ML18040A218

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Forwards Niagara Mohawk Power Corp,Nine Mile Point Nuclear Station Unit 2 - Pump & Valve First Ten Yr In-Service Testing Program Plan, NMP2-IST-001.Plan Incorporates Changes Per GL-89-04
ML18040A218
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 11/08/1993
From: Terry C
NIAGARA MOHAWK POWER CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17059A098 List:
References
GL-89-04, GL-89-4, NMP2L-1453, NUDOCS 9311150064
Download: ML18040A218 (114)
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Text

ACCEI ERAT DOCVMENT DIST VTION SYSTEM REGULAT INFORMATION DISTRIBUTION STEM (RIDS)

ACCESSION NBR:9311150064 DOC.DATE: 93/11/08 NOTARIZED: NO DOCKET g FACIL:.50;-410 Nine Mile Point Nuclear Station, Unit 2, Niagara Moha 05000410 AUTH.NAME AUTHOR AFFILIATION TERRY,C.D.

Niagara Mohawk Power Corp.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

D NOTES:

SUBJECT:

Forwards "Niagara Mohawk Power Corp, Nine Mile Point I

Nuclear Station Unit 2 Pump 6 Valve First Ten Yr In-Service Testing Program Plan," NMP2-IST-001.Plan incorporates changes per GL-89-04.

DISTRIBUTION CODE:

A047D COPIES RECEIVED:LTR f

ENCL Q SIZE:

TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code RECIPIENT ID CODE/NAME PD1-1 LA MENNINGPJ COPIES LTTR ENCL 1

0 2

2 RECIPIENT ID CODE/NAME PD1-1 PD COPIES LTTR ENCL 1

1 D

INTERNAL: ACRS NRR/DE/EMEB NUDOCS-ABSTRACT OGC/HDS1 RES/DSIR/EIB 6

6 AEOD/DSP/ROAB 1

1 NRR/EMCB 1

1 OC Q)CB 1

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1 1

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EXTERNAL: EG&G BROWNpB NRC PDR 1

1 1

1 EGGG RANSOMEPC NSIC 1

1 1

1 D

NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTEI CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISIS FOR DOCUMENTS YOU DON'T NEED!

D TOTAL NUMBER OF COPIES REQUIRED:

LTTR 22 ENCL 19

NIAGARAMOHAWKPOWER CORPORATION/301 PLAINFIELDROAD, SYRACUSE, N.Y. 13212/TELEPHONE (315) 474-1511 November 8, 1993 NMP2L 1453 U. S. Nuclear Regulatory Commission A'ttn:-.Document.'Control Desk-I Washington, D. C. 20555 Re:

Nine Mile Point Unit 2 Docket No. 50-410 F-Gentlemen:

Enclosed is the "Niagara Mohawk Power Corporation, Nine MilePoint Nuclear Station Unit2-Pump and Valve First Ten-Year In-Service Testing Program Plan", NMP2-IST-001, Revision

4. This revision supersedes the previous revision and incorporates changes made in accordance with Generic Letter 89-04, 10CFR50.59 and various Commission Safety Evaluation Reports.

There are no Code relief requests or deviations in this revision which require Commission evaluation or approval.

This Revision is being submitted in compliance with Generic Letter 89-04.

Very truly yours, C. D. Terry Vice President Nuclear Engineering MGM/mls Attachment p: W~Ah Regional Administrator, Region I Mr. R. A. Capra, Director, Project Directorate I-l, NRR Mr. J. E. Menning, Project Manager, NRR Mr. B. S. Norris, Senior Resident Inspector A

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SUMMARY

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Description of Change Reason for Change

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4, 6.

7.

8.

9.

Revise Technical Specification Leakage test references in the IST Program

Plan, as well as editorial changes Change Request 2-91-IST401:

Add cold shutdown justification ISCNS-I for testing the containment

, vacuum

breakers, 2ISC*RV33A and B through RV36A and B Change Request 2-91-IST-002:

Correct test frequency for valves 2SWP~V1002A and B, to be consistent with Relief Request No. SWP-VRR2 Change Request 2-91-IST403:

Delete'Section III, Pump and Valve IST Program Plan from the general 10-year ISI Program Plan since the Pump and Valve

'" IST Program Plan exists under a separate document, NMP2-IST401 Change Request 2-91-IST404:

Revise SWPZS-2 to delete valves SWP~V1024 and V1025 and add them to quarterly test due to additional system lineup evaluation and change

'Change Request 2-91-IST405

Delete the close safety function and the associated test requirements for valves 2CMS~SOV23A through E

and 2CMS~SOV25A through D

per design basis Appendix "B" determination No. 91409 and Safety Evaluation No. 91405, Rev. 2; the valves'afety

" function is to open only.

Change Request 2-91-IST407:

Editorial, to correct

-, change request numbers incorporated into Revisions 1,2, and 3 Change Request 2-91-IST408:

To correct page number in SWP system Change Request 2-91-IST409:

Change

10CFR50, Appendix J, LJ type C test with air to Appendix J, LK type C test with water for systems that are normally filled with water and operating under post-accident condition To reflect Tech Spec Amendment 37, dated 3/24/92, TAC No. M82635 To comply with NRC SER dated May 28, 1991, TAC No.

79781 Editorial change Administrative change To comply with the Code quarterly test requirements To test the valves to their safety function To comply with QA audit recommendation Editorial, to correct a typo To reflect NMP2 Tech Spec amendment No.

22, dated October 11, 1990 (TAC No. 7719)

NMP2-IST-001, Rev. 4 p$ t(/5 09 Qg October 1993 I

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Description of Change Change Request 2-92-IST-002:

To perform pump vibration testing in accordance with OMA-1988, Part 6 'ode per NRC-approved Relief 'equest.

Additionally, add editorial changes and clarific'ation to the Program Plan I

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Change, Request 2-92-IST403:

Delete valves 2CMS~SOV25A through D from testing and add them to the Exclusion/Justification section, retired in place per PM 89-94 and Safety Evaluation 91-84

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4 Change Request 2-92-IST-004:

Change page number in the CMS system

'hange Request 2-92-IST-005:

Add Relief Request GVRR-5 to deviate from ASME Section XI Subsection IWV-3417(a) to allow the use of established reference value instead ofprevious stroke time for trending, per NRC GL8944, Position 6 Change Request 2-92-IST406:

Delete cold shutdown justification and testing frequency and replace it with once per refueling outage frequency for the vacuum breakers 21SC*RV33A and B through 36A and B, per Tech Spec Section 4.6.2.1 and 4.6.4.

Further design basis analysis Appendix B determination f8947, Rev. 2 and USAR Section 6.2.1.1.2 determine that valves 2ISC~RV33A and B through 36A and B are not containment vacuum breakers

and, therefore, OM-1-1981, Subsection 1.3.4.2 test frequency is not applicable.

LDCR 2-92-IST-001, Rev.

1:

Editorial changes, changes previous CR 2-92-IST406 to LDCR 2 IST401 LDCR 2-92-1ST@02:

Add Relief Request ICS-VRR-2 to the IST Program Plan to allow the performance of disassembly and inspection in lieu of full forward flow exercise for valve 2ICS~V29.

This Relief Request is approved per NRC GL 8944, Position 2.

Additional changes to specify individual test requirements for the pressure relief valve devices and other editorial changes LDCR 2-92-IST403:

Revise GVRR-5 to cover all powerwperated valves to allow the use ofestablished reference value instead of previous stroke time for trending per NRC GL 8944, Position 6 Reason for Change To comply with NRC SER, dated 10/29/90 g AC No. 63429)

Component retired in place with no safety function Editorial change, typo For proper trending per NRC GL 8944, Position 6 To test the valves in accordance with Tech Spec frequency which meets and exceeds the OM-1 Code frequency To comply with Nuclear Interface Procedure NIP-LPPAI System configuration does not allow full forward flow except partial flow at quarterly For proper trending per NRC GL 89~, Position 6 NMP2-IST-001, Rev. 4 October 1993 Page ii of v

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Description of Change LDCR 2-93-IST405:

Revise Relief Request SWP-VRR-2 for valves 2SWP~V1002A and B to perform partial exercise quarterly and disassembly and inspection once per refueling outage per NRC GL 8944, Position 2; also adding a statement to Section I.2, "Basis",

to ensure Code requirements are implemented within six months time period for components whose design function is upgraded and requires testing per ASME/ANSI Code Reason for Change To comply with NRC regulations and guidelines and to document deviation from the Code;

also, to state NMPC position for time required to implement the Code for components whose design function is upgraded (not modification) 19.

LDCR 2-92-IST406:

Revise pump testing program To comply with NRC SER dated April 19, 1993 (TAC No.

plan.to be in compliance with ASME/ANSI OM4, M85500) 1988 Code pursuant to 10CFR50.55a(0 20.

LDCR 2-93-IST407:

Revise Tech Spec leakage references, TS amendment nos.

22, 37, and 49; incorporate all issued changes against IST Program Plan, Rev. 3, into Rev. 4 To comply with NRC GL 89M requirements and to reflect plant Tech Spec changes NMP2-'IST-001, Rev. 4 October 1993 Page iiiof v

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TABLEOF CORI'ENTS SECTION I PAGE I-1.0 I-2.0 I-3.0 IC.O I-5.0 I-6.0 I-6.1 I-6.2 I-6.3 I-6.4 I-6.5 I-7.0 I-8.0 Introduction t

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General Program Plan Concept Organization Definitions Relief Requests Discussion....

