Text

Summary of 860910 Meeting W/B&W Owners Group,Utils,Inel & Eg&G in Bethesda,Md Re B&W Owners Group Tech Spec Committee. Agenda & Handout Encl
	ML20211E453
Person / Time
Issue date:	10/15/1986
From:	Mozafari B; Office of Nuclear Reactor Regulation
To:	; Office of Nuclear Reactor Regulation
References
	NUDOCS 8610220452
	Download: ML20211E453 (123)
	v • d • e

t October 15 1986 0

c@hb LICENSEE: B&W Owners Group

SUBJECT:

SL'MMARY OF MEETING HELD CN SEPTEMBER 10, 1986.

WITH THE B&W OWNERS GP0UP On September 10, 1986, the NRC staff met with representatives of the B&W Owners Group Technical Specification Committee in Bethesda, Maryland. The list of attendees and the agenda are enclosed as Enclosures 1 and 2, respectively.

The purpose of the meeting was to discuss the format and content of proposed Containment Systems Technical specifications submittal under the Technical Specification Improvement Program. The meeting was organized as a working session to discuss the proposed changes point by point. The. B&W Owners Group sought acceptance of B&WOG style and format for new Tech. Specs. and detailed technical comments from NRC staff on Containment LCOs, surveillance, and Bases. contains the licensee's handout material.

B&WOG stated they hoped for some indication from the NRR staff that their program was headed in the right direction.

Staff provided assurance that although the Commission policy statement has not been issued on the Technical Specification Improvement Program, the B&WOG program appeared to be headed in the right direction.

The staff agreed to discuss with OGC how taking the tabular list of containment isolation valves out of the TSs will affect the license when the list is revised.

The scheduling of the next meeting was deferred until after the NRR staff has met to discuss how the review of the B&WOG material should proceed.

/S/

Brenda Mozafari, Project Manager PWR Project Directorate No. 6 Division of PWR Licensing-B

Enclosures:

1.

Attendees List 2.

Agenda 3.

Licensee Handouts cc w/cnclosures:

See next page 72 D M (W

PBD#6 PMorpfari ;cf 9//j/86 8610220452 861015 DR TOPRP EMVII

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Mr. W. S. Wilgus Crystal River Unit ?!o. 3 Nuclear Florida Power Corporation Generating Plant cc:

Mr. R. W. Neiser State Planning and Development Senior Vice President Clearinghouse and General Counsel Office of Planning and Budget Florida Power Corporation Executive Office of the Governor P. O. Box 14042 The Capitol Building St. Petert-burg, Florida 33733 Tallahassee, Florida 32301 Mr. P. McKee Mr. F. Alex Griffin, Chairman Nuclear Plant Manager Board of County Commissioners Florida Power Corporation Citrus County P. O. Box 219 110 North Apopka Avenue Crystal River, Florida 32629 Inverness, Florida 36250 Mr. Robert'B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Resident Inspector U.S. Nuclear Regulatory Commission 15760 West Powerline Street Crystal River, Florida 32629

. Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Mr. Allan-Schubert, Manager Public Health Physicist Department of Health and Rehabilitative Services 1323 Winewood Blvd.

Tallahassee, Florida 32301 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301

't Attorney Genera.1 Department of Legal Affairs The Capitol Tallahassee, Florida 32304

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SUMMARY

DISTRIBUTION Licensee: B&W Owners Group l

Copies also sent to those people on service (cc) list for subject plant (s).

Docket File NRC PDR L PDR PBD-6 Rdg JStolz BMozafari OGC-MNBB 9604 Edordan BGrimes ACRS-10 NRC Participants SBryan RFerguson JWermiel LBeltracchi WPaulson i

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ATTENDEES LIST FOR MEETING HELD ON SEPTEMBER 10, 1986 NAME AFFILIATION 4

Dan Green Florida Power Corporation Robert Gill Duke Power Company

- George Jacks B&W Robert A. Turner B&W l-Frank McPhatter BSW Hugh Clark B&k' Courtney W. Smyth GPU Nuclear Charles N. Alan Toledo Edison Patrick C. Rogers AP8L

- Ron Columbo SMUD G. L. Plumlee NRC/F08 Sam Bryan NFC/TSCB i

i Robert Gerguson-NRC/PEICSB Jerry Wermiel NRC/PEICSB Walt Paulson NRC/PWR-B Leo Beltracchi NRC/PEICSB Brenda Mozafari NRC/PWR-B i

Wayne Roberts INEL/EG8G Jim Riley WOG/SNUPPS s

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NGENDA FRC/B&WOG Technical Specification Committee Meeting September 10.-1986 t

Openi ng Pema rks........................................... Brenda Moze fari, NRP/PWR-B 1

Bob Gill, D?Co Objectives of the Meeting................................. Bob Gill', DPCo j

Presentation of Containment Technical Specifications...... George Jacks, B8W l

i informal Discussion and Comments on LCOs,. Surveillance.... Staff and B&WOG and Bases Tech Spec Committee

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Define Open Items and Actions.............................Brenda Mozafari, NRR/PWR-B and Establish Next Meeting Bob Gill, DPCo-U t

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I"LOWNERS GROUP Technical Specification Committee l

l NRC/B&WOG Technical Specification Comrnittee Meeting September 10,1986 1

Babcock &Wilcox a McDermott company

TABIE OF (DNTINTS Tab No.

1 Objectives of Meeting 2

How to Handle Former Technical Specifimtions 3

How to Handle Surveillance 4

Ground Rules for New IIDs 5

Application of Separation Criteria 6

Engineered Safety Features LOOS and Surveillances for Containnent Systens c

IID & Surveillance Package For B&W SPD. T.S. 3.6.1.1 a.

C b.

IID & Surveillance Package For B&W SPD. T.S. 3.6.1.3 c.

100 & Surveillance Package For B&W STD. T.S. 3.6.1.5 d.

IXD & surveillance Package For B&W SPD. T.S. 3.6.1.6 IID & Surveillance Package Ebr B&W SID. T.S. 3.6.1.8 e.

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IXD & Surveillance Package For B&W STD. T.S. 3.6.2.1 & 3.6.2.3 LOO & Surveillance' Package For B&W STD T.S. 3.6.2.2 g.

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IXD & Surveillan Package For B&W SID T.S. 3.6.4

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NRC/B&WOG TECHNICAL SPECIFICATION COMMITTEE MEETING-September 10, 1986 4

1 OBJECTIVES OF THE MEETING i

o Obtain acceptance of B&WOG style and format for new-Tech Specs 1

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e Obtain detailed technical comments from Staff on Containment LCOs, Surveillances, and Bases e

Define open items and actions e

Establish next' meeting d

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FORMER TECHNICAL SPECIFICATIONS f

BACKGROUND Application of the Selection Criterion to present technical specifications (STS and Custom) results in many requirements not being included in New STS.

These are termed former Tech Specs.

It is desirable by. operators that such requirements be located in a manner such that they are easily located.

It is recognized that in all cases, procedures exist to operate and maintain that equipment that had been under the regulatory control of Tech Specs.

FIRST PROPOSED SOLUTION 1.

Chapter 16 of the FSAR was chosen as a single location for all former

" Tech Specs..It is presently unused by operating plants.

2.

A new style and format was selected similar to that used for Tech Specs.

3.

A process to maintain was modeled after that presently described in Chapter 6 of Tech Specs fpr procedure control. This results in administrative control of former Tech Specs.

(See Attachment 1)

( gROBLEMS WITH FIRST SOLUTION l.

A new program was unnecessarily created. The process was duplicative of the process on procedures.

SECOND PROPOSED SOLUTION 1.

Revise STS Section 6.8 which requires procedures for certain elements of plant operation to refer to those Selected Licensee Commitments listed in FSAR Chapter 16.0.

2.

Delete references to the previously proposed process to maintain as the process is described in TS Section 6.8.

3.

Use the same style and format as in first proposed solution. Testing requirements, bases need not be included as they are already i'n procedures, FSAR respectively.

4.'

Former TS requiring plant shutdown are revised consistent with BWOG position.

Sscond Proposed Solution looks like Attachment 2.

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a McDermott compan) 3315 Old Forest Road June 3, 1986

- P 0. Box 10935 ESC-367

. Lyng> burg. VA24506 0935

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DPC-86-331,r8, cnVE;.

385-2000 10?$

1986 i

DUKE POWER CO.

LICENSING To:

B&W Owners Group Technical Specification Committee

Subject:

Review of Draft FSAR Chapter 16

Dear Committee Members:

The draft of proposed Chapter 16 prepared by Bob Gill is attached

.for your review.

Please return written comments or marked-up text to me by June 23.

If you have any questions, please call.

Very truly yours, WOW R. A. Turner Project Manager Owners Group Engineering Services RAT /leh Attachment Tech Spec Committee D.

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,_ M _ NUCLEAR' STATION FINAL SAFETY ANALYSIS REPORT CHAPTER 16 SELECTED LICENSEE COMMITMENTS S

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LIST OF EFFECTIVE PAGES O

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Chapter 16 - Selected Licensee Commitments (NEW TITLE)

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16.0 SELECTED LICENSEE COMMITMENTS Y

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16.1 INTRODUCTION

16.2 PROCESS TO MAINTAIN 16.3 DEFINITIONS 16.4 COMMITMENTS RELATED TO REACTOR COMPONENTS 16.5 COMMITMENTS RELATED TO REACTOR COOLANT SYSTEM COMPONENTS 16.6 COMMITMENTS RELATED TO ENGINEERED SAFETY FEATURES (NON-ESF SYSTEMS) 16.7 COMMITMENTS RELATED TO INSTRUMENTATION 16.8 COMMITMENTS RELATED TO ELECTRICAL POWER SYSTEMS 3

. 16.9 COMMITMENTS RELATED TO PLANT SYSTEMS t

16.10 COMMITMENTS RELATED TO STEAM AND POWER CONVERSION SYSTEMS 16.11 COMMITMENTS RELATED TO RADIOACTIVE WASTE MANAGEMENT 4

16.12 COMMITMENTS RELATED TO RADIATION PROTECTION 16.13 COMMITMENTS RELATED TO REFUELING OPERATIONS (OTHER SECTIONS AS DEEMED NECESSARY) 1 p t- +

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16.0 SELECTED LICENSEE COMMITMENTS

16.1 INTRODUCTION

This chapter provides a single location in the FSAR where certsin selected licensee commitments are presented. The initial content of this chapter is based on the results of application of a set of criteria to determine content of technical specifications.

Those technical specification requirements which did not meet the criteria were relocated initially to this chapter.

Additionaloperationalrelatedcommitments,asselectedb(euhm m ] may be located in this chapter.

It is the intent of this chapter to provide direction to the plant operating staff regarding systems that are a part of the licensing basis, as described in the FSAR, but are not of such a level of importance that they need to be under the rigorous control provided by technical specifications.

This guidance includes testing requirements for certain systems, and remedial actions to be taken in the event the system is not wholly capable of performing its design function. A bries for the commitment is also provided. Reference is also provided to specific sections of the FSAR where the information relative to the commitment is further described.

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16.2 PROCESS TO MAINTAIN 16.2.1 The content of Chapter 16.0, Selected Licensee Commitments will be approved by the or his designee.

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set) 16.2.2 Changes to the content of this chapter shall be prepared by a qualified individual / organization. The preparation of each proposed change shall be reviewed by an individual / group other than the individual / group which prepared the proposed change, but who may be from the same organization as the individual / group which prepared the proposed change.

Proposed changes shall be approved by the{ WVe se, fr s s o nlt sh]

16.2.3 16.2.4 Proposed changes shall become effective upon review and acceptance by a qualified individual / organization.

