ML20009B884

Amend 70 to License DPR-65,revising Tech Specs to Incorporate Inservice Insp & Inservice Test Requirements & Remove Outmoded Requirements

ML20009B884
Person / Time
Site:	Millstone
Issue date:	07/01/1981
From:	Clark R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20009B883	List: ML20009B882 ML20009B884 ML20009B885
References
TAC-8320, NUDOCS 8107170306
Download: ML20009B884 (14)

Text

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UNITED STATES

.g NUCLEAR REGULATORY COMMISSION g i,

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WASHINGTON D. C. 20555 1 l

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NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE HARTFORD ELECTRIC __ LIGHT COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY 00CKET NO.

50-336 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 70 License No. OPR-65 1.

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

A.

The application for amendment by Northeast Nuclear Energy Company (the licensee) dated October 26, 1978, complies with the standards and requirements o'f the Atomic Energy Act of 1954, as amended (the Act) and the Commission'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 Ccamission; 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 Commission's regulations; The issuance of this amendment will not be inimical to" the D.

common defense and security or to the health and safety of the pubi f c; and E.

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

8107170306 810701 DRADOCK05000g

. 2.

Accordingly, the license is amended by changes to the Technical

. Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-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. 70, 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 Robe,rt AD k.A. -

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w ark, Chief

'perating Reactors Branch No. 3

ivision of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

July 1, 1981 e

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s ATTACHMENT TO LICENSE AMENDMENT NO. 70 FACILITY OPERATING LICENSE NO.

DPR-65 DOCKET NO.

50-336 l'eplas e 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 compl eteness.

Pages 3/a 0-2 3/4 0-3 (add new page) 3/4 4-22 3/4 4-23 3/4 4-24 3/4 4-25 (deleted) 3/4 4-26 (deleted) 3/4 4-27 (deleted) 3/4 4-28 (deleted) 3/4 4-29 (deleted) 3/4 4-30 (deleted) 3/4 4-31 (deleted) 3/4 4-32 (deleted) 3/4 4-33 (deleted)

B 3/4 0-4 (add new page)

B 3/4 4-11 B 3/4 4-12 A

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3/4 LIMITING CONDITIONS FOR OPMATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding spectficat ons is required during the OPERATIONAL MODES or other conditms specified therein; except that upon failure to meet the Limiting Conditicas 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 intarvals, 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

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to place the unit' in a MODE in which the specification'does not apply by placing it, as applicable, in:

1.

At least HOT STANDSY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, 2.

At least 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 />, and 3.

At least COLD SHUTC?WN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Where corrective meassres'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 of failure to meet the Limiting Condition for Opera tion.

Exceptions to these requirements are stated in the individual specifications.

3.0.4 Entry into an OPERATIONAL NODE or other specified condition shall not be made unless the conditions of the Limiting Condition for Operation are met without reliance on provisions contained in the ACTION requirements.

This provision shall not p

• event passage through OPERATIONAL MODES as required to comply with ACTION requirements.

Exceptiens to these require,ments are stated in the individual specifications.

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 l

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 i,o,3r source is OPERABLE: and (2) all of its redundant system (.5).,

i subsystem (s), train (s), component (s) and device (s) are OPERA 9LE, or likewise satisfy the requirements of:this specification.

Unless both conditions (1) and (2) are satisfied within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, ACTION shall be initiated to place the unit in a MODE in which the applicable Limiting Condition for Operation does not apply by placing it, as applicable, in:.

1.

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MILLSTONE

. UNIT 2 3/4.0-1 Amendment No. 62

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i APPLICABILITY.

LIMITING CONGITION FOR OPERATION (Continued) 1.

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 />, 2.

At least HOT SHUTOOWN within the following _6 hours, and 3.

At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

This specification is not applicable in MODES 5 or 6.

