locations:

a.

Reactor Vessel head b.

Pressurizer stream space APPLICABILITY: MODES 1, 2, 3, and 4 ACTIDN:

a.

With the Pressurizer vent path inoperable, STARTUP and/cr POWER OPERATION may continue provided that 1) the inoperable vent path is maintained closed with power removed from the valve actuator of all the valves in the inoperable vent path and ii) one power operated relief valve (PORV) and its associated block valve is OPERABLE; otherwise, restore either the inoperable vent path or one PORV and its associated block valve to OPERABLE status within 30 days, or submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the path to OPERABLE status, b.

With the Reactor Vessel Head vent path inoperable, STARTL'P and/or POWER OPERATION may continue provided that the inoperable vent path is maintained closed with power removed from the valve actuator of all the valves in the inoperable vent path; restore the Reactor Vessel Head vent path to OPERABLE status within 30 days or submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the path to OPERABLE status.

SURVEILLANCE RE0VIREMENTS 4.4.11 Each reactor coolant system vent path shall be demonstrated OPERABLE at least once per 18 months by:

1.

Verifying all manual isolation valves in each vent path are locked in the open position.

2.

Cycling each valve in the vent path through at least once complete cycle of full travel from the control room during COLD SHUTDOWN or REFUELING.

3.

Verifying flow through the reactor coolant vent system vent paths during venting during COLD SHUTDOWN or REFUELING.

MILLSTONE - UNIT 2 3/4 4-23 Amendment No. 70,72,12p,151

~.

CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 The containment air lock shall be OPERABLE with:

a.

Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed, and b.

An overall air lock leakage rate of s 0.05 L, at P, (54 psig).

APPilCABILITY: MODES 1, 2, 3 and 4.

ACTION:

a.

With one containment air lock door inoperable:

1.

Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock the OPERABLE air lock door closed.

2.

Operation may then continue until performsnce of the next required overall air lock leakage test provided that the OPERABLE air lock door is verified to be 1ccked closed at least once per 31 days.

3.

Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHU100WN within the follcwing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

4.

Entry into an OPERATIONAL MODE or other specified condition under the provisions of Specification 3.0.4 shall not be made if the inner air lock door is inoperable, b.

With the containment air lock inoperable, except as the result of an inoperable air lock door, maintain at least one air lock door closed; restore the inope able air lock to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

a.

After each opening, except when the air lock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , by verifying no l

detectable seal leakage be pressure decay when the volume between the door seals is pressurized to greater than or equal to 25 psig I

for at least 15 minutes.

MILLSTONE - UNIT 2 3/4 6-6 Amendment No. #.151 1

3/4.7 PLANT SYSJJH$

L4. 7.1 TURBINE CY(1(

SAFETY VAlyLS LIMITING CONDIT10N FOR OpERAT10N 3.7.1.1 All main steam line code safety valver shall be OPERADLC, APPLICABillTY:

MODES 1, 2, and 3.

&Cll.03:

a.

With both reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves inoperable, operation in MODES 1, 2, and 3 may proceed provided, that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the inoperable valve is restored to OPERABLE status or the Power leve! High trip setpoint is reduced per Table 3.7-1; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.7.1.1 Each main steam line code safety valve shall be demonstrated OPERABLE, with lif t settings and orifice sizes as shown in Table 4.7-1, in accordance with Specification 4.0.5.

MILLSTONE - UNIT 2 3/4 7 1 Amendnent No. H. Jf7,151

M,NT. SY11Llit lfLGLIARY FEEDWATER PUMPS tlMITING CONDITIONS FOR OPERATION 3.7.1.2 At least three steam generator auxiliary feedwater pumps shall be OPERABLE with:

a.

Two feedwater pumps capable of being powered from separate OPERABLE emergency busses, and b.

One feedwater pump capable of being powered from an OPERABLE steam supply system.

APPLKABillIYt MODES 1, 2, and 3.

AtlLOS:

a.

With one auxiliary feedwater pump inoperable, restore the required auxiliary feejwater pumps to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTOOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , b.

With two auxiliary feedwater pumps inoperable be in at least HOT STANDBY within 6

hours and in HOT SHUT 00WN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.

Entry into an OPERATIONAL MODE or other specified condition under the provisions of Specification 3.0.4 shall not be made with three auxiliary faedwater pumps inoperable.