Relief Request GVRR Valves Relief Request GVRR Valves Relief Request GVRR Valves Relief Request GVRR Valves Relief Request GVRR Valves Pump and Valve P&ID's.....

References

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. I-21 SECTION II PUMP IST PROGRAM PLAN II-1.0 II-2.0 II-3.0 II-3.1 II-3.3 II-4.0 II Pump Program Introduction"..........

Pump Inservice Testing Scope Pump Test Table - Nomenclafure.......

Sample Pump /ST) Program Table Pump Test Tables & Notes Pump Relief Requests..............

.. II-1

.. II-2

.. II-4

.. II-6

.. II-7

.. II-10 SECTION IIIVALVEIST PROGRAM PLAN m-1.0 III-2.0 III-3.0 III-3.1 III-3.2 III-4.0 Valve Program Introduction..........

Valve Inservice Testing Scope Valve Test Table - Nomenclature....

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Sample Valve /ST) Program Table Valve Table Codes Valve Test Tables:

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.. III-7 III-10 III-11 Attachment 1

Attachment 2

Attachment 3

Attachment 4

Attachment 5

AAS CCP CMS CPS...

CSH III-1-1 III-2-1 III-3-1 III-4-1 III-5-1 NMP2-IST-001, Rev. 4 October 1993 Page iv of v

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Table of Contents (Cont'd.)

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III-6-1 III-7-1 III-8-1 III-9-1 III-10-1 III-11-1 III-12-1 III-13-1 III-14-1 III-15-1 III-16-1 III-17-1 III-18-1 III-19-1 III-20-1 III-21-1 III-22-1 III-23-1 III-24-1 III-25-1 III-26-1 III-27-1 III-28-1 III-29-1 III-30-1 APPENDIX A EXCLUSION/JUSTIFICATIONTABLE NMP2-IST-001, Rev. 4 October 1993 Page v of v

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1.0 INTRODUCTION

This document presents Revision 4 to the First Ten Year Program Plan for Inservice Testing (IST) of Pumps and Valves at the Nine Mile Point Nuclear Station Unit 2 (NMP-2) in compliance with the requirements of 10CFR50.55a(g) and Station Technical Specification 4.0.5.

This Program Plan was prepared in accordance with the rules of the ASME Boiler and Pressure Vessel Code,Section XI, 1983 Edition through Summer 1983 Addenda, and ASME/ANSIOM-1 and OM-6, 1988 for relief valves and pump testing respectively.

Unit 2 IST Program Plan, Revision 1, was issued on 4/6/88 and incorporated the following Change Requests:

PSI/ISI CR¹ 305, 306, 307, ISI/IST¹ 309, 310, 311, 312, 313, 314, 315, 316, 317, 318, 319, 320, 321, 322, 323, 324, 325, 326, 327, 328, 329, 330, 331, 332, 333, 334, 335, 336, 377, 338, 343, 344, 345, 346, 347, 350, 351, 352, 353, 354 and 355.

Revision 2 was issued on 9/11/90 and incorporated the following Change Requests:

ISI/IST CR¹ 356, 362, 363, 364, 365, 366, 367, 369, 371, 372, 373, 374, 375, 376, 377, 2-88-034-001 (Rev. 2), 2-89-034-024, 2-89-034-025, 2-89-034-028, 2-89-034-030 (Rev. 1), 2-89-034-31, 2-89-034-32,2-89-034-42,2-89-034-60,2-89-034-61,2-89-034-62, 2-89-2-89-034-63, 2-89-034-64, 2-89-034-65, 2-89-034-66, 2 034-67, 2-89-034-68, 2-89-034-69, 2-89-IST-70, 2-89-034-71, 2-90-IST-81, 2-90-IST-92, 2-90-IST-93, 2-90-IST-107, 2-90-IST-112, 2-90-IST-113, a!id 2-90-IST-114.

Revision 3 incorporates the following Change Requests:

2-90-IST-001, 002, 003, 004, 005, 006, 010, 011, 012, 013, 015, 016, 018, 019, 020, 021, 022, 023, 024, 025, 028, 029, 030, 031, 032, 033, a!ld 2-91-IST-034.

All requests for relief from the requirements of 10CFR50.55a(g) and ASME Code Section XI since Revisions 1 and 2 have been submitted to the NRC and interim relief has been granted per NRC SER dated October 29, 1990 (Ref. TAC No. 63429).

These Relief Requests are included in this document and are being implemented.

Additionally, in the effort to standardize the format of the Unit 1 and 2 ISI/IST Program Plans, this document format was changed to more closely follow the format established for the Unit 1 IST Program Plan, NMP1-IST-001.

Additional changes incorporated into this document are as follows:

NMP2-IST-001, Rev. 4 Section I - October 1993 Page 1 of 22

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1.0 Introduction (Cont'd.)

Relief Requests EGA-VRR-1 and EGA-VRR-2 were deleted.

The valves addressed in these Relief Requests are non-ASME; therefore, a Relief Request is not required.

The contents of the Relief Requests were incorporated into Notes (1) and (2).

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All notes pertaining to valve set points were removed.

These notes were found in the ISC, RHS, and SVV Valve Tables.

These setpoints are included in the plant surveillance procedures.

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Various changes were made to "Relief Request" and "Cold Shutdown Identification Nomenclature" as listed in the Record of Revisions.

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Added the specific required test parameter for Relief and Vacuum Breakers per OM-1.

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Perform inservice testing for all pumps in accordance with OM-6, pursuant to 10CFR50.55a(f)(4)(iv) per NRC SER dated April 19, 1993 (Ref. TAC No. M85500).

Allother changes to this document were editorial changes only.

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2.0 BASIS The Nine Mile Point Unit 2 P&ID drawings were used in conjunction with the ASME XI Code, Generic Letter 89-04, the Niagara Mohawk USAR, ANSI/ASMEOM-1, and ANSI/ASMEOM-6 to prepare the NMP2 1st Interval IST Program Plan and the Exclusion/Justification document.

The Exclusion/Justification document contains components which would otherwise be found in the IST Program, but for special cases have been exempted from the Plan.

The bases for excluding these components may be summarized as:

The component is exempt from testing per ASME XI IWV-1200.

This includes valves used for operating convenience, valves used for system control, and valves used only for maintenance or test.

The component is safety-related, but considered passive with respect to its function during an accident.

The component function has been evaluated by Niagara Mohawk Design Engineering and/or Licensing.

Components required to operate post-accident have DIV I or DIV III Class 1E power available.

The Class 1E power designation, called "overcoding", is represented by yellow or green, and is identified on the P&IDat each safety-related component mark number.

Components which are not safety-related (pipe class 4 or N), or do not receive Class 1E power post-accident, are

~n required to be tested per ASME XI and, consequently, are

~no contained in this document.

Passive components which do not have to change position to perform their intended safety function(s) will be listed and comprise many of the entries in this document.

As part of the development of this document, a problem report (PR9301) and 33 associated supplements were prepared to identify components subject to testing. The Engineering dispositions to these PR Supplements and the Program Change Requests were generated to define the IST Program at Unit 2.

All safety-related components considered passive during an accident were evaluated by Engineering via a PR Supplement or by Licensing via a 10CFR50 Appendix B Quality Determination and inserted into the Exclusion/Justification Document. The attached Table contains a listing of the justification material used to substantiate this document.

In addition to the reference Code Edition and Addenda, the Program Plan has been prepared in compliance with the NRC guidance (except where exception/relief has been requested) contained in the NRC letter dated January 1978, "Guidance for Preparing Pump and Valve Testing Program Descriptions and Associated Relief Requests Pursuant to 10CFR50.55a(g)",

and 10CFR50.55a(f)(4)(iv) per NRC SER dated April 19, 1993 (Ref. TAC No. M85500); the NRC letter dated November 1976, "NRC Staff Guidance for Complying with Certain Provisions of 10CFR50.55a(g) Inservice Inspection Requirements"; and NRC Generic Letter 89-04, dated April 3, 1989, "Guidance on Developing Acceptable Inservice Testing Programs".

These four documents provide the basis for selection of components, test requirements, and relief requests.

NMP2-IST-001, Rev. 4 Section I - October 1993 Page 3 of 22

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2.0 BASIS (Cont'd.)

Additionally, the Valve Testing Program adopts Code Case N-415 (approved for use by the NRC per R.G.1.147, Rev. 5), which permits the use of ANSI/ASME OM-1, 1981 as alternative requirements for replacement, repair and maintenance, inservice testing, and testing frequency for safety valves, primary containment vacuum relief valves, relief valves (including all other vacuum relief valves which are tested as relief valves) and rupture disks.

Regarding the inclusion of certain valves based on their Containment/Reactor Coolant Isolation functions, this Program is inclusive of valves which are categorized as Containment Isolation Valves, as specified in the latest NMPC NMP2 Appendix J Program.

Current NMP2 practice is to perform Leakage Testing in accordance with the NMP2 Appendix J Program.

Any changes to the Appendix J Program shall be incorporated into the IST Program Plan as applicable.

NMPC's position regarding time required to implement Code (ASME/O&M) requirements for updated/upgraded design basis or design requirements is six (6) months from the update of the applicable design basis documents (i.e., Tech Spec, USAR, Appendix "B" determination).