SURVEILLANCE REQUIREMENTS

4. 0.1 Surveillance Requirements shall be applicable during the OPERATIONAL fiODES 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 the specified time interval with:

i A maximum allowable extension not to exceed 25% of the surveillance a.

interval, and b.

The combined time interval for any 3 consecutive surveillance intervals not to exceed 3.25 times the specified surveillance interval.

4.0.3 Failure to perform a Surveillas;e Requirement within the specified time interval shall constitute a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.

Exceptions to these requirements are stated in the individual specifications.

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

4.0.4 Entry into 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.

4.0.5 Surveillance Requirements for inservice ins.pection and testing of ASME Code Class 1, 2 and 1 components shall be applicable as follows:

Inservice inspection of ASME Code Class 1, 2 and 3 components and a.

inservice testing ASME Code Class 1, 2 and 3 pumps and valves shall be performed in accordance with Section AI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 59.55a(g), except where specific written relief 1,1s been granted by the rammission pursuant to 10 CFR 50, Section 60.55a(g)

(6)(1).

MILLSTONE - UNIT 2 3/4 0-2 Amendment No. ff, 70 L

APPLICABILITY SURVEILLANCE REQUIREMENTS (Continued) b.

Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressur J Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

t ASME Boiler and Pressure Vessel Code and applicable Re qu i r a. ' frequencies for Addenda terminology for perforni<g inservice inservice inspectio,i and inspection and testing testing activities activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Yearly or annually At least once per 366 days c.

The' provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities, d.

Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Recuirements, e.

Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specifica-tion.

MILLSTONE - UNIT 2 3/4 0-3 Anendment No. 70 l

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.9.3.1 Each PORY shall be demonstrated OPERABLE by:

a.

Performance of a CHANNEL FUNCTIONAL TEST on the PORV actuation channel, but excluding valve operation, within 31 days prior to entering a condition in which the PORV is required OPERABLE and at least once per 31 days thereafter when the PORV is required OPERABLE.

b.

Performance of a CHANNEL CALIBRATION on the PORV actuation channel at least once per 18 months.

c.

Verifying the PORY isolation valve is open at least once per 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.

d.

Testing in accordance with the inservice test requirements for ASME Category C valves pursuant to Subsection IWV-3510 of Section XI of the ASME Boiler and Pressure Vessel Code 1974 Edition, and Addenda through Summer 1975.

4.4.9.3.2 The RCS vent (s) shall be verified to be open at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

• when the vent (s) is being used for overpressure protection.

• Except when the vent pathway is provided with a valve which is locked, sealed, or otherwise secured in the open position, then verify these valves open at least once per 31 days.

MILLSTONE - UNIT 2 3/4 4-21b Amendment No. 50

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 ACTION:

With the structural integrity of any ASliE Code Class 1 component (s) a.

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 0

Coolant System temperature more than 50 F above the minimum temperature required by NDT 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) prfor 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 ta within its limit or isolate the affected component from service.

d.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.4.10 In addition to the inspection requirements.for ASME Code Classes 1, 2 and 3 components delineated 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.

!!!LLSTONE - UNIT 2 3/4 4-22 Amendment No. 70

t REACTOR COOLANT SYSTEM CORE BARREL MOVEMENT LIMITING CONDITION FOR OPERATION 3.4.11 Core barrel movement shall be limited to less than the Amplitude Probability Distribution (APD) and Spectral Analysis (SA) Alert Levels for the applicable THERMAL POWER level.

APPLICABILITY: MODE 1.

ACTION:

a.

With the APD exceeding its applicable Alert Level, measure and process a spectral analysis within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

The APD Alert and Action Levels may be adjusted to reflect changes in RMS noise level resulting from neutronic effects.

b.

With the SA exceeding its applicable Alert Levels, POWER OPERATION may proceed provided the following actions are taken:

1.

APD shall be measured and processed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2.

SA shall be measured within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and at least once per 7 days thereafter; SA shall be processed at least once per 7 days.

The APD Alert and Action Levels may be adjusted to reflect changes in RMS noise level resulting from neutronic effects.