16.2.5 Changes to this chapter shall be submitted to the NRC in accordance with the requirements of 10CFR50.71 (Annual FSAR Update)

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16.2.6 Reports documenting the reviews / approvals of changes to this chapter shall be maintained. Copies shall be provided to the andthhuclear-SafetyReview

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4 16.3 DEFINITIONS (To the extent practical, use definitions as present in existing Tech Specs. Revise / supplement as necessary.)

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FORMER TECH SPEC LOGO 16.6 COMMITMENTS RELATED TO ENGINEERED SAFETY FEATURES (NON-CSF SYSTEMS)

System: Hydrogen Control Commitment 16.6.1: The HYDROGEN RECOMBINER should be functional.

APPLICABILITY: Modes 1,2 DEGRADED REMEDIAL TESTING CONDITION ACTION REQUIREMENTS I

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ADMINISTRATIVE CONTROLS f

SAFETY LIMIT VIOLATION (Continued) c.

The Safety Limit Violation Report shall be submitted to' the Commission, the NSRB and the Vice President, Nuclear Production, within 14 days of the violation; and d.

Critical operation of the unit shall not be resumed until authorized by the Commission.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:

The applicable procedures recommended in Appendix A of Regulatory a.

Guide 1.33, Revision 2, February 1978; b.

The applicable procedures required to implement the requirements of NUREG-0737; c.

Security Plan implementation;*

d.

Emergency Plan implemerftstion; i

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PROCESS CONTROL PROGRAM implementation; l'

f.

OFFSITE DOSE CALCULATION MANUAL implementation; g.

Quality Assurance Program for effluent and environmental monitoring; and i

h.

Selected Licensee Commit,xbents contained in FSAR Chapter 16.0.

l 6.8.2 Each procedure of Specification 6.8.1 above, and changes thereto, shall be reviewed and approved by the Station Manager; or by:

(1) the Operating Superintendent, (2) the Technical Services Superintendent, (3) the Maintenance Superintendent, or (4) the Snerintendent of Integrated Scheduling as previously designated by the Station Manager; prior to implementation and shall be reviewed periodically as set forth in administrative procedures.

l 6.8.3 Temporary changes to procedures of Specification 6.8.1 above may be made l

provided:

l a.

The intent of the original procedure is not altered; b.

The change is approved by two members of the plant management staff, at least one of whom holds a Senior Operator license on the unit i

affected; and

Review and approval may be performed by the Superintendent of Station Services.

l 6-14 Amendment No.

(Unit 1) l Amendment No.

(Unit 2) 19 2 - 2.

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FINAL SAFETY ANALYSIS REPORT l

t CHAPTER 16 SELECTED LICENSEE COMMITMENTS

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TABLE OF CONTENTS I

SECTION TITLE PAGE NO.

NO.

16.0 SELECTED LICENSEE COMMInfENTS 16.1-1

16.1 INTRODUCTION

16.1-1 16.2 RELATION TO TECHNICAL SPECIFICATIONS 16.2-1 16.3 DEFINITIONS 16.3-1 16.4 COMMITMENTS RELATED TO REACTOR COMPONENTS 16.4-1 16.5 COMMIDfENTS RELATED TO REACTOR COOLANT SYSTEM COMPONENTS 16.5-1 16.6 COMMITMENTS RELATED TO ENGINEERED SAFETY FEATURES 16.6-1 16.7 COMMITMENTS RELATED INSTRUMENTATION

-16.7-1 16.8 COMMITMENTS RELATED TO ELECTRICAL POWER SYSTEMS 16.8-1 16.9 COMMIDfENTS RELATED TO PLANT SYSTEMS 16.9-1 16.10 COMMITMENTS RELATED TO STEAM AND POWER CONVERSION SYSTEMS 16.10-1 16.11 COMMITMENTS RELATED TO RADIOACTIVE WASTE MANAGEMENT 16.11-1 16.12 COMMIDfENTS RELATED TO RADIATION PROTECTION 16.12-1 16.13 COMMITMENTS RELATED TO REFUELING OPERATIONS 16.13-1 e

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16.0 SELECTED LICENSEE COMMITMENTS f

16.1 INTRODUCTION

This chapter provides a single location in the FSAR where certain selected licenses commitments are presented. The initial content of this chapter is based on the results of application of a set of criteria to determine the content of technical specifications. Those technical specification requirements which did not meet the criteria were relocated initially to this chapter.

Additional operational related commitments, as selected by the (Station Superintendent] may be located in this chapter.

It is the intent of this chapter to provide information regarding systems that are a part of the licensing basis, as described in the FSAR, but are not of such a level of importance that they need to be under the rigorous control provided by technical specifications.

This chapter includes testing requirements for certain systems, and remedial actions to be taken in the event the system is not wholly capable of performing its design function. A bases for the commitment is also provided. Reference is also provided to specific sections of the FSAR where the information relative to the commitment is further described.

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16.2 RELATION TO TECHNICAL SPECIFICATIONS This chapter of the [

] FSAR contains a listing of Selected Licensee Conunitments for which [

] Technical Specification 6.8 (Procedures and Programs) requires written procedures to be established, implemented, and maintained.

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SURVEILLANCE REQUIREMENTS BACKGROUND Regulation requires surveillance requirements for LCO's be contained in TS.

Many surveillance requirements are written in extensive detail such that even minor changos require an amendment to the license.

Many surveillance intervals should be relaxed as the equipment is over-tested.

Some LCO's have no explicit surveillance, some surveillances do not have an explicit LCO, some surveillances centain LCO's rather than acceptance criteria.

FIRST PROPOSED SOLUTION The features of the first proposed solution are summarized in-the following:

9 1.

New format that drives a one-to-one correlation to an LCO.

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Minimal details contained in TS.

3.

Concept of Surveillance Plan to contain details.

4.

New process te maintain Surveillance Plan.

5.

New front matter to Section 4.0 of TS that includes surveillance related definitions.

(See Attachment 1)

PROBLEMS WITH FIRST SOLUTION:

1.

Created c. new process that is different than that used to change station procedures and is different than that used to meet 10CFR50.59.

2.

Surveillance requirements in TS lacked specified acceptance criteria.

3.

It created snother document that really is not necessary.

SECOND PROPOSED SOLUTION:

1..

Transform existing STS surveillance requirements into the Surveillance Plan page format. Title of form would now become Generic Surveillance.

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2.

Rewrite Section 4.0 to delete any reference to Surveillance Plan or Process to Maintain.

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Delete-Surveillance Plan from Volume II of Topical Report - Volume II now becomes just the Bases of Tech Specs.

4.

As each STS Surveillance is rolled into the new format, identify those features that need to be revised.

Such items identified in Background (above) as problems would be corrected / revised as justifiable.

Second Proposed Solution looks like Attachment 2.

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' SURVEILLANCE REQUIREMENTS TABLE OF CONTENTS 4.0 SURVEILLANCE REQUIREMENTS (CENERAL) 4.1 REQUIREMENT FOR THE CONTENTS OF THE SDiVEILLANCE PLAN 4.2 PROCESS TO MAINTAIN SURVEILLANCE PLAN 4.3 SURVEILLANCE DEFINITIONS 4.4 SURVEILLANCE REQUIREMENTS FOR REACTOR LCO'S 4.5 SURVEILLANCE REQUIREMENTS FOR REACTOR COOLANT SYSTEM LCO'S 4.6 SURVEILLANCE REQUIREMENTS FOR ENGINEERED SAFETY FEATURES LCO'S 4.7 SURVEILLANCE REQUIREMENTS FOR INSTRUMENTATION LCO'S 4.8 SURVEILLANCE REQUIRE $ENTS FOR-ELECTRICAL POWER SYSTEMS LCO' 4.9 SURVEILLANCE REQUIREMENTS FOR AUXILIARY SYSTEMS LCO'S 4.10 SURVEILLANCE REQUIREMENTS FOR STEAM AND POWER CONVERSIO 4.11 SURVEILLANCE REQUIREMENTS FOR RADIOACTIVE INVENTORY LCO'S 4.12 SURVEILLANCE REQUIREMENTS FOR REFUELING OPERATIONS LCO'S A l-l

i 4.0 SURVEILLANCE REOUIREMENTS (GENERAL)*

4.0.1 Surveillance Requirements shall. be met 'during the OPERATIONAL MODES or

~ ther conditions specified for individual Limiting Conditions for Operation o

unless otherwise stated in an individual Surveillance Requirements.

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

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

interval,-but b.

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

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

stated in the individual specifications. Exceptions to these requirements are Surveillance Requirements do not have to be perfomed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL MODE cr 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 inspection and testing of ASME Code Class 1, 2, and 3 components shall be applicable as follows:

Inservice inspection of ASME Code Class 1, 2, and 3 comp ~onents and a.

inservice testing of 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 by 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);

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This section will reflect the results of AIF/NRC Short Term Improvement Items (e.g. Specification 4.0.3, 18 month surveillance) as they become available.

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4.0.5 (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 Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ASME Boiler and Pressure Vessel Code and applicable Addenda Required frequencies for terminology for inservice performing inservice inspection and testing activities inspection and testing activities Weekly At least once per 7 days Monthly At Quarterly or every 3 months least once per 31 days Semiannually or every 6 months At least once per 92 days Every 9 months At least once per 184 days At least once per 276 days Yearly or annually At least once per 366 days The provisions of Specification 4.0.2 are applicable to the above c.

required frequencies for performing inservice inspection and testing activities; d.

Performance of the above inservice inspection and testing activi-ties shall be in addition to other specified Surveillance Require-ments; and Nothing in the ASME Boiler and Pressure Vessel Code shall be e.

construed to supersede the requirements of any Technical Spec-ification.

4.0.6 Surveillance Requirements shall apply to each unit individually unless otherwise indicated as stated in Specification 3.0.5 for individual specifications or whenever certain portions of a specification contain surveillaace parameters different for each unit, which will be identified in' parentheses or footnotes.

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4.1 REQUIREMENT FOR THE CONTENTS OF THE SURVEILLANCE PLAN The SURVEILLANCE PLAN shall contain the. methodology relating to test, calibration, or inspection to assure that the necessary quality of systems tnd components are maintained, that facility operation will be within safety limits, and that the limiting conditions of operation will be met.

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l 4.2 Process to Maintain Surveillance Plan 4.2.1 The Surveillance Plan shall be approved by the Commis-sion prior to implementation.

1 4.2.2 A licensee may make changes to the Surveillance Plan i

without prior NRC approval unless the change involves (1). a conflict with the incorporated in the licenser ortechnical specifications effectiveness of the existing surv(ii) a decrose in the 3

eillance program.

4.2.3 A change to the surveillance Plan may be deemed to t

involve a decrease in the effectiveness of the plan:

(a)

If the frequency of the surveillance, monitoring, inspection, testing, or calibration is decreased without compensation in the acceptance criterion or through an increase in the sensitivity or accuracy of the method used, unless the cumulative history of test results (either generic or plant specific) clearly supports the reduction in frequency.

Probability methods may be utilized, in lieu of cumulative history of test results, to support the reduction in frequency without compensation.

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(b)

If the sensitivity or the accuracy of the method used to perform the surveillance, monitoring, l

inspection, testing, or calibration is decreased without compensation in the acceptance criterion (tightening the criteria) or through an increase in the frequency of the surveillance, monitoring, inspection, testing, or calibration.

Another method may be utilized without compensation to perform the surveillance, monitoring, inspection, testing, or calibration as long as it can be shown i

to be equivalent to the existing method in demonstrating operability of the structure, system, or component.

4,

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(c)

If the acceptance criterion for the surveillance, monitoring, inspection, testing, or calibration is relaxed without compensation through an increase in the frequency, sensitivity, or accuracy of the method used.

The acceptance criterion may be relaxed without compensation if it can be shown that the assumptions made in the safety analysis j

are still preserved.

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mu 4.2.4 Licensee initiated changes to the surveillance Plan:

b (a) shall be submitted to the This submittal shall contain: commission annually.

,\\

1.