SURVEILLANCE REQUIREMENTS 4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE:

a.

At least once per 31 days by:

1.

Starting each pump from the control room.

2.

Verifying that:

a)

Each tr.otor driven pump develops a discharge pressure of 21070 psig on recirculation flow, and b)

The steam turbine driven pump develops a discharge pressure of 2 1080 psig on recirculation flow when the secondary steam supply pressure is greater than 800 psig.

The provisions of Specification 4.0.4 are not applicable for entry into Mode 3.

MILLSTONE UNIT 2 3/4 7-4 Amendment No. EJ. /E, 99.151

PLANT SYSTEMS 3/a.7.7 SEALED S0QBCE CONTAMINATION

IMITING CONDITION FOR OPERATION 3.7.7.1 Each sealed source containing radioactive material either in excess of those quantities of byproduct material listed in 10 CFR 30.71 or 0.1 microcuries, including alpha emitters, shall be free of 2 0.005 microcuries of removable contamination.

APPLICABILITY:

AT ALL TlHES.

i aC1103:

[

a.

Each sealed source with removable contamination in excess of the above limit shall be immediately withdrawn from use and:

i 1.

Either decontaminated and repaired, or r

2.

Disposed of in accordance with Commission Regulations.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.7.7.1.1 T.est Reauirementi - Each sealed source shall be tested for leakage and/or contamination by:

a.

The licensee or f

b.-

Other persons specifically authorized by the Commission or an Agreenent State.

The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.

4.7.7.1.2 Test Freautatici - Each category of sealed sources -shall be tested at the frequencies described below.

a.

Sources in use (excludina startuo sources previousiv tub.iected to core ficx)

-. At least once per six months for all sealed sources containing radioactive material:

3 P

t r

MILLSTONE - UNIT 2 3/4 7-19 Amendment No. 151

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PLANT SYSTEMS 3/4.7.9 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYST[3 LIMITING CONDITION FOR OPERATION 3.7.9.1 The fire suppression water system shall be OPERABLE with:

a.

Three high pressure pumps, each with a capacity of at least 1800 gpm, with their discharge aligned to the fire suppression

header, b.

Two water supplies, each with a minimum containe.d volume of 200,000 gallons, and c.

An OPERABLE flow path capable of taking suctio'. fiom the fire water tanks and transferring the water through distrQution piping with OPERABLE sectionalizing control or isolation vaives to the yard hydrant curb valves and the first valve ahead of the water flow alarm device on each sprinkler, hose standpipe or spray system riser required to be OPERABLE per Specifications 3.7.9,2 and 3.7.9.3.

APPLICABILITY: At all times.

ACTION:

a.

With one pump and/or one water supply inoperable, restore the inoperable equipment to OPERABLE status within 7 days or, in lieu of any other report required by Specificatien 6.6.1, prepare and submit t Special Report to the Commission pursuant to Specification 6.9.2 within the nee 30 days outlining the plans and procedures to be used to provide for the loss of redundancy in this system.

The provisions of Specification 3.0.3 are not applicable, b.

With two pumps inoperable, establish a continuous fire watch of the turbine building with backup fire suppression equipment within I hour; restore the inoperable equipment to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Repert to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the equipment to OPERABLE status.

The provisions of Specification 3.0.3 are not applicable.

MILLSTONE - UNIT 2 3/4 7-33 Amendment No. JE, /J, JJJ,151

PLANT SYSTEMS SPRAY AND/OR SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.9.2 The following spray and/or sprinkler systems shall be OPERABLE:

a.

Diesel Generator Rooms b.

Diesel Generator Day Tank Rooms c.

Cable Vault (Aux. Building) 1.

Sprinkler 2.

Deluge d.

Cable Vault (Turbine Building) e.

Hydrogen Seal Oil Unit f.

Turbine Building Northeast Corner g.

Turbine Building 31'6"/14'6" - North h.

Turbine Building 31'6"/14'6" - South i.

Lube Oil Room J.

Aux. Building (-45'6") General Area k.

Aux. Building (14'6") Truck Access 1.

Turbine Bearing m.

Steam Generator feed Pumps AP.,LICABillTY:

Whenever equipment in the spray / sprinkler protected areas is P

required to be OPERABLE.

ACTION:

a.