3.

A Special Report, identifying the cause(s) for* exceeding the applicable Alert Level, shall be. prepared and sub-mitted to the Commission pursuant to Specification 6.9.2 within 30 days of detection.

c.

With the APD and/or SA exceeding their applicable Action Levels, measure and process APD and SA data within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to determine if the core barrel motion is exceeding its limits.

With the core barrel motion exceeding its limits, reduce the core barrel motion to within its Action Levels within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in HOT STANDBY within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Amentent No. 77. 70 l

MILLSTONE - UNIT 2 3/4 4-23

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REACTOR COOLANT SYSTEM I

ACTION:

(Continued) d.

With the APD and/or SA data processing equipment inoperable, perform the required monitoring and data processing within the next 7 days 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 />.

SURVEILLANCE REQUIREMENTS 4.4.11.1 Baseline Monitoring Core barrel movement Alert Levels and Action Levels, as determined by APD and SA monitoring of the excore neutron detectors, shall be determined at nominal THERMAL POWER levels of -20%, 50%, 80% and 100% of RATED THERMAL POWER during the reactor startup test program; these Alert Levels and Action Levels shall be reported in a Special Report pursuant to Specification 6.9.2 within 31 days after initially reaching 100% of RATED THERMAL POWER.

4.4.11.2 Routine Monitoring Core barrel movement shall be determined to be less than the APD and SA Alert Levels by using the excore neutron detectors to measure APD an6 SA at the following frequencies:

a.

APD data shall be measured and processed at least once per 7 days, b.

SA data shall be measured and processed at least once per 31 days.

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8 MILLSTONE - UNIT 2 3/A 4-24 Amendment No. 7/, 70

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' APPLICABILITY i

BASES 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 satisfied, action is required in accordance with this speci. cation.

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

4.0.1 This specification provides that surveillance activities necessary to insure the Limiting Conditions for Operation are met and will be performed during the OPERATIONAL MODES or other conditions for which the Limiting Condi-l tions for Operation are applicable.

Provisions for additional surveillance activities to be performed without regard to the applicable OPERATIONAL MODES or other conditions are provided in the individual Surveillance Requirements.

Surveillance Requirements for Special Test Exceptions need only be performed when the Special Test Exception is being utilized as an exception to an individual specification.

4.0.2 The provisions of this specification provide allowable tolerances for performing surveillance activities beyond those specified in the nominal surveillance interval. These tolerances are necessary to provide operational flexibility because of scheduling and performance considerations.

The phrase "at least" associated with a surveillance frequency does not negate this allowable tolerance value and permits the performance of more frequent surveillance activities.

The tolerance values, taken either individually or consecutively over 3 test intervals, are sufficiently restrictive to ensure that the reliability associated with the surveillance activity is not s'ignificantly degraded beyond that obtained from the nominal specified interval.

4.0.3 The provisions of this specification set forth the criteria for determination of compliance with the OPERABILITY requirements of the Limiting Conditions for Operation.

Under this criteria, equipment, systems or compo-nents are assumed to be OPERABLE if the associated surveillance activities have been satisfactorily performed within the specified time interval.

Nothing in this provision is to be construed as defining equipment, systems or components OPERABLE, when such items are found or known to be inoperable although still meeting the Surveillance Requirements.

pILLSTONE-Unit 2 B 3/4 0-3 Amendment No. 62 i

AJPLICABILITY B.ASES 4.0.4 This specification ensures that the surveillance activities associated with a Limiting Condition for Operation have been performed within the specified time interval prior to entry into an OPERATIONAL tiODE or other applicable condition.

The intent of this provision is to ensure that surveillance activities have been satisfactorily demonstrated on a current basis as required to meet the_ OPERABILITY requirements of the Limiting Condition for Operation.

Under the terms of this specification, for example, during initial plant startup or following extended plant outages, the applicable surveillance activities must be performed within the stated surveillance interval prior to placing or returning the system or equipment to OPERABLE status.