Sufficiently detailed information to totally support the rationale for the change.

)

2.

A determination that the change did not reduce the overall effectiveness of the existin i

review). g eurveillance requirement (50.59 3.

Documentation of the fact that the change has been reviewed and found acceptable by the i

Station Manager.

(b) shall become effective upon review and acceptance by a qualified individual / organization.

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I 4.3 SURVEILLANCE DEFINITIONS

f I

ACTUATION TEST An ACTUATION TEST shall be the appifcation of a simulated signal to a valve or pump to verify that it will open, close, start, or stop.

i ACTUATION LOGIC TEST An ACTUATION LOGIC TEST shall be the application of various simulated 1

input combinations in conjunction with each possible interlock logic i

state and verification-of the required logic output.

The ACTUATION LOGIC TEST shall include a continuity check, as a minimum, of output devices.

4 ANALOG CHANNEL OPERATIONAL TEST An ANALOG CHANNEL OPERATIONAL TEST shall be the injection of a simulated i

signal into the channel -as close to the sensor as practicable to verify OPERABILITY of alarm, interlock and/or trip functions.

The ANALOG CHANNEL OPERATIONAL TEST shall include adjustments, as necessary, of the alarm, interlock and/or Trip Setpoints such that the Setpoints are within the required range and accuracy.

}-

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment,

! (V channel such that it resbonds with the required range and accuracy to as necessary, of the i

known values of input.

The CHANNEL CALIBRATION shall encompass the entire channel including the sensors and alarm, interlock and functions and may be performed by any series of sequential, over/or trip

lapping, or total channel steps such that the antire channel is calibrated.

i CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation.

This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the sam.e parameter.

l FRE00ENCY NOTATION The FREQUENCY NOTATION specified for the performance of Surveillance i

Requirements shall correspond to the intervals defined in Table 4.3-I.

l FUNCTIONAL TEST i

A FUNCTIONAL TEST shall be the determination or verification of the i

capability of an item to meet specified requirements by subjecting the I

l item to a set of physical, chemical, or operating conditions.

This is a preliminary list of definitions.

This list will be revised j.

as the Surveillance Requirements are developed.

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/9/-7 L

4.3 SURVEILLANCE DEFINITIONS (Continued)

MASTER RELAY TEST A MASTER RELAY TEST shall be the energization of each master relay verification of OPERABILITY of each relay.

The MASTER RELAY TEST shall include a continuity check of each associated slave relay.

PEYSICS TESTS PHYSICS TESTS shall be those testa performed to measure the fundamental nuclear characteristics of the core and related instrumentation i

(1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission.

_ SLAVE RELAY TEST A SLAVE RELAY TEST shall be the energization of each slave relay and verification of~0PERABILITY of each relay.

include a continuity check, as a minimum, of associated testableThe SLAVE R actuation devices.

3

, SOURCE CHECK when the channel sentor is exposed to a source of increase

(.

radioactivity.

STACCERED TEST BASIS A STACCERED TEST BASIS shall consist oft A test schedule for n systems, subsystems, trains, or other a.

designated components obtained by dividing the specified test interval into n equal subintervals, and b.

The testing of one system, subsystem, train, or other designated comp,9ent at the beginning of each subinterval.

TRIP ACTUATING DEVICE OPERATION TEST A TRIP ACTUATING DEVICE OPERATIONAL TEST shall consist of operating the Trip Actuating Device and verifying OPERABILITY of alarm, interlock and/or trip functions.

The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include adjustment, as necessary, of the Trip Actuating Device such that it actuates at the required Setpoint within the required accuracy.

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t TABLE 4.3-1 FREQUENCY NOTATION J

1 NOTATION FREQUENCY S

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

DA At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

WK i

At least.once per 7 days, MO At least once per 31 days.

QU At least once per 92 days.

i SA At least once per 184 days.

RF At least once per 18 months.

S/U Prior to each reactor startup.

N.A.

Not applicable.

P Completed prior to each release.

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I 4.4 SUtvEILLANCE REQUIREMENTS FOR RZACTOR LCO'S (To Be Provided) 4.5 SURVEILLANCE REQUIREMENTS FOR REACTOR COOLANT SYSTEM LCO' i

(To Be Provided) i e

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P E OWNERS GROUP m

m GENERIC SURVEILLANCE M.,

M 4.6 SURVEILLANCE REQUIREMENTS FOR ENGINEERED SAFETY FEATURES LCOs LCO SURVEILLANCE REQUIREMENT SURVEILLANCE FREQUENCi EMERGENCY CORE COOLING SYSTEM 3.6.1 through 3.6.7 (to be provided)

CONTAINMENT 3.6.10 Containment A.

FUNCTIONAL TEST A.

Prior to entering Equipment Hatch (Seal Leakage)

MODF. 4 if the r

eq,uipment hatetr has been opened.

3.6.11 Containment A.

FUNCTIONAL TEST A.

After each clos-(-

Air Lock (Seal Leakage) ing, QB once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months during multiple entries

+

B.

FUNCTIONAL TEST B.

SA (Air Leakage)

C.

FUNCTIONAL TEST C.

SA MQ Each RF (Mechanical Inter-prior to entering lock)

MODE 4.

3.6.12 Containment A.1 FUNCTIONAL TEST A.1 Not to exceed 24 Isolation Valves (Leakage) months A.2 CHECK A.2 Prior to MODE 4 (Manual Valves)

A.3 FUNCTIONAL TEST

.3 As Specified (StrokeTime)

A.4 FUNCTIONAL TEST A.4 RF (Isolation Signal)

(CONTINUED)

(Amendment No

)

Rev.

j9l-I/

r 2 OWNERS GROUP

-n I""

GENERIC SURVEILLANCE M,um 4.6 SURVEILLANCE REQUIREMENTS FOR ENGINEERED SAFETY FEATURES LCOs (CONTINUED l

LCO SURVEILLANCE REQUIREMENT SURVEILLANCE FREQUENCY 3.6.13 Containment A.

CHECK A.

M0 Purge Supply and Exhaust Isolation Valves 3.6.14 Containment A.

CHECK A.

S Internal Pressure 3.6.15 Containment A.

CHECK A.

DA Air Temperature CONTAINMENT SPRAY AND COOLING t

(

3.6.20 Containment A.1 CHECK A.1 M0 Spray System (Valve Position)

A.2 FUNCTIONAL TEST A.2 QU (Pump Discharge Pressure)

A.3 ACTUATION TEST A.3 RF (Automatic Valves)

A.4 ACTUATION TEST A.4 RF (Spray Pump)

A.5 FUNCTIONAL TEST A.5 RF (LeakRate)

A.6 FUNCTIONAL TEST A.6 5 Years (Smoke / Airflow)

Cont:inment B.1 FUNCTIONAL TEST B.1 M0 Cooling Fans (Start / Operate)

B.2 CHECK B.2 RF (Water Flow)

B.3 FUNCTIONAL TEST B.3 RF (ESF Actuation)

[ Amendment No

]

Rev.

/9/-/1

- ~ - - - - - -, - - - - - - - - - - - - -.. - -. -

4.7 SURVEILLANCE EQUIREMENTS FOR INSTRUMENTATION LCO'S (To Be Provided) ~

4.8 SURVEILLANCE E QUIREMENTS FOR ELECTRICAL POWER STSTEMS LCO (To Be Provided) 4.9 SURVEILLANCE EQUIEMENTS FOR AUKILIAIT STSTEMS LCO'S (To Be Provided) 4.10 SURVEILLANCE E QUI EMENTS FOR STEAM AND POWER CON (to Be Provided) 4.11 SURVEILLANCE REQUIREMENTS FOR RADI0 ACTIVE INVENTORT LC (To Be Provided) f 4.12 SURVEILLANCE REQUIREMENTS FOR REFUELING OPERATIONS i,

(To Be Provided) a C.-

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AP /-/ 3 i

TABLE OF CONTENTS 4.O SURVEILLANCE REQUIREMENTS 4.1 Requirement for the Contents of a Surveillance 4.2 Reserved 4.3 Reserved 4.4 Reactor (Later) 4.5 Reactor Coolant System (Later) 4.6 Enginered Safety Features 4.7 Instrumentation 4.8 Electrical Power Systems 4.9 Auxiliary Systems 4.10 Steam & Power Conversion 4.11 Radioactive Inventory 4.12 Refueling Operations 1

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i 4.0 SURVEILLANCE REQUIREMENTS ~

j 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otha; wise stated in an individual Surveillance Requirements.

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

A maximum allowable extension not to exceed 25% of the surveillance 4

a.

interval, but b.

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

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

stated in the individual specifications. Exceptions to these requirements are have to be performed on inoperable equipment. Surveillance Requirements do not 4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not j

be made unless the Surveillance Requirement (s) associated with the Limiting 4

Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.

4.0.5 Surveillance Requirements for in' service inspection and t'esting of ASME Code Class 1, 2, and 3 components shall be applicable as follows; Inservice inspection of ASME Code Class 1, 2, and 3 components and a.

inservice testing of 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 by 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)(1);

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This section will reflect the results of AIF/NRC Short Term Improvement Items e.g.

Specification 4.0.3, 18 month surveillance) as they become availab e.

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t 4.0.5 (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 a d Pressure Vessel Code and applicable Addenda shall be applicable n

as follows in these Technical Specifications:

ASME Boiler and Pressure Vessel 1

Code and applicable Addenda Required frequencies for terminology for inservice performing inservice inspection and testing activities inspection and testing activities Weekly Monthly At least once per 7 days Quarterly or every 3 months At least once per 31 days Semiannually or every 6 months At least once per 92 days

,gp Every 9 months least once penb184 days At Yearly.or annually At least once per 276 days At least once per 366 days The provisions of Specification 4.0.2 are applicable to the above c.

required frequepcies for performing inservice inspection and f

testing activities d.

Performance of ghe above inservice inspection and testing activi-ties shall be in addition to other specified Surveillance Require-ments; and Nothing in the ASME Boiler and Pressure Vessel Code shall be e.

construed to supersede the requirements of any Technical Spec-ification.

4.0.6 Surveillance Requirements shall apply to each unit individually unless otherwise indicated as statec in Specification 3.0.5 for individual specifications or whenever certain portions of a specification contain surveillance parameters dilferent for each unit, which will be identified in parentheses or footnotes.

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4.1 REQUIREMENT FOR THE CONTENTS OF A SURVEILLANCE A SURVEILLANCE shall contain the methodology relating to test, calibration, or inspection to assure that the necessary quality of systems and components are maintained, that facility operation will be within safety limits, and that the limiting conditions of operation will be met.

4.2 (Reserved) 4.3 (Reserved) 4.4 through 4.6.9 (Later)

- 4. 6.10 through 4. 6. 22 4e 4.7 through 4.12 (Later) 9 C.

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Auoust 4. 1986

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GUIDELINES FOR PREPARING NEW LCO's AND SURVEILLANCES Guidelines for First Draft 1.

Use AIF criteria of May 2,1986 and check the split as provided to you

- document kny the LCO is in or out (briefly) and relate to specific criterion on criteria.

2.

Rewrite LC0/Surveillances using B&W STD Tech Specs and B&WOG Writers Guide as closely as possible.

Editorial changes and changes for clarity are to be made.

Use nu abers as they are found in the STD and put them in [

).

If a blank space is used in STD then us (

) in new LCO with no (ntry.

~

3.

LSSS and Safety Limits are to be rolled into the appropriate LCOs.

4.

There will be one to one correspondence between LCOs and Surveillances.

5.

Fill out the " work sheet" for each LC0/ Surveillance and highlight all changes to STD with just,1fication.

List any known problem using the TSIMP " Problem" sorteand notes /coments from meetings with the Owners.

Fill out the matrix for A0Ts, SI, process variables.

List any " holes" i,

in STD have need to be filled (such as a missing surveillance or a missing LCO condition).