With one or more of the above required spray and/or systems inoperable, establish a continuous fire watch with backup fire suppression equipment for the unprotected area (s) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.6.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the rause of the inoperability and the plans and schedule for restoring the system to OPERABLE status, b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENT 4.7.9.2 Each of the above required spray and/or sprinkler systems shall be demonstrated OPERABLE:

MILLSTONE - UFiT 2 3/4 7-37 Amendment No. 75, /3, JJp, JJJ,151

f PLANT SYST[tij FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION 3.7.9.3 The fire hose stations shown in Table 3.7 2 shall be OPERABLE.

APPLICABillTY: Whenever equipment in the areas protected by the fire hose stations is required to be OPERABLE.*

ACTION:

a.

With one or more of the fire hose stations shown in Table 3.7 2 inoperable, route an additional equivalent capacity fire hose to the unprotected area (s) from an OPERABLE hose station within I hour or establish a continuous fire watch with backup fire suppression equipment for the unprotected area (s).

If the inoperable hose station (s) is not the primary means of fire suppression, then route the additional fire hose (s) or establish a continuous fire watch with fire suppression equipment within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

The provisions of Specification 3.0.3 are not applicable.

t SURVEILLANCE REQUIREMENTS 4.7.9.3 Each of the fire hose stations shown in Table 3.7 2 shall be demonstrated OPERABLE:

a.

At least once per 31 days by visual inspection of the station to assure all required equipment is at the station.

The exception to the above will be the containment hose stations.

The equipment will be located outside containment except when the unit is in cold shutdown.

b.

At least once per 18 months by:

1.

Removing the hose for inspection and re racking, and 2.

P.eplacement of all degraded gaskets in couplings, c.

At least once per 3 years by:

1.

Partially opening each hose station valve to verify valve OPERABILITY and no flow blockage.

2.

Conducting a hose hydrostatic test at a pressure at least 50 psig greater than the maximum pressure available at that hose station.

Containment hose stations shall be operable in MODE 5 when required to support maintenance activities and MODE ?.

MILLSTONE - UNIT 2 3/4 7-39 Amendment No. AB, U p,151

PLANV ESTEMS 3/4.7.10 PENETRATION FIRE BARR11M LIMITING CONDITION FOR OPERAi!ON 3.7.10 All fire rated assemblies (walls, floor /cellings, cable tray enclosures, and other fire barriers) separating safety related fire areas or separating portions of redundant systems important to safe shutdown within a fire area and all sealing devices in fire rated assembly penetrations (fire doors, fire windows, fire dampers, cable, piping, and ventilation duct penetration seals) shall be OPERABLE.

APPLICABILITY: At all times unless otherwise determined that the separation of safety-related fire areas or separating portions of redundant systems important to safe shutdown within a fire area is not required based on the MODE of operation.

El!QU:

a.

With one or more of the above required fire rated asserblies and/or penetration sealing devices inoperable, within I hour:

1.

Determine that the fire areas / zones on both sides of the affected fire rr.ted assembly and/or penetration sealing device are monitored by either an OPERABLE fire detection or automatic suppression system at the fire barrier and establish a fire watch patrol that inspects both areas at least once per hour, E

2.

Establish a continuous fire watch on at least one side of the affected fire rated assembly and/or penetration seal, E 3.

Temporarily repur the inoperable fire rated assembly and/or sealing device and classify it as temporary.

All temporary or inoperable fire rated assemblies and/or sealing devices shall be permanently repaired within 30 days, or implement ACTION 1 or 2 above.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.10 The above required fire rated assemblies and penetration sealing devices shall be verified to be OPERABLE by a visual inspection:

a.

At least once per 18 months for fire doors and fire dampers, b.

At least once per 18 months for fire barrier penetration seals, on at least 10% of the total number of penetration seals.

If any of i

the penetration seals in the inspection sample are found to be inoperable, then an additional 10% sample of the total number of penetration seals shall be visually inspected.

Sampling and inspection shall continue until all of the seals in a sample are found OPERABLE or 100% of the seals are inspectcd.

l c.

Prior to returning a fire rated assembly and/or penetration sealing device to OPERABLE status following repairs or maintenance.

MILLSTONE - UNIT 2 3/4 7-41 Amendment No. M. JJp iS1 i-

l MD10 ACTIVE EFFlVENTS DOSE t10W1Q1 LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to any REAL MEMBER OF THE PUBLIC from radicactive materials in liquid effluents from Unit 2 released from the site (see figure 5.1 1) shall be limited:

a.