Pump inservice testing at NMP2 shall be performed in accordance with ASME/ANSI OM-6, pursuant to 10CFR50.55a(f)(4)(iv) per NRC SER dated April 19, 1993 (Ref. TAC No. M85500).

NMP2-IST-001, Rev. 4 Section I - October 1993 Page 4 of 22

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3.0 GENERAL PROGRAM PLAN CONCEPT The Program Plan specifiesSection XI testing requirements for the valves and ASME/ANSIOM-6

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for the pumps providing a safety-related function.

By definition, a safety-related function is one that is required to assure:

A.

B.

C.

integrity of the reactor coolant pressure boundary; capability to achieve and maintain safe shutdown; capability to prevent or mitigate the consequences of postulated accidents which could result in off-site exposures comparable to the guidances of 10CFR50.55a(g),

Part 100.

The selection criteria used for components included in this Program Plan are safety-related active components.

Safety-related passive components have no operability test requirements, and are not included in the Program Plan.

Only those safety-related passive components which have leakage and position indication requirements have been included in the Program Plan.

Station Technical Specifications, manufacturers recommendations, system operating conditions, etc. may suggest additional components which should be included in the overall station testing program, but whose functions fall outside the criteria above and are not addressed by this Program Plan.

In general,Section XI and ASME/ANSI OM-6 require Quarterly testing of components unless it is impractical to do so.

This Program specifies quarterly functional testing of pumps and valves unless it has been determined that such testing would:

A.

B.

C.

D.

E.

render a safety-related system inoperable; cause a reactor scram or turbine trip; require significant deviations from the normal operations; require entry into inaccessible station areas; increase the possibility of an inner system LOCA.

Each component excluded from quarterly testing has been analyzed to determine when appropriate testing may be performed. Ifoperation of a valve is not practical during station operation, the ASME Section XI Code allows part-stroke exercising during normal station operation, and full-stroke exercising at cold shutdown.

Since the ASME Section XI Code allows testing at cold shutdown, this Program does not request relief for those valves for which testing is delayed until cold shutdown.

The Valve IST Program Plan provides a justification for the delay of testing until cold shutdown.

These justifications are prepared in a format similar to relief requests, and are included following the Valve Test Tables for each system.

Where it has been determined that testing is not practical during station operation, or at cold shutdowns, a specific relief request has been prepared unless the valves are non-ASME.

The specific relief requests provide justification for not performing the ASME Section XICode required testing, and also provide appropriate alternate testing.

NMP2-IST-001, Rev. 4 Section I - October 1993 Page 5 of 22

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3.0 General Program Plan Concept (Cont'd.)

In addition to specific relief requests, general relief requests which address specific ASME Section XI Code requirements found to be impractical for this station have been prepared.

Because of the general nature of these relief requests, and the number of components involved, they are presented in Section I and are not in the individual system sections.

NMP2-IST-001, Rev. 4 Section I - October 1993 Page 6 of 22

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4.0 ORGANIZATION The Pump and Valve Inservice Testing Program Plan is organized into three sections:

Section I represents the general program commitment basis, the conceptual framework used in developing the Program

Plan, and general relief requests for Code requirements found to be impractical for this Station.

Section II deals specifically with the Pump Test Program.

Section IIIdeals specifically with the Valve Test Program.

Sections II and III are formatted in a manner to aid review.

Each Section summarizes the basis and concepts used to formulate the Pump and Valve Test Tables.

Pump testing requirements are summarized in a single Pump Test Table attached to Section II.

Valve test requirements are summarized in Valve Test Tables attached to Section III. The Valve Test Tables are arranged into separate attachments for each system.

Where quarterly testing has been found to be impractical, either a justification for delay of test to cold shutdown or a relief request is provided following the appropriate Pump or Valve Test Table.

In those cases where additional discussion of the test requirements for a component is needed, the remarks column of the Test Table contains a note number.

These notes may be found following the Valve Test Tables for each system.

NMP2-IST-001, Rev. 4 Section I - October 1993 Page 7 of 22

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5.0 DEFINITIONS The terms below, when used in the Inservice Testing Program Plan, are defined as follows:

Quarterly An interval of 92 days for testing components which can be tested during normal plant operation.

Cold Shutdown Testing deferred until cold shutdown where testing shall commence within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of achieving cold shutdown, and shall continue until testing is complete or until the plant is ready to return to power.

Completion of cold shutdown testing is not a

prerequisite to return to power.

Any testing not completed at one cold shutdown shall be preferentially scheduled for testing at subsequent cold shutdowns.

Cold shutdown testing of a component is not required if less than 92 days have passed since the last cold shutdown test of that component.

NOTE:

Cold Shutdown test results in the "Alert Range" shall have the test frequency of the applicable component(s) increased such that testing is performed during subsequent cold shutdown ifnot performed during the last 45 days, Refueling Testing deferred to refueling willbe performed during the normally scheduled refueling shutdown before returning to power operation.

Pressure Isolation Any valve which acts as an isolation boundary between the high pressure Reactor Coolant System and a system having a lower operating or design pressure.

Containment Isolation Unless exempted per Technical Specification, any valve which performs a containment isolation function and is included in the Appendix J Leakage Rate Test Program.

Active Any valve which is required to change position to accomplish its safety-related function.

NMP2-IST-001, Rev. 4 Section I - October 1993 Page 8 of 22

4

5.0 Definitions (Cont'd.)

Passive Any valve which is not required to change position to accomplish a specific function.

Additionally, passive valves are those valves where the normal and safety position are the same, and the valve is not required to change position during any normal plant operating condition, except for convenience

use, and provided the valve does not receive an automatic actuation signal.

NMP2-IST-001, Rev. 4 Section I - October 1993 Page 9 of 22

6.0 RELIEF REQUESTS DISCUSSION 6.1 General Written relief requests, as allowed by 10CFR50.55a(g)(5)(iii), are discussed in Section I for general relief requests; Section IIfor specific pumps; and Section IIIfor specific valves, to provide justification for:

performance of testing requirements on pumps and valves that are impractical during both operation and cold shutdown;

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the use of alternate testing methods when Code requirements are either impractical, or where the alternate methods provide equal to, or greater, assurance of pump and valve operational readiness.

Each relief request is formatted to include the following information:

relief request number; system (specific relief requests only);

pump or valve identification number; category (valves only);

class; function (specific relief requests only);

testing requirement; basis for relief; alternate testing.

6.2 Generic Pump and Valve Relief Requests Generic relief requests are used when a relief request applies to pumps or valves in general, e.g., all containment isolation valves that are Type C tested, or all centrifugal pumps.

These relief requests are formatted for numerical filing as follows:

GVRR-Y or GPRR-Y where:

GVRR = Generic Valve Relief Request; GPRR = Generic Pump Relief Request; Y = Sequential Number NMP2-IST-001, Rev. 4 Section I - October 1993 Page 10 of 22

6.0 RELIEF REQUFDTS DISCUSSION (Cont'd.)

6.3 Specific Relief Requests

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These reliefs are used to provide relief to specific pumps or valves and are formatted for numerical filing as follows:

XXX-PRR-Y or XXX-VRR-Y where:

XXX = System Designation; PRR = Pump Relief Request; VRR = Valve Relief Request; Y = Sequential Relief Request number in any system.

NMP2-IST-001, Rev. 4 Section I - October 1993 Page 11 of 22

6.3 RELIEF REQUEST NO. GVRR-I Valves Containment Isolation Valves Category A

Class 1,2 Testing Requirements Leak rate test in accordance with Subsection IWV-3420.

Basis for Relief IWV-2200(a) defines "Category A" valves as "valves for which seat leakage is limited to a specified maximum amount in the closed position for fulfillment of their function".

Containment isolation valves, as defined in technical specifications, have been identified as "Category A" valves for ASME XI testing purposes since they are required to be leak rate tested.

Leak rate requirements for these valves are based on a total allowable leakage rate for all valves.

Only those containment isolation valves with potential for bypass leakage paths outside containment have individual maximum allowable leak rates (as defined in technical specifications).

For example, excess flow check valves listed in technical specifications as containment isolation valves will receive an operability test and will not receive leak rate testing as allowed by technical specifications and IWV-3421.

Since containment isolation valves are "Category A", leakage rate testing requirements ofIWV-3420 must be satisfied.

The leakage rate testing performed, per Appendix J, satisfies the requirements ofIWV-3421 through 3425. However, it does not satisfy the individual valve leakage rate analysis and corrective actions required by IWV-3426 and 3427.

Therefore, the requirements of IWV-3426 and 3427(a) will be applied to individual leakage rate testing results obtained during (Appendix J) technical specification required surveillance testing.

The requirements of IWV-3427(b) will not be applied as outlined in NRC generic letter No. 89-04.

Alternate Testing Those valves listed as containment isolation valves in the Technical Specifications and categorized as "Category A or AC" valves (with the exception ofcertain valves in Table 3.6.3-1, Item D) shall be leak rate tested in accordance with 10CFR50, Appendix J.

In addition, individual valve leakage rates willbe obtained by test or analysis and the requirements of IWV-3426 and 3427(a) will be applied via a separate procedure.

NMP2-IST-001, Rev. 4 Section I - October 1993 Page 12 of 22

6.3 Relief Request No. GVRR-1 (Cont'd.)

Containment isolation valves that are exempted from 10CFR50, Appendix J, shall meet the test requirements of the Technical Specification Table 3.6.3-1 notes, the USAR Table 6.2-56, 10CFR50, Appendix J requirements, or of the Inservice Testing Program.