6.

Within a section put LCO's in descending order of safety based on en-gineering judgement.

7.

Review Special Test Exceptions and roll applicable ones into the LCO.

See Writers Guide for style on how to include special test exceptions.

8.

Remove all conditions related to instrumentation and put in appropriate instrumentation section.

9.

Develop notes in LCOs and Surveillance in accordance with B&WOG Writers Guide.

10.

Identify deviations from Writers Guide recomended to improve clarity or l

simplicity of new Tech Specs (note on work sheet).

Guidance For Subsecuent Drafts 1.

Use Owners feedback and above gudiance to prepare next draft of i

j material.

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1 B&W - Atmospheric Type Containment t

Disoosition of All Tech. Soee. In Section 3.6 B&W STD New T.S.

T.S. No.

No.

EXPLANATION 3.6.1.1 3.6.10 Standard T.S.

CONTAINMENT INTEGRITY changed to CONTAINMENT EQUIPMENT HATCH. The reason for this change was that all the operator actions and equipment functions necessary to assure contain-ment integrity were already included in other i

LCOs of this section. Hence, the inclusion of an LCO for the equipment hatch completed the group of LCOs which assure containment integrity. This action made retaining the CONTAINMENT. INTEGRITY T.S. superfluous.

3.6.1.2 NA CONTAINMENT LEAK LIMITS - This T.S. does not deal with leak. rates during operation but during outages.

It does not meet the AIF selection celteria for T.S.

3.6.1.3 3.6.11 CONTAINMENT AIR LOCKS - Title changed to CONTAIN-C' MENT PERSONNEL AIR LOCKS to better describe its function. Credit for air tightness is considered in analyses to limit offsite doses during a DBA.

Meets AIF Selection Criterion #3 for new T.S.

3.6.1.4 NA CONTAINMENT ISOLATION VALVE AND CHANNEL WELD PRESSURIZATION SYSTEMS This is an optional i

system which is not installed in the B&WOG plants. Thus, the T.S. was not included as a new generic T.S. although its contents meet the AIF 1

T.S. selection criteria.

3.6.1.5 3.6.14 CONTAINMENT INTERNAL PRESSURE Containment Deletion pressure is a variable used in the-initial Candidate

. conditions of the safety analyses.

Hence, this T.S. meets AIF Selection Criterion #3.

However, studies are now proposed to possibly show that this T.S. is no longer needed.

3.6.1.6 3.6.15 CONTAINMENT AIR TEMPERATURE Containment Air Deletion Average temperature is a variable used in the Candidate initial conditions of the safety analyses.

This T.S. meets AIF Selecti6n Criterion #3.

However, studies are now proposed to possibly show that 1

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B&W STD New T.S.

T.S. No.

No.

EXPLANATION 3.6.1.7 NA CONTAINMENT STRUCTURAL INTEGRITY - This is a T.S.

for tests and inspections not nomally performed during power operation, and it does not meet AIF T.S. selection criteria.

3.6.1.8 3.6.13 CONTAINMENT VENTILATION SYSTEM - This system is part of the primary success path for accidents involving release.of radioactivity offsite.

Thus, it meets AIF T.S. Selection Criterion #3.

3.6.2.1 3.6.20 CONTAINMENT SPRAY SYSTEM 3.6.2.3 CONTAINMENT COOLING SYSTEM - The T.S. for these two systems were combined into a single new T.S.

entitled CONTAINMENT SPRAY and COOLING SYSTEMS.

Since these systems function to mitigate a DBA, th'e T.S.

meets AIF Selection Criterion #3 to become a new T.S.

3.6.2.2 3.6.21 SPRAY ADDITIVE - Although this T.S. meets the AIF

. Deletion selection criteria to be included as a new T.S.,

. Candidate work is being proposed to show that it can be deleted from the T.S. list.

3.6.3 3.6.22 IODINE CLEANUP SYSTEM - Iodine Cleanup limits offsite radiation doses during DBA.

This T.S.

meets AIF Selection Criterion #3, and will be a plant specific document for SMUD only.

3.6.4 3.6.12 CONTAINMENT ISOLATION VALVES - These valves func-tion to limit the consequences of a DBA.

The T.S. meets AIF Criterion #3 to become a new T.S.

3. 6. 5.1 -

NA COMBUSTIBLE GAS CONTROL - These T.S. do not meet 3.6.5.2 NA the AIF selection criteria to be' included as new 3.6.5.3 NA T.S.

3.6.5.4 NA 3.6.6 3.6.22 PENETRATION ROOM EXHAUST AIR ~ CLEANUP SYSTEM (OPTIONAL) - Impact on DBA analysis or accident mitigating equipment.

Plant s for Oconee and Arkansas only. pecific Tech Spec 3.6.7 NA VACUUM RELIEF VALVES - Not used to mitigate DBA l

and.does not meet AIF criteria to be included as a T.S.

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1 B&W - DUAL TYPE CONTAINMENT g:

Disoosition of All Tech. Soecs. in Section 3.6 B&W STD T.S. No.

3.6.1 3.6.2 3.6.3 No B&W plant owners have dual con-3.6.4 tainment systems. Therefore, these 3.6.5 technical specifications have not 3.6.6 been included in the T.S. split.

3.6.7 i..

3.6.8 i

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SURVEILIANCES FOR CDNPADMENT SYSTEMS i

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u TECHNICAL SPECIFICATION PACKAGE CONTENTS i

1.

BaW STANDARD TECH. SPECS. WITH TRANSPOSIT10N NOTATIONS.

2.

. WORKS W ET TO DENOTE CHANGES TO THE STANDARD TECH. SPEC.

3.

MARKEDREV.00FGENERICLC0(WH$RECHANGED).

~

4.

MARKED REV. 0 0F GENERIC SURVEILLANCE (WE RE CHANGED).

5.

REV. 1 0F GENERIC LCO.

-6.

REV.10F GENERIC SURVEILLANCE.

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j.'s 3/4.6 CONTAINMENT SYSTEMS 3/4. 6.1 PRIMARY CONTAINMENT Co,arws.unt.ar~ fg.o rp ~ t a r*

Narcd CONTAINMENT INTEGRITY m,,., r, a To Cev t,e oac/ 4specT eF 7%.s 7'c c a. S e cc.. NOT L:ov ere c o df LIMITING CONDITION 80R OPERATION n r A,e 4 c. o 's.

.6.1.1 Primary CONTAIN INTEGRITY shall be maintained.

{sM c A A**LICABILITY: MODES 1, 2, 3 and 4.

ggf. #p ACTION:

Without primary CONTAI4 TENT INTEGRITY, restore CONTAllMENT INTEGRITY within one hour or be in at least NOT STAND 8Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHtJIDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REOUIREMENTS 4.6.1.1 Primary CONTAI6 JNTEGRITY shall be demonstrated:

p,e N'#'

a.

At least once per 31 cays by verifying that all ons= not capable of being cigsed by OPERABLE containment automatic isolation p,t "

valves and required to be closed auring accident conditions are g

closed by valves, blind flanges, or enactivated automatic valves g/ 'Cg U

secured in their positions, except as provided in Table 3.6-1 of L

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[

ification 3.6.4.

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b.

8y verifying that each containment air lock is OPERABLE per fed 5'[e.s W fication (3.6.1. 3 L 3'

incwn a c.

After each closing of the equipment hatch, by leak rate testing the

,g Su,en equipment hatch seals with gas at P (50 psig) and verifying that W.<c t. p, when the measured leakage rate for these seals is added to the

' y.o y,g,,

leakage rates detemined pursuant to Specification 4.6.1.2.0 for all other Type 8 and C penetrations, the cambined leakage rate is less than or equal to 0.60 L,.

"Except valves, blind flanges, and deactivated automatic valves which are b#'

located inside the containment and are locked, sealed, or otherwise secured in Tecd N the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that verification of these penetrations being closed need not be performed more often than once per 92 asys.

84W-ATMDSPHERIC 3/4 6-u SEP 1

1979 g

1

? OWNERS GROUP R&mllm f C-WORKSHEET FOR LC0 3.6.10 A.

3.6.10 (Containment Equipment Hatch) is a newly generated LC0 which replaces 3.6.1.1 (Containment Integrity) of the B&W STD.

B.

The reason for generating the new LC0 to replace the Containment Integrity Tech. Spec. was that all aspects of Containment Integrity are covered by the other LCOs written for the Containment System except the equipment hatch.

Thus it seems more appropriate and direct to address the equipment hatch with its own LC0 rather than infer its operating conditions from the genenlized Containment Integrity requirements.

C.

A0Ts ' included for the equipment hatch LCO are the same as those in the STD Tech. Spec. for the Containment Integrity since that document controlled the hatch operai. ions.

~

D.

3.6.10 Surveillance was written up from the requirements already contained in 4.6.1.1 c.

The frequency of the Surveillance was changed to better define the intent of the original frequency in the STD.

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r-GENERIC TECHNICAL SPECIFICATION 3.6 ENGINEERED SAFETY FEATURES SYSTEM: CONTAINMENT LCO: 3.6.10 The CONTAINMENT EQUIPMENT HATCH shall be OPERABLE.

I APPLICABILITY: Modes 1, 2, 3, 4 Condition Required Action Completion A.

Equipment Hatch A.1 Make Equipment Hatch I hour INOPERABLE due to OPERABLE excessive air leak-age B.

Recuired action B.1 HOT STANDBY Next 6 EDI completed hours within allowed gg time B.2 COLD SHUTDOWN Next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months l

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3.6-

[ Amendment No.

]

Rev.

0

O.e m.n c: -

c c_>q uw OWNERS GROUP p

EMmi

[g GENERIC SURVEILLANCE 4.6 SURVEILLANCE REQUIREMENTS FOR ENGINEERED SAFETY FEATURES SYSTEM: CONTAINMENT LCO: 3.6.10 CONTAINMENT EQUIPMENT HATCH Surveillance h

Frequency p, grmed A.

Leak rate test the equipment hatch seals with Prior to Mode 5, 6 seals with gas at Pa [ ] psig and verify that entering when the measured leakage rate for these seals Mode 4, if is added to the leakage rates determined for the equip-all other 10 CFR 50 Appendix J type B and C ment hatch penetrations, the combined leakage rate is has been less than or equal to 0.6 La.

opened and each re-fueling i

I-I 6

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4.6-Rev.

0

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GENERIC TECHNICAL SPECIFICATION 3.6 ENGINEERED SAFETY FEATURES p"s., _. _

^

SYSTEM: CONTAINMENT LCO:

3.6.10 The CONTAINMENT EQUIPMENT HATCH shall be OPERABLE.

APPLICABILITY: Modes 1, 2, 3, 4 Completion Condition Required Action Time A.

Equipment Hatch A.I Make Equinment Hatch

[I] hour IN0PERABLE due to OPERABLE excessive air leak-age B.

Required action B.1 HOT STANDBY Next [6]

r NOT completed hours

(-

within allowed AND time B.2 COLD SHUTDOWN Next [30]

hours I

1 3.6-

[ Amendment No.

]

Rev.

I l

EOWNERS GROUP gg, GENERIC SURVElLLANCE j1;-

4.6 SURVEILLANCE REQUIREMENTS.FOR ENGINEERED SAFETY FEATURES LC SYSTEM:

CONTAINMENT LCO: 3.6.10 CONTAINMENT EQUIPMENT HATCH When Surveillance Frequency Performed A.

Leak rate test the equipment hatch seals with Prior to Mode 5, 6 seals with gas at Pa [50] psig and verify that entering

~

when the measured leakage rate for these seals Mode 4, if is added to the leakage rates determined for the equip-all other 10 CFR 50 Appendix J type B and C ment hatch penetrations, the combined leakage rate is has been less than or equal to 0.6 La.

opened and each re-fueling e

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CONTAINMENT AIR LOCKS LIMITING CONDITION FOR ODERATION l

3.6.1.3 Each containment air lock shall be OPERABLE with:

L ec.