During any calendar quarter to s 1.5 mrem to the total body and to 1 5 mrem to any organ, and b.

During any calendar year to 1 3 mrem to the total body and to 1 10 mrem to any organ.

APPLICABillTY:

At all times.

811101{:

a.

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the remainder of the calendar year so that the cumulative dose or dose commitment to any REAL MEMBER OF THE PUBLIC from such releases during the calendar year is within 3 mrem to the total body and 10 mrem to any organ, b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2.1 0.gse Calculations.

Cumulative dose contributions from liquid effluents shall be determined in accordance w 'h Section II of the REMODCH.

i 4.11.1.2.2 Relative accuracy of conservat, of the calculations shall be confirmed by performance of the Radiological Environmental Muitoring Program as detailed in the REMODCH.

s MILLSTONE - UNIT 2 3/4 11 2 Amendment No. JM,iS1

]

)

__._m RAD 10 ACTIVE EFFLUENTS DOSE. NOBLE GAS [i SURVEILLANCEREQUIREMENTS 3.11.2.2 The air dose offsite (see Figure 5.1-1) due to noble gases released from Unit 2 in gaseous effluents shall be limited to the following:

a.

During any calendar. quarter, to s 5 mrad for gamma radiation - and s 10 mrad for beta radiation; b.-

During any calendar year, to - 1 10 mrad for gamma radiation and s 20 mead for beta radiation.

APPLICABILITY: At all times.

ACTION:

a.

With the calculated air dose from radioactive noble gases in gaseaus effluents exceeding any of the above limits, prepare and submit to the' Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(:;) for exceeding the limit (s) and defines the corrective actions to be taken to reduce -

the releases of radioactive noble gases in gaseous ef t c

'ts during the remainder of the current calendar quarter and ing the

. remainder of the current calendar year so that the cumulative dose during.the calendar year is within 10 mrad for gamma radiation and 20 mrad for beta radiation.

b.

The provisions of Specification 3.0.3 are not applicable.

\\

SURVEILLANCE REQUIREMENTJ 4.11.2.2.1 Qgse Calculation 1.

Cumulative dose contributions for the current 1

calendar quarter and current calendar year shall be determined in accordance with Sectinn II of the REMODCM once every 31 days.

44.11.2.2 2 Relative L c-e or conservatism of the calculations shall -be confikmed by performancs le Radiological Environmental Monitoring Program as detailed inJSection I or tne REM 00CM.-

c

- MILLSTONE - UNIT 2 3/4 11-4 Amendment No. J#f,151

RADI0 ACTIVE EFFLUENTS DOSE.

RADie 'DitiLSm RAD 10 ACTIVE MATERIAL IN PARTICULATE FORM.

AND s

RADIONUCLIDES OTHER THAN NOBLE GASES LIMITING CON 0lTION FOR OPERATION 3.11.2.3 The dose to inv REAL MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium and rtJioactive materials in particulate form with half lives greater than 8 days in gaseous effluents from Unit 2 released offsite (see Figure 5.1-1) shall be limited to the following:

During any calendar quarter to s 7.5 mrem to any organ; b.

During any calendar year to 1 15 mrem to any organ.

APPLICABILITf: At all times.

ACTION:

a.

Witn the c al c,' a t ed dose from the release of radioiodines, radioactivo masu lais in particulate form, or radionuclides other than than noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases during the remainder of the current calendar quarter and during the remainder of the calendar year so that.the cumulative dose or dose commitment to any REAL MEMBER OF THE PUBLIC from such releases during the calendar year is within 15 mrem to any organ.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3.1 Dose Cal"ulations.

Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with Section II of the REM 00CH once every 31 days.

4.11.2.3.2 Relative accuracy or conservatism of the calculotions shall be confirmed by performance of the Radiological Environmental Monitoring Program as detailed in Section l of the REM 00CM.

MILLSTONE - UNIT 2 3/4 11-5 Amendment No. Jpf,151

~._

h RADIOACTIVE EFFLUENTS 3/4 11.3 TOTAL DOSE

, LIMITING CONDITION FOR OPERATION 3.11.3 The dose of dose commitment to a REAL MEMBER OF THE PUBLIC from the Millstone Site is limited to s 25 mrem to the total body or any organ (except the thyroid, which is limited to 5 75 mrem) over a period of 12 consecutive months.