For

example, excess flow check valves shall meet the requirements of Technical Specifications Table 3.6,3-1, Note "E", and IST Program Plan Relief Request GVRR-2.

NMP2-IST-001, Rev. 4 Section I - October 1993 Page 13 of 22

Valves 6.4 RELIEF REQUEST NO. GVRR-2 Excess Flow Check Valves Category Class Testing Requirements Quarterly Operability Testing Basis for Relief Excess flowcheck valves are installed on instrument lines penetrating containment to minimize leakage in the event of an instrument line failure outside the containment in accordance with Regulatory Guide 1.11.

The excess flow check valve is basically a spring loaded ball check valve.

Since the system is normally in a static condition, the valve ball is held open by the spring.

Any sudden increase in flow through the valve (i.e., line break) will result in a differential pressure across the valve which will overcome the spring and close the valve.

The valve is designed to allow some leakage past the seat in the closed position.

This leakage will act to equalize pressure across the valve in the event the excess flow condition is corrected, thus allowing the spring to reopen the valve.

At NMP2, there are excess flow check valves with and without installed position indication.

Functional testing of valve closure is accomplished by venting the instrument side of the valve while the process side is under pressure and observing the position indicator (for those with installed position indicators) and by verifying that only a small amount of leakage exists through the vent.

The testing described above requires the removal of the associated instrument or instruments from service.

Since these instruments are in use during plant operation and cold shutdown, removal of any of these instruments from service could cause a spurious signal which could result in a plant trip, an inadvertent initiation of a safety

system, loss of decay heat removal and/or the defeating of safety interlocks.

In addition to the plant safety concerns, personnel safety concerns must be considered since the process side of many of these valves is normally high pressure

(>500 psig) and/or high temperature

(>200'F) and highly contaminated reactor coolant.

The remainder of the valves process side is the containment atmosphere which is inerted, contaminated, and at atmospheric pressure during operation and cold shutdown; therefore, the test described above cannot be accomplished.

NMP2-IST-001, Rev. 4 Section I - October 1993 Page 14 of 22

6.4 Relief Request No. GVRR-2 (Cont'd.)

I In summary, due to the plant and personnel safety concerns and plant operating conditions that prohibit the testing of these valves quarterly or at cold shutdown, testing will be performed at refueling when decay heat loads are at a minimum, the containment is de-inerted and ventilated, and safety systems can be removed from service to prevent inadvertent initiation.

Alternate Testing Functional testing willbe performed at refueling.

NMP2-IST-001, Rev. 4 Section I - October 1993 Page 15 of 22

6.5 REUEF REQUEST NO. GVRR-3 Valves Rapid actuating power-operated valves with stroke times of 2 sec or less Category A,B Testing Requirements IWV-3417 requires corrective action ifthe measured stroke time for a valve that normally strokes in 10 sec or less varies by 50% from the last measured stroke time. IWV-3413 allows measurement to the nearest sec for stroke times of 10 sec or less.

Basis for Relief For rapid actuating power-operated

valves, the application of the above criteria could result in requiring corrective action when the valves are functioning normally. These valves generally are small air and solenoid operated valves which, because oftheir size and actuator types, stroke very quickly.

Operating history on this type of valve indicates that they generally either operate immediately or fail to operate in a reasonable length of time. The intent of the referenced Code sections is to track valve stroke time as a means of detecting valve degradation.

This type of valve does not lend itself to this tracking technique.

Alternate Testing A maximum stroke time of 2 sec will be specified for each rapid actuating valve.

If the valve strokes in 2 sec or less, it will be considered acceptable and no corrective action will be required. If the valve exceeds 2 sec, it will be considered inoperable and the appropriate corrective action willbe taken.

NMP2-IST-001, Rev. 4 Section I - October 1993 Page 16 of 22

6.6 RELIEF REQUEST GVRR-4 Valve(s)

System Pressure Pump Discharge Check Valves 2CSH*P2 to CSH Header 2CSH*V17, V55 2CSL*P2 to CSL Header 2CSL*V14, V21, and 2RHS*V47, V48 2RHS*P2 to valves 2RHS*V60, V61, V17, and V18 Category Class 2

Testing Requirements Quarterly reverse flow operability testing Basis for Relief These check valves close on the initiation of the associated ECCS system to prevent the diversion ofECCS pump discharge flowvia the pressure pump piping. In each case above, these check valves are in series without any means provided for individual reverse flow verification.

NMPC contacted General Electric who designed the system to determine the need for both check valves.

GE said that only one was needed and that the second was placed there for added reliability. NMPC considered removing the internals from one valve; however, NMPC determined a more conservative approach would be to test the valves as a unit.

The test results of each set will be applied to each valve of the set individually.

Alternate Testing Test each set of series check valves as a unit quarterly for reverse flow closure.

NMP2-IST-001, Rev. 4 Section I - October 1993 Page 17 of 22

Relief Request GVRR-5 Ives Category Code Requirements Code Acceptance Criteria Allpower-operated valves other than rapid acting valves.

A,B Corrective Action, IWV-3417(a)

The acceptance criteria provided by IWV-3417(a) allows an unchecked gradual degradation (stair steps) of valve stroke time rather than fixing an allowable deviation limit from which corrective action is started.

Basis for Relief Basing the trending of stroke times for power-operated valves on the stroke time measured for a valve during its previous test can permit the gradual degradation of valve over an extended period of time without taking any action until the limiting values of full stroke time is exceeded.

To base acceptance criteria on reference values would give adequate assurance to operational readiness and provide a

reasonable alternative to the Code requirements.

In addition, this is a more conservative than the Code requirements and provides an acceptable level ofquality and safety because it willnot permit the gradual increase in valve stroke time without requiring corrective action.

Alternate Acceptance Criteria Reference values shall be determined from the results ofpreservice testing or from the results of inservice testing.

These tests shall be performed under conditions as near as practicable to those expected during subsequent inservice testing.

Reference values shall only be established when the valve is known to be operating acceptably.

If the particular parameter being measured can be significantly influenced by other related conditions, then these conditions shall be analyzed.

Per GL 89-04, position 6, reference values willbe used instead of the previous stroke time to determine acceptability in accordance with IWV-3417(a).

NMP2-IST-001, Rev. 4 Section I - October 1993 Page 18 of 22

7.0 PUMP ANDVALVEP&ID's A listing of all the P&ID's identifying ASME Class 1, 2, and 3 safety-related pumps and valves

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is included in Table 2.3-1.

ID BER TABLE2.3-1 PUMP AND VALVE(IST) PROGRAM P&ID'S 2-A,B,C,D,E 1-A,B,C,D,E,F,J 6-B 11-A,B,C,D,EG,H,J,L,P,Q 13-A,B,C,D,E 19-D,E,F,G,J,L,M 20-E 28-A,B,C 29-A,B,C 30-B,C 31-A,B,C,D,E,F,G 32-A 33-A,B 35-A,B,C,D 36-A 37-A,B EM-38A 38-A,B,C 43-G Symbols Main Steam Mainsteam Safety Valves, Vents, and Drains Feed water Service Water Reac. Bldg. Closed Loop Cooling Water Instrument Air Service Air Breathing Air Reactor Vessel Instrument Reactor Recirc. System CRD Hydraulic System Residual Heat Removal System Low-Pressure Core Spray High-Pressure Core Spray Reactor Core Isolation Cooling Standby Liquid Control Reactor Water Cleanup System Neutron Monitoring System Fuel Pool Cooling and Cleanup Fire Protection Water (MSS)

(SVV)

(FWS)

(SWP)

(CCP)

(IAS)

(SAS)

(AAS)

(ISC)

(RCS)

(RDS)

(RHS)

(CSL)

(CSH)

(ICS)

(SLS)

(WCS)

(NMS)

(SFC)

(FPW)

NMP2-IST-001, Rev. 4 Section I - October 1993 Page 19 of 22

P&ID MBER Y TEM 53-A,B 61-A,B 62-A,B 63-E 67-A 81-A 82-A,B 104-A B,C 105-B Control Bldg. Chilled Water Primary Containment Purge DBA Hydrogen Recombiner Reactor Bldg. Floor Drains Drywell Equipment Drains Cont. Leakage Monitoring Cont. Atmosphere Monitoring Diesel Gen. AirStartup Standby Diesel Gen. Fuel Nitrogen System (HVK)

(CPS)

(HCS)

(DFR)

(DER)

(LMS)

(CMS)

(EGA)

(EGF)

(GSN)

NMP2-IST-001, Rev. 4 Section I - October 1993 Page 20 of 22

8.0 REFERENCES

8.1

8. 2
8. 3
8. 4
8. 5 ASME Boiler and Pressure Vessel Code Section XI, Rules for Inservice Inspection ofNuclear Power Plant Components; 1983 Edition through Summer 1983 Addenda.

10CFR50.55a(g),

Inservice Inspection Requirements, Guidance for Preparing Pump and Valve Testing Program Descriptions and Associated Relief Requests.

Updated Safety Analysis Report (USAR), Nine Mile Point Nuclear Station Unit 2.

Updated Safety Analysis Report (USAR), Sections 1.12-32a, NMP2 for LimihxlVibration on ECCS Systems.

