ML17291A585

Amend 133 to License NPF-21,revising TS to Delete Ref to Written Relief from ASME Code Requirements Being Granted by NRC

ML17291A585
Person / Time
Site:	Columbia
Issue date:	01/05/1995
From:	Clifford J Office of Nuclear Reactor Regulation
To:
Shared Package
ML17291A586	List: ML17291A585 ML17291A587
References
NUDOCS 9501130256
Download: ML17291A585 (11)

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 WASHINGTON PUBLIC POWER SU LY SYSTEM DOCKET NO. 50-397 NUCLEAR PROJECT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

133 License.No.

NPF-2I The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the Washington Public Power Supply System (licensee) dated August 8, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (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; 2.

D.

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

Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-21 is hereby amended to read as follows:

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(2)

Technica S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.

i33 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

This amendment is effective immediately and will be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Jam s

W. Cl iffor, Senior Pr oject Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

january 5,

.1995

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. i33 TO FACILITY OPERATING LICENSE NO.

NPF-21 DOCKET NO. 50-397 Replace the following pages of the Appendix A Technical Specifications and the bases section with the enclosed pages.

The revised pages are identified by amendment number and contain vertical lines indicat'ing the areas of change.

The corresponding overleaf pages are also provided to maintain document completeness.

REMOVE INSERT 3/4 0-2 8 3/4 0-6 8 3/4 4-5 3/4 0-2 8 3/4 0-6 8 3/4 4-5

3/4. 0 APPLICABILITY LIHITING CONDITION FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation contained fn the succeeding Speckffcatfons fs required during the OPERATIONAL CONDITIONS or other conditions specfffed 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 Specfffcatfon shall exist when the requirements of the Limiting Condition for Operation and assocfated ACTION requirements are not met within the specfffed time intervals. If the Limiting Condition for Operation ks restored prior to expiration of the speckffed time intervals, completion of the Action requirements ks not required.

3.0.3 Mhen a Limiting Condition for Operation ks not met, except as provided kn the associated ACTION requirements, within one hour action shall be initiated to place the unit fn an OPERATIONAL CONDITION kn which the Specfffcatfon does not apply by placing kt, as applicable, kn:

1.

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

Mhere corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken kn accordance with the specified time limits as measured from the time of faflure to meet the Limiting Condition for Operation.

Exceptions to these requirements are stated fn the individual Speckk'icatkons.

This specification fs not applicable kn OPERATIONAL CONDITION 4 or 5.

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

This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements.

Exceptions to these requirements are stated fn the fndfvfdual Speck ffcatf ons.

WASHINGTON NUCLEAR - UNIT 2 3/4 0-1

IC B L SURVEILLANCE RE UIREHENTS 4.0.1 Surveillance Requirements shall be met during the, OPERATIONAL CONDI-TIONS 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'urveillance interval with a maximum allowable extension not to exceed 25X of the specified surveillance interval.

4.0.3 Failure to perform a Surveillance Requirement within the allowed sur-veillance interval defined by Specification 4.0.2 shall constitute noncompli-ance with 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Surveillance requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable condition shall not be made unless the Surveillance Requirement(s) associated with the Limiting Condition for Operation have been performed within the applicable surveillance interval or as otherwise specified.

This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements.

4.0.5 Surveillance Requirements for inservice inspection and testing of ASHE Code Class I, 2, 5 3 components shall be applicable as follows:

a ~

Inser vice inspection of ASHE Code Class 1, 2, and 3 components and inservice testing of ASHE Code Class I, 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 by 10 CFR 50, Section 50.55a.

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 ASHE Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ASHE Boiler and Pressure Vessel Code and applicable Addenda terminology for inser vice ins ection and testin activities Meekly Monthly quarterly or every 3 months Semiannually or every 6 months Every 9 months Yearly or annually Biennially or every two years Required frequencies for performing inservice inspection and testing activities At least once per 7 days At least once per 31 days At least once per 92 days At least once per 184 days At least once per 276 days At least once per 366 days At least once per 731 days MASHINGTON NUCLEAR UNIT 2 3/4 0-2 Amendment No.~ f33

APPLICABILITY BASES Continued ifmitfng Condition for Operation that is subject to enforcement action.

Further, the failure to perform a surveillance Kthfn the provisions of Specfficatfon 4.0.2 is a violation of a Technical Specification requfrement and fs, therefore, a reportable event under the requirements of 10 CFR 50.73(a)(2)(f)(B) because ft is a condition prohibited by the plant's Technical Specifications.

If the allowable outage time lfmfts of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or a shutdown is required to comply with ACTION requirements, e.g.,

Specfficatfon 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 completfon of a surveillance before a shut-cfown would be rcquircd to comply with ACTION requirements or before other reme-dial measures would be required that may preclude the completion of a surveil-lance.