APPLICABILITY:

At all times.

ACTION:

a.

With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 3.11.1.2, 1.11.2.2, or 3.11.2.3, prepare and submit a Special Report to the Conunission pursuant to Specification 6.9.2 and limit the subsequent releases such that the dose or dose commitment to any REAL MEMBER OF THE PUBLIC from the Millstone Site is limited to s 25 mrem to the total body or any organ (except thyroid, which is limited to 5 75 mrem) over 12 consecutive months.

This Special Report shall include an analysis which demonstrates that radiation exposures to any REAL MEMBER OF THE PUBLIC from the hillstone Site (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard.

If the estimated doses exceed the above limits, the special report shall include a request for a variance in accordance with the provisions of 40 CFR 190.

Submittal of the report is considered a timely request and a variance is granted until staff action on the request is

complete, b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.3 Dose Lalculat' Cumulative dose contributions from liquid and ga gaseous effluents ant unrect radiation from the Hillstone Site shall be determined in Specifications 4.11.1.2.1, 4.11.2.2.1 and 4.11.2.3.1 and in accordance with Section II of the REM 0DCM once per 31 days.

MILLSTONE - UNIT 2 3/4 11-6 Amendment No. J0,4,151

a

\\

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE00lREMENTS 3/4.0 APPLICABill1Y BASES Specification 3.0.1 throuah 3.0.4 establish the general requirements applicable to Limiting Conditions for Operation.

These requirements are based on the requirements for Limiting Conditions for Operation stated in the Code of Federal Regulations, 10CFR50.36(c)(2):

" Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility.

When a-limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specification until-the condition can be met."

Soecification 3.0,1 establishes the Applicability statement within each individual specification as the requirement-for when (i.e., in which OPERATIONAL MODES or other specified conditions) conformance to the Lituiting.

Conditions for Operation is required for safe operation of the facility. The ACTION requirements establish those remedial measures that must be taken within specified time limits when the requirements of a Limiting Condition for Operation are not_ met.

There are two basic types of ACTION requirements.

The first specifies'the remedial measures that permit continued operation of the facility which is not further_ restricted by the time limits of the ACTION requirements.

In this case, conformance to the ACTION requirements provides an acceptable level of safety for unlimited continued operation as long as the ACTION requirements continue to be met. -The second type of ACTION requ_irement-specifies a time lirit in which conformance to the conditions of the Limiting Condition for Operation must be met.

This time limit is the allowable outhge time to restore an inoperable system or component to OPERABLE status or for restoring _

parameters within'specified limits.

If these actions are not-completed within the allowable outage time limits, a shutdown.is required to place the facility

-in a MODE or condition in which the specif' cation no longer applies.

It is-not intended that the shutdown ACTION requirements be used.as an operational convenience which permits groutine) voluntary removal of a system (s) or component (s) from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.

The specific time limits of the ACTION requirements are applicable from the point in time it-is idr.ntified that a Limiting Condition for Operation is not met. The time limits of the ACTION requirements are also applicable when a system or component is -removed from service for surveillance testing or.

_ investigation of operational problems.

Individual specifications may include a specified time limit for the completion of a Surveillance Requirement when equipment is removed from service.

In this case, the allowable outage time MILLSTONE - UNIT 2 B 3/4 0-1 Amendment Nos. 62, 151

N 3/4.0 APPLICABILITY BASES (Cnn't) limits of ACTION requirements are applicable when thi:. limit expires if the surveillance has not been completed. When a shutdown is required to comply with ACTION requirements, the plant may have entered a MODE in which a new specification becomes applicable, in this case, the time limits of the ACTION requirements would apply from the point in time that the new specification becomes applicable if the requirements of the Limiting Condition for Operation are not met.

Soecification 3.0.2 establishes that noncompliance with a specification exists when the requirements of the Limiting Condition for Operation are not met and the associated ACTION requirements have not been implemented within the specified time interval.

The purpose of this specification is to clarify that (1) implementation of the ACTION requirements within the specified time interval constitutes compliance with a specification and (2) completion of the remedial measures of the ACTION requirements is not required when compliance with a Limiting Condition of Operation is restored within the time interval specified in the associated ACTION requirements.