USNRC Letter, Capra to Mangan, "Use of ASME Code Case N-415 for the Inservice Testing (IST) Program at Nine Mile Point Unit 2 (TAC 67172), dated April 14, 1988.

Access

¹09416 1615. NMPC Letter NMP2L 1104, Mangan to USNRC, Untitled, subject regarding use of ASME Code Case N-415, dated January 18, 1988.

Access ¹09104 3800.

8. 6 ANSI/ASME OM-1 1981, "Requirements for Inservice Performance Testing of Nuclear Power Plant Pressure Relief Devices".
8. 7 8.8
8. 9 ANSI/ASME OM-6 1987, "Inservice Testing of Pumps in Light-Water Reactor Power Plants".

Used for guidance only.

ANSI/ASME OM-10 1987, "Inservice Testing of Valves in Light-Water Reactor Power Plants".

Used for guidance only.

Nine Mile Point Unit 2 Technical Specifications.

8.10 8.11 8.12 8.13 8.14 NRC letter dated January 1978, "NRC Staff Guideline for Preparing Pump and Valve Testing Program Descriptions and Associated Relief Requests, pursuant to 10CFR50.55a(g)".

NRC letter dated November 1976, "NRC Staff Guidance for Complying with Certain Provisions of 10CFR50.55a(g) Inservice Inspection Requirements".

NRC Generic Letter 89-04, dated April 3,

1989, "Guidance on Developing Acceptable Inservice Testing Programs" and "Minutes to Public Meeting on Generic Letter 89-04".

Division I Draft Regulatory Guide and Valve Impact Statement (Draft 2), "Identification of Valves for Inclusion in Inservice Testing Programs".

NRC Regulatory Guide 1.26, "Quality Group Classification and Standards for Water-, Steam, and Radioactive-Waste-Containing Components of Nuclear Power Plants".

8.15 NRC Regulatory Guide 1.137, "Fuel Oil Systems for Standby Diesel Generators".

NMP2-IST-001, Rev. 4 Section I - October 1993 Page 21 of 22

8.0 References (Cont'd.)

8.16 NRC IE Information Notice 84-74, "Isolation of Reactor Coolant System from Low-Pressure Systems Outside Containment".

8. 17 NMPC Correspondence

- Prior to Code Case N-415 approved A. P.E. Francisco to it 2 Licensing File, Notes of Telecon with NRC regarding IST Relief Request and Commercial operation of Unit 2, dated March 9, 1988.

Access ¹ 09400 3404.

B.

K.B. Thomas to R. Abbott, Nine MilePoint Unit 2 IST, dated March 10, 1988.

Access

¹09400 3408.

C.

K.B. Thomas to Unit 2 Licensing File, Notes ofTelecon with NRC IST Relief Requests, Dated March 14, 1988.

Access ¹09401 2677.

8.18 NMPC Correspondence

- SRV Testing A.

Egap to Korcz, Pump and Valve Program Revision and SRV Testing, File Code SM-CS90-0293, dated August 15, 1990.

B.

Egap to Distribution, SRV Testing (Korcz response to above memo), File Code NMP73769, dated November 28, 1990.

C.

Egap to Distribution, IST Meeting Minutes, File Code NMP 71597, dated September 26, 1990.

8.19 NMPC Correspondence

- Vacuum Breakers A. Hammelmann/Egap, ANSI/ASMEOM-1 Code Interpretation, File Code SM-ISI90-0053, dated November 27, 1990.

8.20 USNRC Safety Evaluation of the Inservice Testing (IST) Program for Pumps and Valves, Nine Mile Point Unit 2 LTAC No. 63429, dated October 29, 1990.

8.21 USNRC SER for ISC-VRR-1, TAC No. 79781, dated May 28, 1991.

8.22 USNRC SER for EGF-PRR-1, SLS-prr-2, and GPRR-3, TAC No. M85500, dated April 19, 1993 (allows the use of ASME/ANSI OM-6 for pump testing).

NMP2-IST-001, Rev. 4 Section I - October 1993 Page 22 of 22

1.0 PUMP PROGRAM INTRODUCTION Class 1, 2, and 3 pumps which are within the scope of the Inservice Testing Program, as defined in Section II Paragraph 2.1, and which are not exempt per Section IIParagraph 2.1.1, shall be tested in accordance with the ASME/ANSI OM-6 Code Editions stated in Section I Paragraph 1.0. Tables listing the pumps, including all applicable testing requirements and frequencies, are contained in this Section.

Pump table descriptions are found in this Section.

When the pump testing requirements of the applicable Code cannot be met for any reason, Relief Requests are provided at the end of this Section.

NMP2-IST-001, Rev. 4 Section II - October 1993 Page 1 of 10

2.0 PUMP INSERVICE TESTING SCOPE

2.1 INTRODUCTION

The scope of the Pump IST Program includes certain Class 1, 2, and 3 safety-related centrifugal and positive displacement type pumps that are provided with an emergency power source and that are not exempt by Paragraph 2.1.1, and which function to:

shut down the reactor; and/or mitigate the consequences of an accident.

These safety-related pumps are found within the ASME Class 1, 2, and 3

boundaries.

The pumps within this scope are listed in Section II.

2.1.1 PUMP EXCLUSIONS IDENTIFIEDIN OM-6, 1.2 NOTE:

The term "Exclusions" is used in OM-6, 1.2 and, for the purpose of this Program Plan, is synonymous with "Exemptions".

A.

drivers of pumps, with the exception that the driver and pump form an

. integral unit and the pump bearings are in the driver; B.

pumps supplied with emergency power solely for operating convenience.

NMP2-IST-001, Rev. 4 Section II - October 1993 Page 2 of 10

3.0 PUMP TEST TABLE-NOMENCLATURE PUMP PROGRAM TABLEDESCRIPTION o

Pump Table Summary The ASME Class 1, 2, and 3 Pump IST Program Table (Section Il) contains an alpha-numeric listing of all the safety-related pumps included in the NMP2 Pump ASME/ANSE OM-6 IST Program.

The data

. contained in these Tables identifies the inservice test parameters to be

measured, the applicable Relief Requests, and any applicable remarks.

A column for testing frequency was not included since all the required pump testing willbe performed QUARTERLY.

o Pump Program Table Format The Pump IST Program Tables have been organized to provide the following information:

Note; The numbers in parentheses correspond to those found on the following sample pump (IST) Program Table.

(1)

PUMP ID NUMBER: The pump identification number; (2)

SYS ID: 3-digit abbreviation for the pump's specific system; (3)

CODE CLASS: ASME Code Class; (4)

P&ID and COORD.: Piping and Instrumentation Drawing where pump is located and location coordinates of the pump on the P&ID; (5)

NOTE: Applicable notes (eg., Technical Specification references, etc.) in numerical format and explained in detail on the last page of the Pump Table; (6)

PARAMETERS:

This column lists the applicable testing parameters that willbe measured.

The parameters listed are those required by the Code unless alternate testing is provided by Relief Request.

The following is a description of applicable parameters:

(6.1)

SPEED - pump speed (only required for variable speed pumps);

NMP2-IST-001, Rev. 4 Section II - October 1993 Page 3 of 10

3.0 Pump Test Table - Nomenclature (Cont'd.)

(6.2)

Discharge Pressure for positive displacement pumps; (6.3)

DIFF. PRESS - pump differential or discharge pressure; (6.4)

FLOW - pump flowrate; (6.5)

VIB. - pump vibration velocity; (7)

REMARKS: Any additional pertinent information NMP2-IST-001, Rev. 4 Section II - October 1993 Page 4 of 10

3.1 SAMPLE PUMP /ST) PROGRAM TABLE NMP2-IST-001 DATE 'X/XX/XX PUMP SYSTEM ASMB P&IDAND NOTE SPEED DISCHAROB DIFF FLOW VIBRATION REMARKS NO.

CLASS COORD.

PRESSURE PRESSURE (3)

(4)

(6.1)

(6 '2)

(6.3)

(6.4)

(6.S)

NMP2-IST-001, Rev. 4 Section II-October 1993 Page 5 of 10

NMP2-IST-001, R.

4 FIRST TEN-YEAR INTERVAL NINE MILE POINT NUCLEAR POWER STATION UNIT 2 DATE: 10/25/93 PAGE:

6 of 10 PUMP ID SYS ASME P&ID/

ID CLAS COORD NOTE SPEED DISCH.

DELTA PRESS.

PRESS.

FLOW VIBRATION REMARKS "

2CSH*P1 CSH 2

33B H-7

'NOTE 1 N/R Y

2CSL*P1 2EGF*P1A CSL 2

EGF 3

32A B-8 104C E-6 NOTE 1 N/R Y

NOTE 1 N/R Y

2EGF*P1B EGF 3

104B E-8 NOTE 1 N/R Y

2EGF*PlC 2EGF*P1D 2EGF*P2A EGF 3

EGF 3

EGF 3

104C C-6 104B C-8 104B E-4 NOTE 1 N/R Y

NOTE 1 N/R Y

NOTE 1 N/R Y

2EGF*P2B EGF 3

104B C-4 NOTE 1 N/R Y

2HVK*P1A 2HVK*P1B 53A C-6 53A C-10 NOTE 1 N/R Y

NOTE 1 N/R Y

2ICS*P1 ICS 2

35D G-9 N/R Y

2RHS*P1A RHS 2

31F D-7 NOTE 1 N/R Y

NMP2-IST-001, R.