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Both doors closed except when the air lock is being used for normal

, transit entry and exit through the containment, then at least one

__atr sack door shall be closed, and 5n overaii air lock leakage rate or sess man er ww.i to 0.05 L, at

,"[yb s P,, (50) psig, g

PPLICA8ILITY: 2 DES 1, 2, 3 and 4 yemg ACTION:

r 1sucts t a s+2 Cedr d

4. ( With one containment air lock door inoperable:

. f_c o, f o,ro e, " c e

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,es wese u "G 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 OPERA 8LE air lock door closed.

2.

Operation any then continue until performance of the next required overall' air loct leakage test provided that the OPERABLE t m,rne air lock door is verified to be locked closed at least once per 31 days.

M,ci$7, Otherwise, be in at least HOT STAND 8Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ~"'^'"'#'#

N and in COLD SHUTDOWN within the folloring 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

4.

The provisions of Specification 3.0.4 are not applicab1Df sepsc.e t us a,rc s~ n

as ury b.

With the containment air lock inoperable, except as the result or an inoperable air lock door, maintain at 1sast one air lock door closed; restore the inoperable 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 NOT STAND 8Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD L:ces c >

SWTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

w erec ' - ir G. C. < O.

cf rat LC.c

';. ces s..-, c sv s :res u res cur mf Tu Ocen.!/ ~v - r A cruMtf Ad L C /emv :- t s see a. ra. - e ar,n u at.

I 34W-ATMDSPMERIC 3/4 6-5J JUN 15 579

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t CONT!I M NT 95 M i

StfPYEILLANCE #EDUIPD'ENTS (Continued)

Q u a s t.

Yv rtC"'

' Aprs t D* *" ~.

4.6.1.3 Lach containnent air Tock sha11 he dronstrated nPEEARLE:

C,y a r,

~

r each op3en

-a.

. except ehen the air lock is being used for - _.n. i. &

mu tiple entries then at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , by verffyine(9 san e.

tectable seal Testage DJ pressure decay h the volume between rr. ~ A

=4 % at feast 15 minutes.tne coor zesis is

..sur12ed te greater than or soual to P, (50)

C unacu rc g'd # gc b.

At least once per 6 months by conducting an overati air lock leakaoe

% ;L..

test at P (50) psig and by verifying that the overall air lock 4 8d*d2 N3 gge,.

1eakage r$te is within its ifmf t # and rn y (

i At least once 5r 6 months by verifying. that only one door 1

,$*,I" air 1ock can he opened at a time, yn y e,

4

/

Exemption to Appendix "J' of 10 CFP 50 x

1 The provisions of Fascification 4.0.2 are not applicable.

1

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WORKSHEET FOR LCO 3.6.11 A.

Title changed from Containment Air Locks to Containment Personnel Air Locks to better describe equipment function as suggested by the BWOG Tech. Spec. Committee.

Note on exception to Spec'. 3.0.4 moved from Action section of old spec.

B.

to Applicability section of new LCO.

C.

Condition A.of new IC0 contains reworded section from old Tech. Spec.

- contents unchanged.

D.

Conditions B, C, & D of new LCO are a modification of Action item B of the~Old Tech. Spec. Conditions have been separated out for clarity, Surveillance For LC0 3.6.11 A.

Item B under Limiting Condition for Operation on Old Tech. Spec.

incorporated as Item B under the new Surveillance.

B.

Item A on T.S. 4.6.1.3 modified to say Surveillance required "after each closing of air lock" rather than "after each opening" since ability to perform amount changed from, testing is based on a closed door.

Seal leakige "no detectable seal leakage" to " seal leakage less than La" as recommended by BWOG T.S. Committee.

{_

Applicable Surveill'ance modes designated and approved by BWOG T.S.

C.

Committee.

I

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= OWNERS GROUP ram GENERIC TECHNICAL SPECIFICATION 3.6 ENGINEERED SAFETY FEATURES SYSTEM: CONTAINMENT LCO: 3.6.11 CONTAINMENT PERSONNEL AIR LOCKS shall be OPERABLE.

Both doors of each air lock shall be closed except when one air lock door is being used for normal entry and exit.

APPLICABILITY: Modes 1, 2, 3, 4 Provisions of Specification 3.0.4 are not applicable.

Condition Required Action Completion A.

One air lock door A.1 Make air lock door seal 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months seal INOPERABLE due OPERABLE to excessive leak-age E

pu,r,tg A.2 Maintain OPERABLE air 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months -

r lock door closed 9

B.

Air lock IN0PERABLE B.1 Restore leakage rate to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months due to excessive acceptable value air leakage C.

Air lock mechanical C.1 Make air lock door 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interlock INOPERABLE mechanical interlock OPERABLE E

Gsaorsek C.2 Maintain associated air 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months i

lock doors closed and l

locked except as necessary for entry to make repairs 2

on interlock D.

Required action D.1 HOT STANDBY 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months M I completed within allowed 6M completion time D.2 COLD SHUTDOWN Next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months 3.6-M'*'Y "

l Rev.

9 E OWNERS GROUP MMIM GENERIC SURVEILLANCE i

4.6 SURVEILLANCE REQUIREMENTS FOR ENGINEERED SAFETY FEATURES LCOs SYSTEM: CONTAINMENT LCO: 3.6.11 CONTAINMENT PERSONNEL AIR LOCKS Surveillance Frequency h

p, grmed Each containment air lock shall be demonstrated OPERABLE:

A.

By verifying seal leakage less than La by After each Any Mode 4

pressure decay when the volume between the closing,4QR door seals ssurized to grea han once per 72 ual tg [] sig for at least(

l hours dur-O[]

inutes ing mul-tiple

NOTE---------------------

entries Exemption to Appendix "f' of 10CFR50 for reduced test pressure h

B.

By conducting an overall air lock SA leakage test as specified by 10 CFR 50, Any Mode Appendix J and by verifying that the air lock leakage rate is within the specified limit.

C.

By verifying that the mechanical inter-SA eM Any Mode i

lock permits only one door in each air each re-l lock to be opened at the same time.

fueling l

prior to

NOTE---------------------

entering The provision of Specification 4.0.2 are Mode 4 not applicable to A, B, and C above m

[ Amendment No.

1 4.6-p,y, o

C

" OWNERS GROUP GENERIC TECHNICAL SPECIFICATION 3.6 ENGINEERED SAFETY FEATURES N "<. '..~,"

e' l

SYSTEM:

CONTAINMENT LCO: 3.6.11 CONTAINMENT PERSONNIL AIR LOCKS shall be OPERABLE.

Both doors of each air lock shall be closed except when one air lock door is being used for normal entry and exit.

APPLICABILITY: Modes 1, 2, 3, 4 Provisions of Specification 3.0.4 are not applicable.

Condition

. Required Action Completion

~

A.

One air lock door A.1 Make air lock door seal

[24] hours seal INOPERABLE due OPERABLE to excessive leak-age E

'A. 2 Maintain OPERABLE air During lock door closed same

[24] hours

(,

B.

Air lock INOPERABLE '

B.1 Restore leakage rate to

[24] hours due to excessive acceptable value air leakage

~

C.

Air lock mechanical C.1 Make air lock door

[24] hours interlock INOPERABLE mechanical interlock OPERABLE M

C.2 Maintain associated air During lock doors closed and same locked except as necessary

[24] hours for entry to make repairs on interlock D.

Required action D.1 HOT STANDBY

[6] hours 1[QI completed within allowed At!Q completion time 0.2 COLD SHUTDOWN Next [30]

(

hours 3.6-

[ Amendment No.

1 g,y, 3

e

C' E OWNERS GROUP I

r i

&m GENERIC SURVEILLANCE OIT^C" Ga '

(

. i.

4.6 SURVEILLANCE REQUIREMENTS.FOR ENGINEERED SAFETY FEATURES LC SYSTEM: CONTAINMENT LCO: 3.6.11 CONTAINMENT PERSONNEL AIR LOCKS Surveillance Frequency Pe ormed Each containment air lock shall be demonstrated OPERABLE:

A.

By verifying seal leakage less than La by After each Any Mode pressure decay when the volume between the closing, QB door seals is pressurized to greater than once per or equal to [50] psig for.at least [15]

[72] hours minutes.

during multiple

NOTE--------- '-----------

entries Exemption to Appendix "y" of 10CFR50 for reduced test pressure

[

B.

By conducting an ove'rall air lock

[SA]

Any Mode L

leakage test as specified by 10 CFR 50, Appendix J and by verifying that the air lock leakage rate is within the specified limit.

C.

By verifying that the mechanical inter-

[SA] MQ Any Mode lock permits only one door in.each air each re-lock to be opened at the same time, fueling prior to

NOTE---------------------

entering The provision of ~ Specification 4.0.2 are Mode 4 not applicable to A, B, and C above v

4 4'6-

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CCNTAft# TNT SYSTD45

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tt?TERNAL PRE 55UPE LIMITING C3NOTT!0N FOR OPERATION

~

3.6.1.5 Primary containment internal pressure shall be afntained between

-zw c.

nd psig.

<v zco APPLICA8TLITY: 790E5 1, 2, 3 a

" #"' 'I ACTII1t!:

With the containment internal pressure outside of limits above, restore the internal pressure to within the Itaf ts within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT STAffD8Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDWN within.the fo11owin hours.

$NC.f.

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SUPVEILLANCE PEOUTPUTNTS

(

4.6.1.5 The erfrary covitainment internal pressure shall be de within the 1terits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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I WORKSHEET FOP LCO 3.6.14 A.

LC0 requirements incorporated with no technical changes.

B.

Surveillance requirements incorporated with no technical changes.

C.

Applicable Surveillance modes designated and approved by BWOG T.S.

Committee.

l 6

S.

f f

I r

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a.

C

L OWNERS GROUP GENERIC TECHNICAL SPECIFICATION 3.6 ENGINEERED SAFETY FEATURES SYSTEM: CONTAINMENT

'IO: 3.6.14 The CONTAINMENT INTERNAL PRESSURE shall be maintained between [ ] and [ ] [psig or inches of H ].

g APPLICABILITY: Modes 1, 2, 3, 4 Condition Required Action Completion A.

Containment internal A.1 Restore to limits

( 24 ours pressure outside specified limits f

B.

Required action F_QI B.1 HOT STANDBY f

completed within Next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

(-

allowed completion A!iQ time B.2 COLD SHUTDOWN Next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months BEING REVIEWED FOR POSSIBLE DELETION I:

DY" '

I 3.6-

p-

~

o E OWNERS. GROUP shg GENERIC SURVEILLANCE

~4.6 SURVEILLANCE REQUIREMENTS FOR ENGINEERED SAFETY FEATURES LCOs SYSTEM: CONTAINMENT LCO: 3.6.14 CONTAINMENT INTERNAL PRESSURE.

When Surveillance Frequency Performed A.

Determine that the containment internal S

Any Mode pressure is within the specified limits g

i l

4.6-Amendp No.

]

C "i OWNERS GROUP MMll GENERIC TECHNICAL SPECIFICATION

(

3.6 ENGINEERED SAFETY FEATURES r,,....,.

SYSTEM: CONTAINMENT LCO: 3.6.14 The CONTAINMENT INTERNAL PRESSURE shall be maintained between ( ) and ( ) [psig or inches of H ]

g APPLICABILITY: Modes 1, 2, 3, 4 Co p etion Condition Required Action e

A.

Containment internal A.1 Restore to limits

[1] hour' pressure outside specified limits B.

Required action NOT B.1 HOT STANDBY Next [6]

completed within hours allowed completion,

B!Q time B.2 COLD SHUTDOWN Next [30]

hours BEING REVIEWED FOR POSSIBLE DELETION l

l

(

3.6-IA**"dfent No.