Soecification 3.0.3 estaotishes the shutdown ACTION requirements that must be implemented when a Limiting Condition for Operation is not met and the condition is not specifically addressed by the associated ACTION requirements.

The purpose of this specification is to delineate the time limits for placing the unit in a safe operation defined by the Limiting Conditions for Operation and its ACTION requirements.

It is not intended to be used as an operational convenience which permits (routine) voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable. This time permits the operator to coordinate the reduction in electrical generatdon with the load dispatcher to ensure the stability and availability of the electrical grid.

The time limits specified to reach lower MODES of operation permit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the cooldown capabilitics of the facility assuming only the minimum required equipment is OPERABLE.

This reduces thermal stresses on components of the primary coolant system and the potential for a plant upset that could challenge safety systems under conditions for which this specification applies.

If remedial measures permitting limited continued operation of the facility under the provisions of the ACTION requirements are completed, the shutdown may be terminated.

The time limits of the ACTION requirements are applicable from the point in time it is identified that a Limiting Condition for Operation is not met.

Therefore, the shutdown may be terminated if the ACTION requirements have been met or the time limits of the ACTION requirements have not expired, thus providing an allowance for the completion of the required acti m

{

l MILLSTONE - UNIT 2 8 3/4 0-2 Amendment Nos. 62, 151

APPLICABILITY BASES The time limits of Specification 3.0.3 allow 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months for the plant to be in the COLD SHUTDOWN MODE when a shutdown is required during the POWER MODE of operation, if the plant is in a lower MODE of operation when a shutdown is required, the time limit for reaching the next lower MODE of operation applies.

However, if a lower M0DE of operation is reached in less time than allowed, the total allowance time to reach COLD SHUTDOWN, or other applicable MODE, is not reduced.

For example, if H0T STANDBY is reached in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , the time aH owed to reach HOT SHUTDOWN is the next 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months becaure the total time to rea:h HOT SHUTDOWN is not reduced from the allowable limit of 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months .

Therefore, if remedial measures are completed that would permit a return to POWER operation, a penalty is not incurred by having to reach a lower MODE of operation in less than the total time allowed.

The same principle applies with regard to the allowable outage time limits of the ACTION requircments, if compliance with the ACTION requirements for one specificatien results in entry into a MODE or condition of operation for another specification in which the requirements of the Limiting Condition for Operation are not met, if the new specification becomes applicable in less time than specified, the difference may be added to the allowable outage time limit of the second specification.

However, the allowable outage time limits of ACTION requirements for higher MODE of operation may not be used to extend the allowable outag; time that is applicable when a Limiting Condition for Operation is not met in a lower MODE of operation.

The shutdown requirements of Specification 3.0.3 do not apply in MODES 5 and 6, because the ACTION requirements of individual specifications define the remedial measures to be taken.

Specification 3.0,4 establishes limitations on MODE chsnges when a Limiting Condition for Operation is not met.

It precludes placing the facility in a higher MODE of operation when the requirements for a Limiting Condition for Operation are not met and continued norcompliance to these conditions would result in a shutdown to comply with the ACTION requirements if a change in MODES were permitted.

The purpose of this specification is to ensure that facility operation is not initiated or that higher MODES of operation are not entered when corrective action is being taken to obtain compliance with a specification by restoring equipment to OPERABLE status or parameters to specified limits.

Compliance with ACTION requiraments that permit continued operation of the facility for an unlimited period of time provides an acceptable level of safety for continued operation without regard to the status of the plant before or after a MODE change. Therefora, in this case, entry into an OPERATIONAL MODE or other specified condition may be made in accordance. tith the provision of the ACTION requirements.

The provisions of this specification should not, however, be interpreted as endorsing the failure to exercise good practice in restoring systems or components to OPERABLE status before plant startup.

I 1

MILLSTONE - UNIT 2 B 3/4 0-3 Amendment Nos. 62,151

APPLICABILITY BASES (Con't)

When a shutdown is required to comply with ACTION requiremew, the provisions oi opccification 3.0.4 do not apply because they would delay placing the facility in a lower MODE of operation.

Soecification 3.0.5 delineates what additional conditions must be satisfied to permit operation to continue, consistent with the ACTION statements for power sources, when a normal or emergency power source is not OPERABLE.