4 FIRST TEN-YEAR INTERVAL NINE MILE POINT NUCLEAR POWER STATION UNIT 2 DATE: 10/25/93 PAGE:

7 of 10 PUMP ID 2RHS*P1B SYS ID ASME P&ID/

CLAS COORD NOTE 31E E-2 SPEED NOTE 1 DISCH.

DELTA PRESS.

PRESS.

N/R Y

FLOW VIBRATION REMARKS 2RHS*P1C 31G D-6 NOTE 1 N/R Y

2SFC*P1A 2SFC*P1B 2SLS*P1A SFC SFC SLS 38B E-3 38A E-10 36A H-5 NOTE 1 NOTE 1 NOTE 1 N/R Y

N/R Y

SLS-PRR-1 2SLS*P1B SLS 36A H-9 NOTE 1 SLS-PRR-1 2SWP*P1A SWP 11B C-9 NOTE 1 N/R Y

2SWP*P1B SWP 11A H-5 NOTE 1 N/R Y

2SWP*pjc SWP 11A H-10 NOTE 1 N/R Y

2SWP*P1D SWP 11A D-5 NOTE 1 N/R Y

2SWP*P1E 2SWP*P1F SWP SWP 11B H-9 11A D-10 NOTE 1 NOTE 1 N/R Y

N/R Y

NMP2-IST-001, R.

4 FIRST TEN-YEAR INTERVAL NINE MILE POINT NUCLEAR POWER STATION UNIT 2 DATE 10/25/93 PAGE:

8 of 10 PUMP ID SYS ID ASME CLAS P&ID/

COORD NOTE SPEED DISCH.

DELTA PRESS.

PRESS.

FLOW VIBRATION REMt&KS 2SWP*P2A SWP 11J J-6 NOTE 1 N/R Y

2SWP*P2B SWP 11J J-6 NOTE 1 N/R Y

PUMP TEST TABLENOYES In the Pump Test Table, the parameters to be measured or observed and the test frequency are identified. Footnote 1 refers to amplifications, deviations, and exceptions to the Code requirements and is further discussed below:

(1)

For pumps with constant speed drive, the speed is not measured since the test will be performed at nominal motor nameplate

speed, as required by OM-6.

NMP2-IST-001, Rev. 4 Section II - October 1993 Page 9 of 10

System Pump(s) 4.0 RELIEF REQUEST NO. SLS-PRR-1 Standby Liquid Control 2SLS*P1A, P1B Class Function Inject borated solution into the reactor for emergency shutdown.

Testing Requirements In accordance with IWP-4600, flow rate shall be measured using a rate or quantity gravity meter installed in the pump test circuit.

The meter may be in any class that provides an overall readout repeatability of J 2% of full scale.

Basis for Relief These pumps'est circuits are not provided with in-place flow meters.

Flow measurement for these pumps willbe accomplished by use of a clamp on ultrasonic flow meter with a full-scale repeatable accuracy of J 3%.

The J 3% accuracy exceeds the allowable instrument accuracy contained in Table IWP-4110-1;

however, this small reduction in accuracy will not provide a significant reduction in the ability to determine pump operability.

NMPC will continue to evaluate industry development of more accurate instrumentation.

Alternate Testing Flow rate willbe measured using a clamp on ultrasonic flow meter with a repeatable full-scall accuracy of J 3%.

NMP2-IST-001, Rev. 4 Section II - October 1993 Page 10 of 10

0

1.0 VALVEPROGRAM INTRODUCHON Class 1, 2, and 3 valves which are within the scope of the Inservice Testing Program, as defined in Section III, Paragraph 2.1, and which are not exempt per Section III,Paragraph 2.1.3, shall be tested in accordance with the Section XI Code Editions stated in Section I, Paragraph 1.0.

Valve Table descriptions and the Tables listing the valves, including all applicable testing requirements and frequencies, are contained in this Section.

When valve testing must be deferred to cold shutdown, cold shutdown test justifications are provided at the end of each respective systems Table in this Section.

When the valve testing requirements of the applicable Code cannot be met for any reason, Relief Requests are provided at the end of each respective systems Table in this Section.

NMP2-IST-001, Rev. 4 Section III-October 1993 PAGE 1 of 10

2.0 VALVEINSERVICE TESTING SCOPE INTRODUCTION The scope of the valve IST program includes certain ASME Class 1, 2, and 3 safety-related valves that are not exempt by Paragraph 2.1.3 and which function is to:

shut down the reactor to a cold shutdown condition; and/or mitigate the consequences of an accident.

These safety-related valves are found within the ASME Class 1, 2, and 3

boundaries.

The valves within this scope are listed in Section III.

2.1.1 CODE REQUIRED POSITIONS This Section indicates the positions used to clarify Code requirements as they apply for the formulation and the implementation of this program:

o Check Valve Full/Partial Stroke In most cases, full design flow through a check valve requires less than full mechanical valve movement.

As used in this program, with the exception of testable check valves, the term "full stroke" refers to the ability of the valve to pass design flow and not the full mechanical stroking.

Forward flow stroke operability testing willbe by any method that verifies the valve is capable of passing design flow. Any test that verifies less than full design flow capability is considered as a partial stroke test.

o Valve Position Indicator Verification Verification of proper indication of remote position indication will normally be accomplished by locally observing the position of the valve and comparing it with the remote indication.

However, certain valves, such as solenoid-operated and excess flow check valves, are not equipped with a local means to verify position; therefore, position willbe verified by the observation of system parameters, such as flow or pressure, NMP2-IST-001, Rev. 4 Section III-October 1993 PAGE 2 of 10

2.0 Valve Inservice Testing Scope (Cont'd.)

during valve cycling, in conjunction with valve light indicators (unless the valve is of a design that requires a positive change in disk position to effect a change in the indicator lights).

2.1.3 VALVEEXEMPTIONS IDENTIFIEDIN IWV-1200 A.

Maintenance Valves - Valves which are used only to isolate components to perform maintenance, including relief valves which provide overpressure protection for a component that is isolated only for maintenance; B.

Operating Convenience Valves - Valves used only for operating convenience, such as manual vent, drain, instrument, and test valves; C.

System Control Valves - Valves such as pressure-regulating, flow control, and manual throttle valves, that do not have an analyzed fail safe function; D.

Valves in External Control Protection Systems systems responsible for sensing plant conditions and providing signals for valve operation.

2.1.4 ALTERATIONS TO CODE REQUIREMENTS o

Increased Testing Frequencies The testing frequencies for certain Category C and D valves have been increased in compliance with Technical Specification or USAR commitments.

The specific frequency designations and the associated references are contained in the test frequency section of Valve Table.

o Cold Shutdown Test Justification Discussion The Code permits the delay of valve testing that is impractical during operation to be performed during cold shutdown.

Justification for this delay of testing is provided by the Cold Shutdown Test Justifications located following each systems valve Table.

Each cold shutdown test justification is formatted to contain the following information:

NMP2-IST-001, Rev. 4 Section III-October 1993 PAGE 3 of 10

2.0 Valve Inservice Testing Scope (Cont'd.)

cold shutdown test justification number; system; valve identification number; category; function; quarterly test requirements; cold shutdown test justification; quarterly partial stroke testing (as applicable);

cold shutdown testing.

The cold shutdown test justifications are formatted for numerical filingas follows:

XXX-CS-Y where:

XXX CS Y

system designation; valve cold shutdown test justification; sequential number within any system's Relief Request

number, USAR or Tech.

Spec. reference, is provided in this space.

OM-1-1981 APPLICABILITYSTATEMENTS NMP2 IST Program Plan adopts ASMEXICode Case N415 which states that the requirements for acceptance

testing, replacement, repair and maintenance, periodic
testing, and test frequency contained in ANSI/ASME OM-1-1981 may be used as alternate requirements for preservice tests, replacement, repair and maintenance, inservice tests, and test frequency for safety valves, relief valves (including vacuum relief valves),

and rupture disks (non-reclosing pressure relief devices) of Subsection IWV of Section XI, Division 1.

o Use of ASME Code Case N-415 was approved for use at NMP2 by the NRC in their letter dated April 14, 1988, R. Capra to C.V.

Mangan, entitled "Use of ASME Code Case N-415 for the Inservice Testing Program at Nine Mile Point Unit 2 (TAC 67172)".

See Reference 8.16.

NMP2-IST-001, Rev. 4 Section III-October 1993 PAGE 4 of 10

2.0 Valve Inservice Testing Scope (Cont'd.)

Before the NRC approval of Code Case N-415, each component received a base line test in accordance with the IST Program Plan prior to commercial operation, as required by ASME Section XI, IWV-3100. Implementation of OM-1 commenced at commercial operation April 1988.

See References listed in 8.17.

Note:

This is consistent with ASME Section XI, IWA-2420; inspection intervals begin at "initialstart ofpower unit commercial operation".

'n October

1990, a review of the Safety Relief Valve testing indicated that Relief Request MSS-VRR-1 was no longer required.

Other changes to the IST Program Plan are discussed in References 8.10.

In November 1990, discussions with an OM-1-1981 representative indicated that only vacuum breakers whose function is to protect the containment are to be tested in accordance with OM-1-1981, Section 1.3.4.3 (3.3.2.3 and 3.4.2.3). Allother vacuum breakers are to be tested as pressure relief devices and tested in accordance with OM-1-1981, Section 1.3.4.1 (3.3.2.1 and 3.4.2.1).