]

Rev.

" OWNERS GROUP Mi GENERIC SURVEILLANCE

{',

4.6 SURVEILLANCE REQUIREMENTS FOR ENGINEERED SAFETY FEATURES LCO SYSTEM: CONTAINMENT LCO: 3.6.14 CONTAINMENT INTERNAL PRESSURE When Surveillance Frequency Performed A.

Determine that the containment internal

[S]

Any Mode pressure is within the specified limits '

3 I'

[ Amendment No.

]

l 4.6-Rev.

I

' N ' 06 9 'W.q&qm gy py _

f 9

9 m

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00CAINMEC gy37pgg g

AIR TEMoERATURE LIMITING CONDITION FOR ODERATION

~

3.6.1.6 X.-

Primary containment average air temperature shall not exceed saa.

<J 4co APoLICABIL!TY: MODES 1, 2, 3 and 4.

__ _t. m. t..4

4. c o A.. ION:

With the containment average air temperature greater than

.,L&Co nf.

'F, reduce the'

'N7b 400 average air temperature to within the limit within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 7 be in at least HOT STAND 8Y 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

.Traus A f 8 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

_ SURVEILLANCE REQUIREMENTS 4.6.

The primary containment average air temperatum shall be the arithmetical average of the temperatures at the following locations and'shall be detemined at least once per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

ed S ud.

LOCATION f

a.

b.

c.

d.

e.

Ip -ATMOSPHERIC 3/4 6-9J SEP i 51979 6

n

~-~~-

"a OWNERS GROUP g y..

EMMll b.! '

_3 "

WORKSHEET FOR LCO 3.6.15 A.

LC0 requirements-incorporated with no technical changes.

B.

Surveillance requirements incorporated with no technical changes.

C.

Applicable Surveillance modes designated and approved by BWO3 T. S.

Committee.

r

1 C-O OWNERS GRdUP

~

GENERIC TECHNICAL SPECIFICATION i

3.6 ENGINEERED SAFETY FEATURES SYSTEM: CONTAINMENT LC0: 3.6.15 The CONTAINMENT AIR AVERAGE TEMPERATURE shall not

].

APPLICABILITY: Modes 1, 2, 3, 4 i

Condition Required Action Completion Time A.

Containment air A.1 Reduce temperature to within 24 ours average tempera-acceptable limits ture greater than specified limit B.

Required action B.1 HOT STANDBY Next 6 F_QI completed hours within allowed MQ completion time B.2 COLD SHUTDOWN Next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months BEING REVIEWED FOR POSSIBLE DELETION i

,~

l 3.6-

[ Amendment No.

1 Rev.*

O

\\

l i

A L OWNERS GROUP EMMim GENERIC SURVElLLANCE j..

i 4.6 SURVEILLANCE REQUIREMENTS FOR ENGINEERED SAFETY FEATURES LCOs SYSTEM: CONTAINMENT LCO: 3.6.15 CONTAINMENT AIR AVERAGE TEMPERATURE Surveillance Frequency When Performed A.

Calculate containment air temperature DA Any Mode as the arithmetic average of at least

[

] of the temperatures at the following locations:

location a.

[

]

(/

b.

[

J s

c.

[

]

d..[

]

e.

[

]

i 4.6-

[An >endment No.

]

Rev. O I

d 1'

" OWNERS GROUP r'

M,MIm GENERIC TECHNICAL SPECIFICATION i

(

3.6 ENGINEERED SAFETY FEATURES

{tQpE7 SYSTEM:

CONTAINMENT LCO: 3.6.15 The CONTAINMENT AIR AVERAGE TEMPERATURE shall not e

).

APPLICABILITY: Modes 1, 2, 3, 4 Condition Required Action Completion Time A.

Containment air A.1 Reduce temperature to within

[8] hours average tempera-acceptable limits ture greater than specified limit e

B.

Required action 8.1 HOT STANDBY f

M I completed Next [6]

hours

(~ ;

within allowed aE completion time B.2 COLD SHUTDOWN Next [30]

hours BEING REVIEWED FOR POSSIBLE DELETION i

I l

P

(

f 3.6-

[ Amendment No.

]

f p,y, 1

p L

....... ~ _. _

<Cr

? OWNERS GROUP GENERIC SURVEILLANCE

?

ll'f 4.6 SURVEILLANCE REQUIREMENTS FOR ENGINEERED SAFETY FEATURES LCOs SYSTEM: CONTAINMENT LCO: 3.6.15 CONTAINMENT AIR AVERAGE TEMPERATURE When Surveillance Frequency Performed A.

Calculate containment air temperature

[DA]

Any Mode as the arithmetic average of at least

[ ] of the temperatures at the following locations:

Location a.

{

}

b.

(

,}

c.

(

f d.

(

e.

(

<)

k 1

(

[Amendmept No.

)

,I 4.6-Rev.

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J e

Q 1

O s

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00NTAt m!NT VENTILATION (ODTIONAL*)

LIMITIE CDCITION FOR 0*ERATION

.Z~a c t.

'd' A CC 3.6.1.8 The containment purge supply and exhaust isolation valves shall be su re "8~ r closed.

A**LICA8!LIW: MODES 1,2,3,a5 y,cwna

,a Af,c ic4 4,u rf ACTION:

With one containment purge supply and/or one exhaust isolation valve open, close the open valve (s) within one hour or be in at least HDT STAND 8Y within h "' A I#

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 .

e f-

- SUWEILLANCE REQUIREMENTS C

r-et., a 4.6.1.8 The containment purge supply and exhaust isolation valves shall be s ua v. res ef detarvined closed at least once per 31 days.

g, "This specification may be modified if the facility design conforms to tranen currreb Technical Position CS8 6-4 of the Standard Review Plan.

~

B M-ATMDSPHERIC 3/4 6-17J JUN 15 573

i OWNERS GROUP aemmamamme

}m.

w....~:

WORKSHEET FOR LC0 3.6~.11 A.

STD. T.S. 3.6.1.8 reformatted with same content as Option 1 of T.S.

3.6.13.

B.

Option 2 of 3.6.13 added with same format and material but different valve openings and completion times for plants that have justified purging.

Surveillance For LCO 3.6.13 A.

No changes to Surveillance 4.6.1.8 in new Surveillance requirements for Option 1.

B.

Optiun 2 Surveillance requirement changed to reflect valve opening angle for plants that have justified purging.

C.

Applicable Surveillance modes designatec' and approved by BWOG T. S.

Committee.-

a e

f I

I I

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Ops Z OWNERS GROUP GENERIC TECHNICAL SPECIFICATION 3.6 ENGINEERED SAFETY FEATURES SYSTEM: CONTAINMENT LCO: 3.6.13 The CONTAINMENT PURGE SUPPLY and EXHAUST ISOLATION VAL shall be closed.

(OPTION 1)

APPLICABILITY: Modes 1, 2, 3, 4 Condition Required Action Completion j

A.

One containment A.1 Close open valve (s)

I hour purge supply and/

or one exhaust isolation valve open 8.

Required action B.1 HOT STANDBf Next 6 El completed hours within allowed MQ completion time B.2 COLD SHUTDOWN Next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months l

l 1

l i

(

3.6-

[ Amendment No.

]

Rev.

O

s C

E OWNERS GROUP GENERIC TECHNICAL SPECIFICATION 3.6 ENGINEERED SAFETY FEATURES.

SYSTEM: CONTAINMENT LCO: 3.6.13 CONTAINMENT PURGE SUPPLY and EXHAUST ISOLATION OPERABLE and opened no greater than.31 degrees. Purging shall be allowed only to perform safety related activities.

(Option 2 - For plants that have justified purging)

APPLICABILITY: Modes 1, 2, 3, 4 Condition Required Action Completion Time A.

One cor,tainment A.1 Close open valve (s) to less 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months purge supply and/

than or equal to 31 degrees or one exhaust isolation valve open greater than 31 degrees B.

Required action 8.1 HOT STANDBY EQI completed Next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months w' thin allowed g2 cc,mpletion time B.2 HOT SHUTDOWN Next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months N

(

l 3.6

[ Amendment No.

]

Rev.

O f

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=

WD-ue.

3a4 o pm,q

" OWNERS GROUP e-'

g GENERIC SURVEILLANCE I,,

i 4.6 SURVEILLANCE REQUIREMENTS FOR ENGINEERI.D SAFETY FEATUR SYSTEM: CONTAINMENT l

LCO: 3.6.13 CONTAINMENT PURGE SUPPLY AND EXHAUST ISOLATION VALVE (OPTinM li Surveillance Frequency When Performed A.

Determine the Containment Purge Supply and M0 Any Mode Exhaust Isolation Valves to be closed is i

i P

k 4,6

[Aniendment No.

~1 Rev.

O

P

i OWNERS GROUP g

GENERIC SURVEILLANCE

p. -

4 r.

4.6 SURVEILLANCE REQUIREMENTS FOR ENGINEERED SAFETY FEATURES L SYSTEM: CONTAINMENT LCO: 3.6.13 CONTAINMENT PURGE SUPPLY And EXHAUST ISOLATION VAL fnDTTOM 7 - Fne nlante that havo itect C fi ori nereninn)

Surveillance h

Frequency p, grmed A.

Verify t'he con inment Purge Supply and Once per Modes Exhaust Isol io Valves are open no each 1, 2, 3, 4 greater thad

) degrees opening t

l 4

[ Amendment No.

]

Rev.

0 t

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-,---,--------__.---_----y-.,,

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C

" OWNERS GROUP

\\

r MMI GENERIC TECHNICAL SPECIFICATION i

I 3.6 ENGINEERED SAFETY FEATURES

{.

sp SYSTEM:

CONTAINMENT c

LCO: 3.6.13 The CONTAINMENT PURGE SUPPLY and EXHAUST ISOLATION shall be closed.

(0PTION 1) 4 APPLICABILITY: Modes 1, 2, 3, 4 Condition Required Action Co p etion e

A.

One containment A.1 Close open valve (s)

[1] hour purge supply and/

or one exhaust isolation valve open r

B.

Required action 8.1 HOT STANDBY Next [6]

E l completed hours within allowed BQ completion time B.2 COLD SHUTDOWN Next hours [30]

l l

I 3.6-

[ Amendment No.

1 Rev.

l

,n

a

= OWNERS GROUP

&MW GENERIC TECHNICAL SPECIFICATION I

3.6 ENGINEERED SAFETY FEAT 0RES

... i-SYSTEM: CONTAINMENT

..,a LCO: 3.6.13 CONTAINMENT PURGE SUPPLY and EXHAUST ISOLATION VA OPERABLE and opened no greater than 31 degrees.

Purging shall be allowed only to perform safety related activities (Option 2 - For plants that have justified purging)

APPLICABILITY: Modes 1, 2, 3, 4 Condition Required Action.

Completion

'O A.

One containment A.1 Close open valve (s) to less 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months purge supply and/

than or equal to 31 degrees or one exhaust isolation valve open greater than 31 degrees B.

Required action B.1 HOT STANDBY Next 6 EQI completed hours within allowed MQ completion time B.2 HOT SHUTDOWN Next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months a

e l

3.6

[ Amendment No.

]

Rev.

I i

m

,=,

m, OWNERS GROUP n.

MI i

GENERIC SURVEILLANCE L"7-I

.... m: si I

4.6 SURVEILLANCE REQUIREMENTS FOR ENGINEERED SAFETY FEATURES LCOs SYSTEM:

CONTAINMENT LCO: 3.6.13 CONTAINMENT PURGE SUPPLY AND EXHAUST ISOLATION VALVES (OPTION 1)

When Surveillance Frequency Performed A.

Determine the Containment Purge Supply and

[MO)

Any Mode Exhaust Isolation Valves to be closed 1

i i

t i

(

t 4.6-

[Amendgent No.