It specifically prohibits operation when one division is inoperable because its normal or emergency power source is inoperable and a system, subsystem, train, component or device in another division is inoperable for another reason.

The provisions of this specification permit the ACTION statements associated with individual systems, subsystems, trains, components, or devices to be consistent with the ACTION statements of the associated electrical power source.

It allows operation to be governed by the time limits of the ACTION statement associated with the Limiting Conditior for Operation for the normal or emergency power source, not the individual ACTION statements for each system, subsystem, train, component or device that is determined to be inop-erable solely because of the inoperability of its normal or emeroency power source.

For example, Specification 3.8.1.1 requires in part that two emergency diesel generators be OPERABLE. The ACTION statement provides for a 72-hour out-of-service time when one emergency diesel generator is not OPERABLE.

If the definition of OPERABLE were applied without consideration of Specification 3.0.5, all systems, subsystems, trains, components and devices supplied by the inoperable emergency power source would also be inoperable.

This would dictate invoking the applicable ACTION statement for each of the applicable limiting Conditions for Operation. However, the provisions of Specification 3.0.5 permit the time limits for continued operation to be consistent with the ACTION statement for the inoperable emergency diesel generator instead, provided the other specified conditions are satisfied.

In this case, this would mean that the corresponding normal power source must be OPERABLE, and all redundant systems, subsys & s, trains, components, and devices must be OPERABLE, or otherwise satisfy Specification 3.0.5 (i.e., be capable of performing their design function and have at least one normal or one emergency power source OPERABLE).

If they are not satisfied, action is required in accordance with this specification.

As a further example, Specification 3.8.1.1 requires in part tk.c two physically independent circuits between the offsite transmission r r. work and the onsite Class IE distribution system be OPERABLE.

The ACTION >tatement provides a 24-hour out-of-service time when both required offs'ee circuits are not OPERABLE.

If the definition of OPERABLE were applied wit'out consider-ation of Specification 3.0.5, all systems, subsystems, train, components and devices supplied by the inoperable normal power sources, t,oth of the offsite circuits, would also be inoperable. This would dictate invoking the applic-able ACTION statements for each of the applicable LCOs. However, the provi-sions of Specification 3.0.5 permit the time limits for continued operation to MILLSTONE - UNT 2 B 3/4 0 4 Amendment Nos. 70, 151

4 BASES (Con't) be consistent with' the ACTION statement for_ the inoperable normal power

. sources instead, provided the other specified conditions are satisfied. 'In case, this would mean that for one division the emergency power source must be OPERABLE (as must be the components supplied by the emergency power source) and all redundant systems, subsystems, trains, components and devices in the other division must be OPERABLE, or likewise satisfy Specification 3.0.5 (i.e., be capable of performing their design functions and have an emergency power source OPERABLE).

In other words, both emergency power sources must be OPERABLE and all redundant systems, subsystems, trains, components and devices in both divisions must also be OPERABLE.

If these conditions are not satis-fied, action is required in accordance with this specification.

In MODES 5 and 6 Specification 3.0.5 is not applicable, and thus the individual ACTION statements for each applicable Limiting Condition for Operation in these MODES must be adhered to.

Soecification 4.0.1 throuah 4.0.5 establish the general requirements applic-able to Surveillance Requirements. These requirements are based on the Surveillance Requirements stated in the Code of Federal Regulations, 10CFR50.36(c)(3):

" Surveillance requirements are requiriments relating to test, cali-

~ bration, or inspection to ensure that the racessary quality of systems and components is maintained, that facility optration will be within safety limits, and.that the limiting conditions o operation will be met."

Specification 4.0.1 establishes the requirement that surveillances must be performed during the OPERATIONAL MODES re other conditions for which the requirements of the Limiting Conditions for Operation apply unless otherwise stated in an' individual Surveillance Roquirements. The purpose of this specification-is to' ensure that surveillances are performed to verify the operational status of systems and comaonents.and that parameters are within specified limits to ensure safe operttion of the facility when the plant is in a MODE or other specified condition ior which the associated Limiting Conditions for Operation are applicable.

Surveillance Requirements do not have to be performed when the facilit( is in an OPERATIONAL MODE for which the requirements of the associated Limiti19 Condition for Operation do not apply-unless otherwise specified. The Surviillance Requirements associated with a Special-Test Exception are only applic'ble when the Special Test Exception is used as an allowable exception to the r 54uirements of a specification.