This necessitated the addition of ISC-VRR-1.

See Reference 8.19,Section I.

o Relief and Vacuum Breakers not meeting acceptance criteria ASME Class 1,

2 and 3

pressure relief devices tested in accordance with ANSI/ASMIOM-1, 1981 code which exceed the set pressure acceptance criteria by J 3% or greater, the following requirements shall be met:

ao Additional valves shall be set pressure tested on the basis of two additional valves to be tested for each valve failure up to the total number of valves of the same type and manufacturer.

If any of the additional valves tested exceeds the stamped set pressure criteria by + 3% or greater, then all valves of the same type and manufacturer shall be tested.

NMP2-IST-001, Rev. 4 Section III-October 1993 PAGE 5 of 10

2.0 Valve Inservice Testing Scope (Cont'd.)

b.

The cause of failure shall be determined and evaluated.

c.

Valve shall be repaired or replaced and retested before the valve returned to service.

o When installing a partial complement of pretested ASME Class 1, 2 and 3 valves to replace those valves that had been in service in accordance with the applicable test schedule, shall be pressure test the valves which were removed within three (3) months of removal from the system or before resumption of electric power generation, whichever is longer.

NMP2-IST-001, Rev. 4 Section III-October 1993 PAGE 6 of 10

3.0 VALVETEST TABLE-NOMENCLATURE VALVEPROGRAM TABLEDESCRIPTION The Valve Program Tables (Section III)provide a tabulation of ASME Class 1, 2, and 3 safety-related valves included in the NMP2 Valve IST Program.

The Tables are arranged by system and the valves in each system are listed in alpha-numeric sequence.

VALVEPROGRAM TABLEFORMAT NOTE:

The numbers in parentheses correspond to those found on the sample valve IST Program Table, found on the next page.

(1)

SYSTEM:

the system that the particular Table applies to; (2)

VALVENUMBER: the valve identification mark number; (3)

CLASS: ASME Code Class; (4)

P&ID: piping and instrumentation drawing where the valve is located; (5)

COORD: location coordinates of the valve on the P&ID; (6)

VCAT: valve category, as identified by IWV-2200 (7)

SIZE: valve size in inches; (8)

VALVETYPE: valve design type; (9)

ACTUATTYPE: type of actuator used to change position of valve; (10)

VALVEPOSITIONS:

(A)

NRM - position during normal plant operation; (B)

SAF - position to fulfillsafety function; (C)

FAL-position valve fails to on loss of actuator power; NMP2-IST-001, Rev. 4 Section III-October 1993 PAGE 7 of 10

3.0 Valve Test Table - Nomenclature (Cont'd.)

(11)

ASME Section XITEST/FREQ/DIR: The testing requirement, frequency the test should be performed and, in parentheses, either the direction(s) stroke time should be measured for power-operated valves, or the direction(s) the valve should be exercised for check valves.

This column identified ASME Section XI Code requirements.

The IST Program Plan commitment column willreflect the same test requirements unless alternate testing is provided by relief request or cold shutdown test justification.

Format for the field is as follows:

Test Code - Frequency Code (stroke time or exercise direction) eg.,:

FE-Q(F&R)

=

Full stroke exercise quarterly in the forward and reverse flow direction; ST-CS(O)

=

Measure valve stroke time in the open direction during cold shutdowns; FE-R(R)

=

Full stroke exercise during a

refueling outage in the reverse direction; (12)

RELIEF REQ./C.S. JUST.: Indicates whether or not there is a Relief Request, or Cold Shutdown Test Justification applicable.

This column identifies the specific Relief Request or Cold Shutdown Test Justification.

(13)

IST PROGRAM PLAN COMMITMENT-TEST/FREQ/DIR: This column reflects the actual testing to be performed as required by ASME Section XIor as written relief was requested.

This column also reflects testing as required by Cold Shutdown Justifications.

This column reflects the total program commitment for the valve.

(14)

REMARKS:

Any additional pertinent information, such as Technical Specification note references are provided in this space.

VALVEPROGRAM TABLE CODES A quick reference table providing definitions for the codes (abbreviations) used on the Valve Program Tables is provided following the Valve Table sample.

NMP2-IST-001, Rev. 4 Section III-October 1993 PAGE 8 of 10

SAMPLE VALVE/ST) PROGRAM TABLE FIRST TEN-YEAR INTERVAL NINE MILEPOINT NUCLEAR POWER STATION - UNIT 2 NMP2-IST-001 DATE: XX/XX/XX SYSTEM: (I)

IST POM. PLAN VALVE ASME P&ID VALVE SIZE ACTU POSITIONS ASMBSBCIIONXI REL REQ.

COMMITMENT NO.

CLASS COORD.

(CAT.)

&TYPE TYPE NRM SAF FAL TEST/FREQ/DIR C.S. JUST.

TEST/FREQ/DIR REMARKS NMP2-IST-001, Rev. 4 Section III-October 1993 Page 9 of 10

VALVETABLE CODES CODE DEFINITION VALVETYPE CODB DEFINITION CODE ACI1JATORTYPE DEFINITION AOV Angle Valve Needle EHA EcctrntHydraulic Actuator BFV BLV DIV Diaphragm POV PRV Plug Regulating Rupture Disc Relief AOA HOA AirOperator Explosive Operator Hydraulic Operator Manual Operator FCV Plow Control OTV 0ate OLV Olobe SKV TCV MOA Motor Operator NOA Nitrogen Operator SEA Self-Actuated CODE VALVEPOSITIONS DESCRIFIION CODB 0

Open C

Closed TEST DIREC11ON DEFINITION AI hhotticd - Dctcnnincd by System Parameters, i.c.,

Check Valve As is DI PE U

PI RT BD AO DEFINITION Disassembly and Inspection Bxphwive Valve pcr IWV-3610 Full Stroke Exercise pcr IWV-3412 or 3522 Partial Stroke Exercise Fail Safe pcr IWV-341$

Leak Test pcr IOCFR50 AppI Leak Test pcr Section XI (Prcssure isoLtioa Only)

Remote Position Indication Test pcr IWV-3300 Valve Sct Pressure Test pcr OM-I Rupture Disc Replacement pcr OM-I Stroke Time per IWV-3413 Visual Exanunation pcr OM-I As Found Tightness Leakage Test pcr OM.I VcnTication of Bahnce Dcviccs pcr OM-I AuxiliaryActuating Dcviccs pcr OM-I Pl p4 DEFINITION Rcfwhng Evcty Rcfwiing and When Conditions Spccificd in Relief Request E Every Other Rcfwling Outage 50% Each Rcfuchng Outage pcr FSAR 5.2.2.10 and MSS Note 3b Every 10 Years pcr OM-I Every 5 Years Replacement pcr OM-I 25% Evcty 2 Years, But No Valve WillExceed Onco Every 5 Yca pcr OM-I 50% Bach Rcfwling Outage pcr T.S. 4.13.d. I I Squib Each Rcfwling Outage pcr T.S. 4.633.b Every 2 Years NMP2-IST-001, Rev. 4 Section III-October 1993 Page 10 of 10

REPORT

. 10/22/93 SYSTEM:

BREATHING AIR FIRST TEN Y TERVAL VALVES NINE MILE POINT NUCLEAR POWER STATION UNIT 2 NMP2-IST-001 Rev.

4 VALVE NO.

AS P&ID ME CL COOR VALVE CAT.

SIZE (IN)

& ACTU TYPE TYPE POSITION NRM SAF FAL IST PROG.PLN ASME XI RELIEF REQ COMMITMENT TEST/FREQ/DIR C.S.JUST.

TEST/FREQ/DIR REMARKS 2AAS*HCV134 2

20E D-3 2.00 GLV LC LC LJ-R PI-T GVRR-1 LJ-R PI-T 2AAS*HCV135 2

20E C-7 F 00 GLV LC LC LJ-R PI-T GVRR-1 LJ-R PI-T 2AAS*HCV136 2

20E D-3 2.00 GLV LC LC LJ-R PI-T GVRR-1 LJ-R PI-T 2AAS*HCV137 2

20E E-7 2.00 GLV LC LC LJ-R PI-T GVRR-1 LJ-R PI-T III AAS 1

REPORT

.,10/22/93 FIRST TEN Y TERVAL VALVES NINE MILE POINT NUCLEAR POWER STATION UNIT 2 SYSTEM:

REACTOR BLDG.

CLOSED LOOP COOLING WATER NMP2-IST-001 Rev.

4 VALVE NO.

AS ME CL P&ID SIZE VALVE (IN)

COOR CAT.

TYPE POSITION ACTU TYPE NRM SAF FAL IST PROG.PLN ASME XI RELIEF REQ COMMITMENT TEST/FREQ/DIR C.S.JUST.