]

Rev.

. v,

~y "s*

t CDCATWEC SYSTNS f

SUPVE!LLANCE REOUTREMEFS (Cortinued)

_.[n c L. A5 1.

Normal operating pressure of orester tman or eoual to (350)

I""

psig for those parts of the system downstream of the pump suction isolation valve.

Za c t.. A t 2.

Greater than or enval to (55) osis for the pipino from the 62.

rc er contatruent emeroency sume isolation valve to the pump suction isolation valve.

En cl. A5 e.

At least once per 5 years by perfoming an air or smoke flow tes through each spray header and verifying each spray nczzle is

" re m 1*

unobstructed.

t RAW-A W SPHEPIC 3/A 6-19J JUN 151979

(

~

/}/ & L,C 0 LG

O 2

DRAF i CONTAIMENT SYS1 EMS

(

CONTAINMENT COOLING $YSTEM (0PTIONAL).(Credit taken for fodine removal Oy spray systems)

LIMITING CONDITION FOR OPERATION

_ f4:c uot

. 6. 2. 3 (Two) independent groups of containment cooling fans shall be OPERA 8LE

,e 4co with (two) fan systems to each grovo.

(Equivalent to 1005 cooling capacity.)

po,e cer

APPt.!CA8ILITY: MODES 1, 2, 3 and 4.

1 AGTION:

a.(With one group of the above required containment coe1tng fans inoperable I*aa a c.ve and both containment spray systans OPERA 8LE, restore the inoperstle A.

I"""# * #[,f

( group of cooline fans ta OPEAAnti status within 7 days or be in a I

Oc V4' N A'

east HOT STAN08Y within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ann in GULD 3MUTW WN thin the followina 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With two groups of the above required containment. cooling fans inoperable, and both containment spray systans OPERA 8LE, restore t Q east ena_aroup of cooline fans to CPERASLE status'within 72 hou I"w8 th "

t,co opr,cd /

rectusza,4 for be in at 1 east lGT STAN0Wintth1n the next e nours aan 1n COLD) cous,r,os 8,

.'4 00 C'"e, read SHUTOOWN within the following 30 hou Restore both above requi groups of cooling rans to vrr.nnsLa a tus within 7 days of initial

,rru h'

loss or be in at lapst NOT STAN08Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and t,v,c,44 /Joi LD SHUTDohne within the followina 30 hour3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months sf T s.ce-~arer /a 4

c. FWith one group of the above required containment coo 11ng fans inoper

mvaL.

teo and one containment spray systas inoperable, restore the inoperab1_e pr,,a /f2

.Cvcy, se, a ray systas to CPERASLE status within 72 hou@r be in at least 1

c,,,,r,. a C.

Lce codo'r'* T following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months estore the inopernoie vroup vi..mi._ ;t i

cooling rans r.a Ors LE status within 7 days of initial loss or be ou,rre d in at least NOT STAN08Y vithin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD $HUTDOWN S y 3wo*

within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

a c m u,rrr i

I

eosw SURVUILLANCE REQUIREMENTS

.zad.rd 4.6.2.3 ch group of containment cooling fans shall be_ demonstrated OPERA 8 gs,,gste (Atleastonceper31daysby:

1.

$ tarting eath fan group from the contro1 rose and verifying that-Z>rH /

uuset Qup operates for at least 15 minutes.

4!C t

.2 rra a 2.

Verifying a cooling water flow rata of greater than or equal to vuoe,e

_ gpa to each cooler.

dfc b.

At least once per 18 aanths by verifying that each fan group starts automatically on a test signal, y

d ! C-Baw-ATMOSPMERIC 3/4 6-24J JUN 151971 r

.w,___,__

m OWNERS GROUP

.mmm..ii DRAFT

(

W.ORKSHEET FOR LCO 3.6.20 A.

Old LCOs 3.6.2.1 (Containment Spray System) and 3.6.2.3 (Containment Cooling System) combined to form new LC0 3.6.20.

B.

New LC0 3.6.20 is split into two options.

j-Option 1 - for plants with 3 cooling units Option 2 - for plants with 2 cooling units C.

Action statements simplified and reformatted to new form with action for 2 or 3 cooling units split out for appropriate option.

D.

Condition C.

added to both options by BWOG T. S. Committee to cover conditions other than Conditions B. & C.

E.

Completion times included in Option 1 or 2 have been inferred from standard times for similar conditions.

F.

Applicable Surveillance modes designated and approved by BWOG T. S.

Committee.

r 8

8

\\

DRAFT C'

E OWNERS GROUP

'~

fem I

Mum GENERIC TECHNICAL SPECIFICATION 3.6 ENGINEERED SAFETY FEATURES l

SYSTEM: CONTAINMENT SPRAY AND COOLING SYSTEM LCO: 3.6.20 Two SPRAY SYSTEMS and two of three COOLING UNITS shall be OPERABLE.

(OPTION 1 - For plants t.ith 3 cooling units)

APPLICABILITY: Modes 1, 2, 3, 4 Co etion Condition Required Action e

A.

One Spray System A.1 If not already OPERABLE, assure 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months INOPERABLE

-th:.t..n aaatu ons-cl' p

'- OPERABLE A.2 Restore INOPERABLE Spray System 2 44

B.

Two of three Cool-B.1 Restore at least one INOPERABLE (2houD ing Systems IN-cooling unit OPERABLE C.

Spray System or C.1 Restore either the Spray System 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months l

Cooling System DB one cooling unit INOPERABLE beyond conditions allowed M

above I

C.2 Perform the required action for Portion of new condition 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months remaining 1

l l

l D.

Required action D.1 HOT STANDBY Next 6 EQI completed hours within allowed M

I completion time D.2 COLD SHUTDOWN Next 30 I

hours 3.6-Y" '

nP "L OWNERS GROUP 'MT

+Q i

GENERIC TECHNICAL SPECIFICATION

(

M, Elm 3.6 ENGINEERED SAFETY FEATURES SYSTEM:

CONTAINMENT SPRAY AND COOLING SYSTEM LCO: 3.6.20 Two SPRAY SYSTEMS and two COOLING UNITS shall be OPERABLE.

(OPTION 2 - For plants with 2 cooling units)

APPLICABILITY: Modes 1, 2, 3, 4 Condition Required Action Completion A.

One Spray System A.1 Restore INOPERABLE Spray System 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months INOPERABLE 1

B.

One of two Cool-B.1 Restore the INOPERABLE, cooling ing Units unit INOPERABLE C.

Spray System or C.1 Restore either the Spray System 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Cooling System.

E one cooling unit INOPERABLE beyond conditions allowed M

l above l

C.2 Perform the required action for Portion of new condition 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months remaining D.

Required action D.I HOT STANDBY Next 6 EQI completed hours within allowed M

completion time D.2 COLD SHUTDOWN Next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months

(

3.6-

[ Amendment No.

]

Rev.

0.

)

C'

= OWNERS GROUP

(

i GENERIC SURVEILLANCE MElm

~,

4.6 SURVEILLANCE REQUIREMENTS FOR ENGINEERED SAFETY FEATURES LCOs SYSTEM: CONTAINMENT SPRAY AND COOLING LCO: 3.6.20 SPRAY AND COOLING SYSTEMS (FOR OPTIONS I OR 2)

Surveillance Frequency Pe ormed A&C. Each Containment Spray System shall be demonstrated to be OPERABLE:

1.

By verifying that each valve (manual, M0 Any Mode power operated or automatic) in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position 2.

By verifying,'that on recirculation QU Any Mode flow, each pump develops a discharge

{Q pressure of greater than or equal to

[ ] psig when' tested pursuant to Specification 4.0.5 3.

By verifying that each automatic valve RF Modes in the flow path actuates to its correct 5 OR 6 position on a containment spray test 4.--=

h 4E4 8F$ M k M 4

@ By verifying that each Spray Pump starts RF Modes automatically on a containment spray 5 or 6 test signal h By verifyin

]gtal leak rate less than RF Modes or equal t lallons per hour for 5 or 6 the system

a. Normal operating ure of greater than or equal td [ ] psig for those parts of the sys wnstream of the Pump Suction Isolation Valve

b. Greater than or equal to h sig t

for the piping from the cma'inment Emergency Sump isolation Valve to the Pump Suction Isolation Valve

(

(CONTINUED)

[ Amendment No.

-1 4.5-p,y, 0

1,7' C

" OWNERS GROUP 4

GENERIC SURVEILLANCE 4.6 SURVEILLANCE REQUIREMENTS FOR ENGINEERED SAFETY FEATURES LCOs SYSTEM: CONTAINMENT SPRAY AND COOLING LCO: 3.6.20 SPRAY AND COOLING SYSTEMS (CONTINUED) h Surveillance Frequency p, grmed h By performing an air or smoke flow 5 Years Modes test through each Spray Header and 5 or 6 verifying each Spray Nozzle is unobstructed B&c.

Each group of Containment Cooling Fans shall be demonstrated to be OPERABLE.

I.

By starting each fan group from M0 Any Mode the Control Room and verifying that each fan group operates

{

for at least [ ] minut,es 2.

By verifying a cooling water flow RF I

Any Mode rate of greater than or equal to

[ ] gpm to each cooler 3.

By verifying that each fan group RF Any Mode starts automatically on a ES test signal pursuant to Specification

[

] (ESF Actuation System Instrumentation) 4.6

[Amengment No.

]

Rev.

O

"" OWNERS GROUP GENERIC TECHNICAL SPECIFICATION 3.6 ENGINEERED SAFETY FEATURES P,p SYSTEM: CONTAINMENT SPRAY AND COOLING SYSTEM

~

LCO: 3.6.20 Two SPRAY SYSTEMS and two of three COOLING UNITS shall be OPERABLE.

(OPTION 1 - For plants with 3 cooling units)

APPLICABILITY: Modes 1, 2, 3, 4 Co p etion Condition Required Action e

A.

One Spray System A.1 If not already OPERABLE, assure

[72] hours INOPERABLE that an additional cooling unit is OPERABLE E

e A.2 Restore INOPERABLE Spray System Same

[72] hours B.

Two of three Cool-B.1 Restore at least one IN0PERABLE

[7] days ing Systems IN-cooling unit OPERABLE C.

Spray System or C.1 Restore either the Spray System

[72] hours Cooling System E one cooling unit INOPERABLE beyond conditions allowed AND above C.2 Perform the required action for Portion of new condition

[72] hours remaining D.

Required action D.1 HOT STANDBY Next [6]

NOT completed hours within allowed MQ completion time D.2 COLD SHUTDOWN Next [30]

(

hours 3.6

[ Amendment No.

]

l Rev.

l

C 2 OWNERS GROUP

~

MMll GENERIC TECHNICAL SPECIFICATION

,{

3.6 ENGINEERED SAFETY FEATURES

.c SYSTEM:

CONTAINMENT SPRAY AND COOLING SYSTEM LCO: 3.6.20 Two SPRAY SYSTEMS and two COOLING UNITS shall be OPERABLE.

(0PTION 2 - For plants with 2 cooling units)

APPLICABILITY: Modes 1, 2, 3, 4 Condition Required Action Completion A.

One Spray System A.1 Restore IN0PERABLE Spray System

[72] hours INOPERABLE e

B.

One of two Cool-8.1 Restore the INOPERABLE, cooling

[7] days ing Units unit IN0PERABLE e

C.

Spray System or C.1 Restore either the Spray System

[72] hours Cooling System DB one cooling unit INOPERABLE beyond conditions allowed MQ above C.2 Perform the required action for Portion of new condition

[72] hours remaining D.