4.0.5 This specification ensures 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 will be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda ds required by 10 CFR 50.55a.

Relief from any of the above requirements has been provided in writing by the Commission and is not a part of these Technical Specifications.

This specification includes a clarification of the frequencies for perform-ing the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda. This clarifica-tion is provided to ensure consistency in surveillance intervals throughout these Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice 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.

For example, the requirements of Specifica-tion 4.0.4 to perform surveillance activities prior to entry into an OPERATIONAL MODE or other specified applicability condition takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows pumps to be tested up to one week after return to normal operation. And for example, the Technical Specification definition of OPERABLE does not grant a grace period before a device that is not capable of performing its specified functibn is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows a valve to be incapable of pe. forming its specified function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared inoperable.

MILLSTONE - UNIT 2 B 3/4 0-4 Anendment No. 70 O

4 REACTOR COOLANT SYSTEM BASES for piping, pumps and valves.

Below this temperature, the system pressure must be limited to a maximum of 20% of the system's hydrostatic test pressure of 3125 psia.

The number of reactor vessel irradiation surveillance specimens and the frequencies for removing and testing these specimens are provided in Table 4.4-3 to assure compliance with the requirements of Appendix H to 10 CFR Part 50.

The limitations imposed on the pressurizer heatup and cooldown rates and spray water temperature differential are provided to a'sure that the pressurizer is operated within the design criteria assumed for the fati-gue analysis performed in accordance with the ASME Code requirements.

The OPERABILITY of two PORVs or an RCS vent opening of greater than 1.3 square inches ensures that the RCS will be protected from pressure transients which could exceed the limits of Appendix G to 10 CFR Part 50 when one or more of the RCS cold legs are < 275 F.

Either PORV has adequate relieving capability to protect tIie RCS from overpressurization when the transient is limited to either (1) the start of an idle RCP with the secondary water temperature of the steam generator < 43'F (31*F when measured by a surface contact instrument) above tee coolant temperature in the reactor vessel or (2) the start of a HPSI pump and its injection into a water solid RCS.

3/4.4.10 STRUCTURAL INTEGRITY The inservice inspection and testing programs for ASME Code Class 1. 2 and 3 components ensure that the structural integrity and operational readiness of these components will be maintained at an acceptable level throughout the life of the plant. These programs are in accordanc'e with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR Part 50.55a(g) except where specific written relief has been granted by the Commission pursuant to 10 CFR Part 50.55a(g)(6)(i).

MILLSTONE - UNIT 2 B 3/4 4-11 Amendment No. M, 70

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REACTOR COOLANT SYSTEM BASES 3/4.4.11 CORE BARREL MOVEMENT This specification is provided to ensure early detection of excessive core barrel movement if it should occur. Neutron noise levels are used to continually monitor core support barrel (CSB) motion. Change in notion is manifested as changes in the four excore neutron detector signals. Base-

11ne core barrel movemant Alert levels and Action Levels at nominal THERMAL POWER levels of 20%, 50%, 80% and 100% of RATED THERMAL 00WER will be determined during the reactor startup test program.

Data from these detectors is to be reduced in two forms. RMS values are computed from the Amplitude Probability Density (APD) of the signal ampli tude. These RMS magnitudes include ver(ations due both to various neutronic effects and internals motion. C?nsequently, these signals alone can only provide a gross measure of CSB motion. A were accurate assessment of CSB motion is obtained from the Auto and Cross Power Spectral Densities (PSD, XPSD), phase (p) and coherence (COH) of these signals. These data result from a Spectral Analysis (SA) of the excore detector signals.

A modification to the required monitoring program may be justified by an analysis of the data obtained and by an examination of the affected parts during the plant shutdown at the end of the first fuel cycle.

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l MILLSTONE - UNIT,2 B 3/4 4-12 Amendment No. 17, 37, 30, 70