TEST/FREQ/DIR REMARKS 2CCP*AOV37A 13E J-2 1.50 GTV AOA 0

C C

FE-Q ST-Q(C)

FS-Q PI-T FE-Q ST-Q(C)

FS-Q PI-T 2CCP*AOV37B 13E D-8 2.00 GTV AOA 0

C C

FE-Q ST-Q (C)

FS-Q PI-T FE-Q ST-Q(C)

FS-Q PI-T 2CCP*AOV38A 13E J-4

l. 50 GTV AOA 0

C C

FE-Q ST-Q(C)

FS-Q PI-T FE-Q ST-Q(C)

FS-Q PI-T 2CCP*AOV38B 13E D-10 2.00 GTV AOA 0

C C

FE-Q ST-Q (C)

FS-Q PI-T FE-Q ST-Q(C)

FS-Q PI-T 2CCP*MOV122 13C J-6 8.00 GTV MOA 0

C AI FE-Q ST-Q(C)

PI-T LJ-R GVRR-1 CCP-CS-2 FE-CS ST-CS(C)

PI-T LJ-R III CCP 1

REPORT D

. 10/22/93 FIRST TEN Y TERVAL VALVES NINE MILE POINT NUCLEAR POWER STATION UNIT 2 SYSTEM:

REACTOR BLDG.

CLOSED LOOP COOLING WATER NMP2-IST-001 Rev.

4 VALVE NO.

AS ME CL P&ID SIZE VALVE (IN)

COOR CAT.

TYPE POSITION ACTU TYPE NRM SAF FAL ASME XI RELIEF REQ TEST/FREQ/DIR C.S.JUST.

IST PROG.PLN COMMITMENT TEST/FREQ/DIR REMAINS 2CCP*MOV124 13C I-6 8.00 GTV MOA 0

C AI FE-Q ST-Q(C)

PI-T LJ-R GVRR-1 CCP-CS-2 FE-CS ST-CS(C)

PI-T LJ-R 2CCP*MOV14A 13E G-7 12.00 GTV MOA OC C

AI FE-Q ST-Q(C)

PI-T FE-Q ST-Q(C)

PI-T 2CCP*MOV14B 13E H-10 12.00 GTV MOA OC C

AI FE-Q ST-Q (C)

PI-T FE-Q ST-Q(C)

PI-T 2CCP*MOV15A 13D K-6 4.00 GTV MOA 0

C AI FE-Q ST-Q(C)

PI-T LJ-R GVRR-1 CCP-CS-1 FE-CS ST-CS(C)

PI-T LJ-R 2CCP*MOV15B 13A I-7 F 00 GTV MOA 0

C AI FE-Q ST-Q(C)

PI-T LJ-R GVRR-1 CCP-CS-1 FE-CS ST-CS(C)

PI-T LJ-R III CCP 2

REPORT

10/22/93 FIRST TEN Y TERVAL VALVES NINE MILE POINT NUCLEAR POWER STATION UNIT 2 SYSTEM:

REACTOR BLDG.

CLOSED LOOP COOLING WATER NMP2-IST-001 Rev.

4 VALVE NO.

AS P&ID ME VALVE CL COOR CAT.

SIZE (IN)

TYPE POSITION ACTU TYPE NRM SAF FAL ASME XI RELIEF REQ TEST/FREQ/DIR C.S.JUST.

IST PROG.PLN COMMITMENT TEST/FREQ/DIR REMARKS 2CCP*MOV16A 13D K-7 F 00 GTV MOA 0

C AI FE-Q ST-Q(C)

PI-T LJ-R GVRR-1 CCP-CS-1 FE-CS ST-CS(C)

PI-T LJ-R 2CCP*MOV16B 13A G-7 F 00 GTV MOA 0

C AI FE-Q ST-Q(C)

PI-T LJ-R GVRR-1 CCP-CS-1 FE-CS ST-CS(C)

PI-T LJ-R 2CCP*MOV17A 13D C-7

4. 00 GTV MOA 0

C AI FE-Q ST-Q(C)

PI-T LJ-R GVRR-1 CCP-CS-1 FE-CS ST-CS(C)

PI-T LJ-R 2CCP*MOV17B 13B E-7 F 00 GTV MOA 0

C AI FE-Q ST-Q(C)

PI-T LJ-R GVRR-1 CCP-CS-1 FE-CS ST-CS(C)

PI-T LJ-R 2CCP*MOV18A 13E G-5 12 ~ 00 GTV MOA OC C

AI FE-Q ST-Q(C)

PI-T FE-Q ST-Q(C)

PI-T III CCP 3

REPORT 10/22/93 FIRST TEN Y TERVAL VALVES NINE MILE POINT NUCLEAR POWER STATION UNIT 2 SYSTEM:

REACTOR BLDG.

CLOSED LOOP COOLING WATER NMP2-IST-001 Rev.

4 VALVE NO.

AS P&ID ME VALVE CL COOR CAT.

SIZE (IN)

& ACTU TYPE TYPE POSITION NRM SAF FAL ASME XI RELIEF REQ TEST/FREQ/DIR C.S.JUST.

IST PROG.PLN COMMITMENT TEST/FREQ/DIR REMARKS 2CCP*MOV18B 13E I-8 12.00 GTV MOA OC C

AI FE-Q ST-Q(C)

PI-T FE-Q ST-Q(C)

PI-T 2CCP*MOV265 13C B-6 8.00 GTV MOA 0

C AI FE-Q ST-Q(C)

PI-T LZ-R GVRR-1 CCP-CS-2 FE-CS ST-CS(C)

PI-T LZ-R 2CCP*MOV273 13C C-6 8.00 GTV MOA 0

C AI FE-Q ST-Q(C)

PI-T LJ-R GVRR-1 CCP-CS-2 FE-CS ST-CS(C)

PI-T LZ-R 2CCP*MOV94A 13D C-7 4.00 GTV MOA 0

C AI FE-Q ST-Q(C)

PI-T LJ-R GVRR-1 CCP-CS-1 FE-CS ST-CS(C)

PI-T LJ-R 2CCP*MOV94B 13B E-8 4.00 GTV MOA 0

C AI FE-Q ST-Q(C)

PI-T LJ-R GVRR-1 CCP-CS-1 FE-CS ST-CS(C)

PI-T LZ-R III CCP 4

REPORT

. 10/22/93 FIRST TEN Y TERVAL VALVES NINE MILE POINT NUCLEAR POWER STATION UNIT 2 SYSTEM:

REACTOR BLDG.

CLOSED LOOP COOLING WATER NMP2-IST-001 Rev.

4 VALVE NO.

AS P&ID ME CL COOR VALVE CAT.

SIZE (IN)

& ACTU TYPE TYPE POSITION NRM SAF FAL IST PROG.PLN ASME XI RELIEF REQ COMMITMENT TEST/FREQ/DIR C.S.JUST.

TEST/FREQ/DIR RE2GQKS 2CCP*RV170 2

13B F~7 AC 0.75 REV C

0 AI RT-P2 VT-P2 LA-P2 LJ-R GVRR-1 RT-P2 VT-P2 LA-P2 LJ-R 2CCP*RV171 2

13A H-6 AC 0.75 REV C

0 AI RT-P2 VT-P2 LA-P2 LJ-R BD-P2 GVRR-1 RT-P2 VT-P2 LA-P2 LJ-R BD-P2 2CCP*RV64A 3

13E H-5 2.00 REV C

0 AI RT-P2 VT-P2 LA-P2 RT-P2 VT-P2 LA-P2 2CCP*RV64B 3

13E I-9 2.00 REV C

0 AI RT-P2 VT-P2 LA-P2 RT-P2 VT-P2 LA-P2 III CCP 5

COLD SHVIDOWNTEST JUSTIFICATION CCP-CS-1 System Valve(s)

Reactor Building Closed Loop Cooling Water 2CCP*MOV15A,B 2CCP*MOV16A,B 2CCP*MOV17A,B 2CCP~MOV94A,B Category A

(2CCP*MOV15A, 15B, 16A, 16B, 17A, 17B, 94A, 94B)

Class 2

(2CCP~MOV15A, 15B, 16A, 16B, 17A, 17B, 94A, 94B)

Function Inlet and outlet primary containment isolation valves to recirculation pump coolers and CCP return line block

valves, Quarterly Test Requirements

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Cold Shutdown Test Justification Exercise and stroke time.

Testing during operation would cause a loss of CCP flow to the recirculation pump seal

coolers, motor bearing coolers, and motor winding coolers.

The failure of any one of these valves to reopen after stroking would result in a complete loss of cooling to the associated recirculation pump, which could cause extensive damage to the pump.

Furthermore, loss of cooling requires a plant shutdown.

Quarterly Partial Stroke Testing The operating circuitry of these valves only permits full stroke operation.

Cold Shutdown Testing Exercise and stroke time.

NMP2-IST-001, Rev. 4 III-CCP-6 of 7

COLD SHVI'DOWNTEST JUSTIFICATION CCP-CS-2

"<ff System Valve(s)

Reactor Building Closed Loop Cooling Water 2CCP~MOV122 2CCP*MOV124 2CCP*MOV265 2CCP*MOV273 Category Class Function CCP supply and return line primary containment isolation valves to drywell unit coolers Quarterly Test Requirements Exercise and stroke time Cold Shutdown Test

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Justification The drywell coolers are required, during normal plant operation, to maintain the average drywell temperature below 150'F.

Cycling of these valves will interrupt cooling water flow to the drywell coolers.

The failure of any one of these valves to reopen after testing would result in a complete loss of cooling water to the drywell coolers.

This loss would lead to a

high drywell temperature condition and required plant shutdown.

Furthermore, the loss of drywell cooling could result in equipment damage and/or a high drywell pressure and subsequent reactor trip.

Quarterly Partial Stroke Testing The operating circuitry of these valves only permits full stroke operation.

Cold Shutdown Testing Exercise and stroke time NMP2-IST-001, Rev. 4 III-CCP-7 of 7

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