Required action D.1 HOT STANDBY Next [6]

11Q1 completed hours within allowed MQ completion time D.2 COLD SHUTDOWN Next [30]

hours

(

kA[%"

I 3.6-v

o

" OWNERS GROUP GENERIC SURVEILLANCE

%E[T

(

4.6 SURVEILLANCE REQUIREMENTS FOR ENGINEERED SAFETY FEATURES LCOs SYSTEM: CONTAINMENT SPRAY AND COOLING LCO: 3.6.20 SPRAY AND COOLING SYSTEMS (FOR OPTIONS 1 OR 2)

Surveillance Frequency Pe ormed A&C.

Each Containment Spray System shall be demonstrated to be OPERABLE:

1.

By verifying that each valve (manual,

[M0]

Any Mode power operated or automatic) in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position 2.

By verifying, that on recirculation

{}

Any Mode flow, each pump develops a discharge.

pressure of greater than or equal to

[

] psig when tested pursuant to Specification 4.0.5

(-

3.

By verifying that each automatic valve

[RF]

Modes in the flow path actuates to its correct 5 or 6 position on a containment spray test signal 4.

Verifying that upon a containment

[RF]

Modes emergency sump suction test signal, 5 or 6 the containment sump isolation valves open and that a recirculation mode flow path via an OPERABLE decay heat cooler is established.

5.

By verifying that each Spray Pump starts

[RF]

Modes automatically on a containment spray 5 or 6 test signal 6.

By verifying a total leak rate less than

[RF]

Modes or equal to [6] gallons per hour for 5 or 6 the system at:

a. Normal operating pressure of greater than or equal to [350] psig for those parts of the system downstream of the Pump Suction Isolation Valve t

(CONTINUED)

[Amendmept No.

]

4.6-Rev.

2 OWNERS GROUP

%{MM i GENERIC SURVEILLANCE g

LCO: 3.6.20 SPRAY AND COOLING SYSTEMS (CONTINUED)

When Surveillance Frequency Performed

b. Greater than or equal to [55] psig for the piping from the containment Emergency Sump isolation Valve to the Pump Suction Isolation Valve 7.

By performing an air or smoke flow

[5] Years Modes test through each Spray Header and 5 or 6 verifying each Spray Nozzle is unobstructed B&C.

Each group of Cogtainment Cooling Fans shall be demonstrated to be OPERABLE.

1.

By starting each fan group from

[M0]

Any Mode the Control Room and verifying that each fan group operates for at least [15] minutes 2.

By verifying a cooling water flow

[M0]

Any Mode rate of greater than or equal to

( ) gpm to each cooler 3.

By verifying that each fan group

[RF]

Any Mode starts automatically on a ES test signal pursuant to Specification

(

) (ESF Actuation System Instrumentation) l

(

[Amendmgnt No.

]

4.6-Rev.

9 f

f

~

SPRAY ADDITIVE SYSTEM TECHNICAL SPECIFICATION 3.6.2.2 This technical specification meets the AIF selection criteria to be included as a new Tech. Spec.

It has not been included in this package, however, since-work is being proposed to delete it from the list.

s O

i t

l

A e

x

" - ~ ~ '

~,e

-r-

~~~#'v'=ew-,_

Als w 4 CO 9.C.!Z DRAFT

(

CONTAIMNT SYSTP'S f

3/a.6.4 CONTAI M NT ISOLATION VALVES LIMITING CDNDITION P08 OPERAff0N

.6.4 The contaiment isolation valves specified in Table 3.6-1 shall be OPERABLE with isolation times as shown in Table 3.61.

7'd 8

/

ICA8fLITY: MDES 1, 2, 3 and u s z,e. g,,,, ;,,s, c, r y ACTION:

rw. a d With one or more of the isolation valve (s) specified in Table 3.5-1 inoperable, nr<.s r3 naintain at least one isolation valve OPERA 8LE in each affected penetration A.,

that is open and.efther:

a.

Westore the inoperable valve (s) to OPERAALE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , b.

Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months oy use of at les mu.,.

one deactivated autamstic valve secured in the isolation position, u r,,a tr.

or r

4,. 2.

c.

Isolata each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least A c ru d one closed manual valve or blind flange, or fr* *v 4. !

/

d.

Be in at least MOT STAN09Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in CDLD g,,,

$HUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

i3.1 a 13 2 SUPVEILLANCE REOU!RD'ENTS f

/ 4.6.4.1 The isolation valves specified in Table 3.6-1 shall be denonstrated o,rr

{ OPEPA8LE prior to returning the valve to service after maintenance, repair or ggu e replacement work is perfomed on the valve or its associated actuator, control

,, m,,

or poner circuit by perfonnance of a cycling test and verification of isolation p,.

4.,. =

I Qne.

Pnoce na

.6.a.2 Each isolation valve speciffed in Table 3.6-1 shall be denoniTPITsd OPERA 8L during the COLD SHUIDOWN or REFUELING MDE at least once per 18 mo'iths by:

,7/j r.

Verifyino that on a contafment isolation test signal, each automatic U""

a clation valve actuates to its isolation position.

A*4 b.

Verifyine that on a contaiment radiation-high test stonal, each puree I

and exhaust autopstic valve actuates to its isolation position.

Lee,((j y, ~ << <

, a Trs M t

A.+

l

(

B&W-A7P057WE*!C 3/4 6-2fk1 JUL 15 571

DrC.\\ w r-s t j-*f )

w

(-

Cor2 T ir Sv57!ws

(

SURVEILLANCE #EOUIREwir*5 (Continued) z'~c c. a s 4.3 The isolation time of each opwer operated or automatic valve of Table 3.61 shall be detemined to be within its limit when tested pursuant to A3 cification 4.0.5.

Each contairment purge isolation valve shall be Nmonstrated 0*DAh d.6.A.4 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months a*ter each closing of the valve, except when the valve is

,, g et,

,a being used for parltiple cyclings, then at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , by veri.

3y,,,

r,., y fying that when the seasured leakage rate is added to the leakage ratas oetemined oursuant to Specification d.E.1.2d for all other Type P and C l d

penetrations, the cambined leakage rate is less than or soual to 0.60 L,.

9 l

l l

/

L BAWATNOS'NERIC 3/4 6-29J JUL )$ pyg

=w

+ =.,

C' M OWNERS GROUP Bm D9 AFT

(

WORKSHEET FOR LCO 3.6.12 Added a statement under Applicability that provisions of Spec. 3.0.4 not applicable to valves exempted by NRC approval and included note under required actions statement to the effect that certain valves may be opened on an intermittent basis with prior NRC approval.

The change to STD. Tech.

Spec. was recommended by the BWOG Tech Spec. Committee.

Surveillance for LCO 3.6.12 A.

Surveillance items rearranged to give 1 to I correspondence with LCO.

B.

Item 4.6.4.1 omitted since it is introductory in nature and is superfluous to Surveillance Action items.

C.

Item 4.6.4.2.b. omitted since BWOG construed a containment radiation-high test signal to be included as one of the containment isolation test signals already included in Surveillance Item A.4.

D.

Applicable Surveillance modes designated and approved by BWOG T.S.

Committee.

t l

l l

i e

l C

E OWNERS GROUP

' pm uhm GENERIC TECHNICAL SPECIFICATION g

3.6 ENGINEERED SAFETY FEATURES

,g. e r._

SYSTEM: CONTAINMENT U: Y.E" i LCO: 3.6.12 The CONTAINMENT ISOLATION VALVES shall be OPERABLE.

)temy

,s. ;. -.,. "': :per"! cit t:= r; l'-+=d p n f k-o- r:1 _

f APPLICABILITY: Modes 1, 2, 3, 4 Provisions of Spec. 3.0.4 not applicable to valves exempted by NRC approval Condition Required Action Completion A.

One or more isola-A.1 Maintain at least one iso-48 ours tion valves speci-lation valve OPERABLE in fied it: _"- " x.4 each affected penetration INOPERABLE that is open and restore the INOPERABLE valve (s)

(i A.2 Isolate each affected pene-48 hours tration by use of at least one deactivated automatic valve secured in the iso-lation position DB A.3 Isolate each affected pene-hours tration by use of at least V

one closed manual valve or blind flange

..............N0TE---------------

Certain valves may be opened on an intermittent basis under ad-ministrative control provided prior NRC approval has been granted.

B.

Required action B.1 HOT STANDBY Next 6 NQI completed hours within allowed ehD completion time B.2 COLD SHUTDOWN Next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months 3.6-

[^"* 6*"' "

Rev.

C

? OWNERS GROUP fam GENERIC SURVEILLANCE P"'

mm-Mmm

r i

4.6 SURVEILLANCE REQUIREMENTS FOR ENGINEERED SAFETY FEATURES LCOs SYSTEM: CONTAINMENT LCO: 3.6.12 CONTAINMENT ISOLATION VALVES h

Surveillance Frequency p, grmed Each Containment Isolation Valve shall be demon-strated OPERABLE.

A.1 By verifying acceptable leakage as specified by t least i As Appendix J once per I Specified 24 months in [ ]

........................N0TE-----------------------

The provisions of Specification 4.0.1 are not applicable to A.1 above.

I A.2 By verifying manual valves locked closed Prior to Modes 5,6 Mode 4 A.3 By verifying stroke time within specified As Speci-As limits fled in Specified

[ ]

in [ ]

A.4 By verifying that the valve strokes to its RF Hodes 5,6 isolation position on a containment isolation signal l

[ Amendment No.

]

4.6-p,v.

0 1

~ - ' -

' ~ ~

Q M OWNERS GROUP GENERIC TECHNICAL SPECIFICATION MWil 3.6 ENGINEERED SAFETY FEATURES h[Tia$U SYSTEM:

CONTAINMENT LCO: 3.6.12 The CONTAINMENT ISOLATION VALVES shall be OPERABLE.

Items covered by this specifications are listed (in the Bases).

APPLICABILITY: Modes 1, 2, 3, 4 Provisions of Spec. 3.0.4 not applicable to valves exempted by NRC approval Condition Required Action Completion l

A.

One or more isola-A.1 Maintain at least one iso-

[4] hours tion valves speci-lation valve OPERABLE in fied [in the Bases) each affected penetration INOPERABLE that is open and restore the INOPERABLE valve (s)

E

{

A.2 Isolate each affected pene-

[4] hours tration by use of at least one deactivated automatic valve secured in the iso-lation position E

A.3 Isolate each affected pene-

[4] hours tration by use of at least one closed manual valve or blind flange

..............N0TE---------------

Certain valves may be opened on an intermittent basis under ad-ministrative control provided prior NRC approval has been granted.

B.

Required action B.I HOT STANDBY Next [6]

MI completed hours within allowed MQ completion time B.2 COLD SHUTOOWN Next [30]

i hours 3.6 (Amendment No.

]

Rev.

1

C

? OWNERS GROUP GENERIC SURVEILLANCE fcC C'

I gg

. 'u a

I 4.6 SURVEILLANCE REQUIREMENTS FOR ENGINEERED SAFETY FEATURES LCOs SYSTEM: CONTAINMENT LCO: 3.6.12 CONTAINMENT ISOLATION VALVES Surveillance Frequency Pe ormed Each Containment Isolation Valve shall be demon-strated OPERABLE.

A.1 By verifying acceptable leakage as specified by

[24] hours As Appendix J after Specified closing in [ ]

NOTE-----------------------

except The provisions of Specification 4.0.1 are not multiple applicable to A.1 above.

cycles, then once per[72]

hours A.2 By verifying manual' valves locked closed Prior to Modes 5,6

(

Mode 4 A.3 By verifying stroke time within specified As Speci-As limits fied in Specified

[

]

in [ ]

A.4 By verifying that the valve strokes to its

[RF]

Modes 5,6 isolation position on a containment isolation signal

[ Amendment No.

)

4.6-p,y, 1

)

________

ML20211E453

Text

SUBJECT:

Enclosures:

SUMMARY

Subject:

Dear Committee Members:

16.1 INTRODUCTION

16.1 INTRODUCTION

16.1 INTRODUCTION

16.1 INTRODUCTION

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