Specification 4.0.2 establishes the condi, ions under which the specified time interval-for Surveillance Requirements may be extended.

Item a, permits an allowable extension:of the nt.nial surveillance interval to facilitate surveil-

-lance-scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or maintenance activities.

Item b. limits the use of-the provisions of item a. to ensure that it is not used repeatedly to extend the survei_11ance interval beyond that specified.

The limits of Specification 4.0.2 are based on engineering judgment and the recognition that the most probable result of-any particular surveillance being performed is the verification of conformance with the Surveillance Requirements. These provi-sions are sufficient to ensure that the reliability ensured through

- MILLSTONE - UNIT 2 B 3/4 0-5 Amendment No. 151

3/4.0 APPLICABILITY BASES (Con't) surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.

Soecification 4.0.3 establishes the failure to perform a Surveillance Require-ment within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure to meet the OPERABillTY requirements for a limiting Condition for Operation. Under the provisions of this specification, systems and components are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily performed within the specified time interval.

However, nothing in this provision is to be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable although still meeting the Surveillance Requirements.

This specification also clarifies that the ACTION requirements are applicable when Surveillance Requirements have not been completed within the allowed surveillance and that the time limits of the ACTION requirements apply from the point in time it is identified that a surveillance has not been performed and not at the time that the allowed surveillance interval was exceeded.

Completion of the Surveillance Requirement within the allowable outage time limits of the ACTION requirements restores compliance with the requirements of Specification 4.0.3.

However, this does not negate the fact that the failure to have performed the surveillance within the allowed surveil-lance interval, defined by the provisions of Specification 4.0.2, was a violation of the OPERABILITY requirements of a Limiting Condition for Operation.

If the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or a shutdown is required to comply with ACTION requirements, e.g., Specification 3.0.3, a 24-hour allowance is provided to permit a delay in implementing the ACTION requirements. This provides an adequate time limit to complete Surveillance Requirements that have not been performed. The purpose of this. allowance is to permit'the completion of a surveillance before a shutdown is required to comply with ACTION requirements or before other remedial measures would be required that may preclude completion of a surveil-lance.

The basis for this allowance includes consideration for plant condi-tions, adequata planning, availability of personnel, the. time required to perform the surveillance, and the safety significance of the delay in complet-ing the required surveillance.

If a surveillance is not completed within the 24-hour allowance, the time limits of the ACTION requirements are applicable at that time. When a surveillance is performed within the 24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is terminated.

Surveillance Requirements do not have to be performed on inoperable equipment because the ACTION requirements define the remedial measures that apply.

However, the Surreillance Requirements have to be met to demonstrate that inoperable equipment has been restored to OPERABLE status.

MILLSTONE - UNIT 2 B 3/4 0-6 Amendment No. 151

1 3/4.0 APPLICABILITY BASES (Con't)

Specification 4.0.4 establishes the requirement that all applicable surveillances must be met before entry into an OPERATIONAL H0DE or other condition of operation specified in the Applicability statement.

The purpose of this specification is to ensure that system and component OPERABILITY requirements or parameter limits are met before entry into a MODE or condition for which these systems and components ensure safe operation of the facility.

This provision applies to changes in OPERATIONAL MCDES or other specified conditions associated with plant shutdown as well as startup.

Under the provisions of this specification, the applicable Surveillance Requirements must be performed within the specified surveillance interval to ensure that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage.

When a shutdown is required to comply with ACTION requirements, the provisions of Specification 4.0.4 do not apply because this would delay placing the facility in a lower MODE of operation.

Specification 4.0.5 establishes the requirement that inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a.

These requirements apply except when relief has been provided in writing by the Commission.

This specification includes a clarification of the frequencies for performing the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda.

This clarification is provided to ensure consistency in surveillance intervals throughout the Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservico inspection and testing activities.

Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda. The requirements of Specification 4.0.4 to perform surveillance activities before entry into an OPERATIONAL MODE or other specified condition takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows pumps and valves to be tested up to one week after return to normal operation. The Technical Specification definition of OPERABLE does not allow a grace period before a component, that is not capable of performing its specified function, is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being declared inoperable.

MILLSTONE - UNIT 2 B 3/4 0-7 Amendment No. 151

ML20070E393

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