The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel, the time required to perform the surveillance, and the safety significance of the delay in completing the required surveillance.

This provision also provides a time limit for the completion of Surveillance Requirements that become applicable as a consequence of CONDITION changes imposed by ACTION requirements and for completing Surveillance Require-ments that are applicable when an exception to the requirements of Specification 4.0.4 is allowed. If a surveillance is not completed within the 24-hour allow-

ance, the time limits of the ACTION requirements are applicable at that time.

Shen a surveillance is performed within the 24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are appli-sable 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.

How-ever, the Surveillance Requirements have to be met to demonstrate that inoperable equipment has been restored to OPERABLE status.

S ecification 4.0.4 establishes the requirement that all applicable surveill-ances must be met before entry into an OPERATIONAL CONDITION or other condition of operation specified in the Applicability statement.

Thc purpose of this specification is to ensure that system and component OPERABILITY requirements or parameter limits are met before entry into an OPERATIONAL CONDITION or other

'pecified condition for which these systems and components ensure safe operation of the facility.

This provision applies to changes in OPERATIONAL CONDITIONS or other specified conditions associated with plant shutdown as well as star tup.

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

WASHINGTON NUCLEAR - UNIT 2 8 3/4 0-5 Amendment No 88

PPL ICABILIT BASES Continued 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 CONDITION of operation.

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

This Specification also contains the requirements for the additional inspection program established in Generic Letter 88-01, "NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping."

An alternative schedule to these requirements was provided by the NRC.

This alternative schedule allows for Category 0 5 E welds to be inspected every three years, as opposed to every two cycles as specified in the Generic Letter.

(Letter, JW Clifford (NRC) to GC Sorensen (Supply System),

dated January 19, 1993, "Alternate Schedule for IGSCC Inspections (TAC No. H84714)").

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

This clarifica-tion 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 inservice inspection and testing activities.

Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASHE Boiler and Pressure Vessel Code and applicable Addenda.

The requirements of Specification 4.0.4 to perform surveillance activities before entry into an OPERATIONAL CONDITION or other specified condition takes precedence over the ASHE Boiler and Pres-sure Vessel Code provision that 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, which is not capable of performing its specified function, is declared inoperable and takes precedence over the ASHE Boiler and Pressure Vessel Code provision that allows a valve to be incapable of performing 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.

WASHINGTON NUCLEAR - UNIT 2 B 3/4 0-6 Amendment No. %~8-, "33

C OR COOL SYS BASES S

U E

E PERATUR I IT (Continued)

The pressure-temperature limit lines shown in Figures 3.4.6.1 and 3.4.6. I.c for reactor criticality and for inservice leak and hydrostatic testing have been provided to assure compliance with the minimum temperature requirements of Appendix G to 10 CFR Part 50 for reactor criticality and for inservice leak and hydrostatic testing.

3

.4.7 MAIN STEAM LINE ISOLATIO VALV S Double isolation valves are provided on each of the main steam lines to minimize the potential leakage paths from the containment in case of a line break.

Only one valve in each line is required to maintain the integrity of the containment, however, single failure considerations require that two valves be OPERABLE.

The surveillance requirements are based on the operating history of this type valve.

The maximum closure time has been selected to contain fission products and to ensure the core is not uncovered following line breaks.

The minimum closure time is consistent with the assumptions in the safety analyses to prevent pressure surges.

3 4.

.8 STRUCTURAL INTEGRITY The inspection programs for ASME Code Class 1,

2 and 3 components ensure that the structural integrity of these components will be maintained at an acceptable level throughout the life of the plant.

Access to permit inservice inspections of components of the reactor coolant system is in accordance with Section XI of the ASME Boiler and Pressure Vessel Code 1974 Edition and Addenda through Summer 1975.

The inservice inspection program for ASME Code Class 1,

2 and 3 compo-nents will be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a.

3 4.4.9 RESIDUAL HEAT REMOVAL A single shutdown cooling mode loop provides sufficient heat removal capability for removing core decay heat and mixing to assure accurate tempera-ture indication, however, single failure considerations require that two loops be OPERABLE or that alternate methods capable of decay heat removal be demonstrated and that an alternate method of coolant mixing be in operation.

WASHINGTON NUCLEAR - UNIT 2 B 3/4 4-5 Amendment No.-87-,BRr ~33

Revise NRC Letter dated:

duly 14, 1994 THIS PAGE IS BLANK INTENTIONALLY MASHINGTON NUCLEAR UNIT 2 B 3/4 4-6 Amendment No.-87-,

122