ML20246E017

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Change 1 to Rev 6 of Pump & Valve Inservice Test Plan
ML20246E017
Person / Time
Site: Waterford Entergy icon.png
Issue date: 08/04/1989
From:
LOUISIANA POWER & LIGHT CO.
To:
Shared Package
ML20246E004 List:
References
PROC-890804, NUDOCS 8908280366
Download: ML20246E017 (191)


Text

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  • a S u PORCJa:D :L^.; - SiG REVIEW AND APPROVAL SHEET REVIEW OF:

I2T,L Pump and Valve Inservice.

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Test Plan {clici E c'; u c e '. 3.1. '. 3 10EL==

) PORC - S/C D (Chance 1)

(Rev. 6)

The PORC or PORC S/C has reviewed this item and determined that a Safety /

Couaitment Review was performed, that a Safety Evaluation was performed (if applicable), that an unreviewed safety question does not exist and that nuclear safety is/was not adversely affected.

PORC O N ED FOR APPRO M MEMBER SIGNATURE DATE MEMBER YES NO Maintenance Supe r i n L eu<len t

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D -D Item No. b.E Date: 3 M l

This item is recommended for approval? XIYES O NO This item requires SRC/NRC review prior tu implementation? O YES 4 NO If yes, ensure documentation supporting review is attached.

PLANT MANAGER-MUCLEAR APPROVAL Comments:

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WATERFORD 3 NUCLEAR SES Pump and Valve Inservice Test Plan Revision 6 Change 1 Change 1 to Revision 6 of the Pump and Valve Test Plan contains the 6 items previously addressed in Change 1 to Revision 5 submitted to the NRC June 19, 1989 in addition to the following:

1.

Relief Request 3.1.43 was deleted.

CCW valves to Containment Fan Coolers are tested quarterly IAW the Code. No relief is necessary.

2.

Revision 6 included 3 new " Pump" relief requests, (2.1.4, 2.1.5, 2.1 6). Per discussions during meeting with NRC at Waterford 3 on May 9, 1989, Relief Request 2.1.4 was dropped.

Relief Request 2.1.6 was renumbered 2.1.4.

Approval is requested for Relief Requests 2.1.4 l

and 2.1.5 in Revision 6 Change 1.

3.

Revision 6 included 2 new " Valve" relief requests, (3.1.55 and 3.1.56). Per discussions during meeting with NRC at Waterford 3 on May 9, 1989 and guidance given in Generic Letter 89-04, Relief Request 3.1.56 was changed and Revision 6 Relief Request 3.1.55 was incorporated into Relief Request 3.1.56. This relief l

request meets all of the approval requirements of I

Generic Letter 89-04.

l (NOTE - Change 1 to Revision 5 uses Relief Request number 3.1.55 for Type C Testing.)

4.

All previously approved relief requests have been annotated.

5.

A new paragraph was added to section 5.3 concerning adminis'trative stroke time limits.

l Tables were updated to reflect changes in relief requests. Notes have been added to the Valve Table (Attachment 6.5).

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4 1

PUMP AND VALVE INSERVICE TEST PIAN Revisirir 6 Chance 1 l

10CFR50.59 Pgfety Evaluation The Inservice Testing of safety-related pumps and valves is required by Technical Specification 4.0.5 and referenced in Section 3.9.6 of the FSAR.

Testing is performed in accordance with ASME Section XI.with deviations as allowed by 10CFR50.55a(g).

This change incorporates the same changes contained in Revision 5 Change 1.

The Safety Evaluation for Revision 5 Change 1 was reviewed and is still valid.

Editorial' changes do not' require an evaluation.

The 2 items that require evaluation are the deletion of Relief Request 3.1.43, and the revising of Relief Request 3.1.56.

1.

Relief Reauest 3.1.43 (Deleted). This relief request was submitted when Technical Specifications required all Containment Fan Coolers (CFC) to be operable in modes 1 - 4. Amendment 39 to Tech-specs no-longer requires all CFCs'to be operable, and thus the basis for this relief request is no longer applicable.

The CCW valves to the Containment Fan Coolers are tested quarterly in accordance with ASME Section XI.

2.

Relief Reauest 3.1.56 (Revised). This relief request meets the requirements for NRC approval per Generic Letter 89-04.

The area of code deviation concerns increased frequency testing criteria. By establishing allowable time limits, a more conservative approach is utilized to increase the monitoring frequency of potentially degraded valves.

Attached are 10CFR50.59 Safety Evaluation Checklists for the above mentioned items.

==

Conclusion:==

Revision 6 Change 1 to the Pump and Valve Inservice Test Plan contains no unresolved safety questions as defined in 10CFR50.59.

1 DOCUENT REVIEW CofftfENTS Page I

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i DOCUENT NO.

NA REVISION NO. S DRAFT NO.

A/A TITLE: LfIL hv-P 4 /4t,e Tw Atliee Test Pt.4.i c A a,,, c,

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2. Comments Resolved'By:

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Date Author Date (1 m b 9 Tr *)

3. Resolution of Comments Accepted By:

Reviewer (Signatuke)

Date Reviewer Date c

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UNT-001E' - S tAANAGEldENT Revision 11.7 (1 of 1)

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10 CFR PART 50.59 SAFETT EVALUATION CHECKLIST PROCEDURE NO. N/A YITLE LP&L Pump and Valve Inservice Test Plan CHANGE NO.

1 Relief Request 3.1.43 (Deleted) i REVISION No.

6 1

DELETION? YES NO x 1.

Will the probability of occurrence of an accident previously calculated in the FSAR be increased?

YES NO X BASIS: T_his change does not affect the design or operation of safety-related equipment and thus the probability of I

occurance of an accident is unaffected.

2.

Will the consequences of an accident previously X

evaluated in the FSAR be incressed?

YES NO BASIS: This change does not alter 'the design or operation of safatv-related eculpment and thus the consequences of an accident are unaffected.

3.

Will the probability of occurrence of a malfunction of equipment important to safety previously calculated in the FSAR be increased?-

YES NO x BASIS: This change increases onitoring frequency of CCW valves to Containment Fan Coolers. Equipment degradation will be detected sooner, reducing the probability of occurance.

4.

Will the consequences of a malfunction of equipment important to safety predously evaluated in the FSAR be increased?'

TES NO X BASIS: The meIhoi! of testinr. is unchanged, thus the design and operation of safety-related equipment is also unaffected.

The consequences of a malfunction are unchanged.

5.

Will the possibility for an accident of a different type than any evaluated previously in the FSAR be cre:ted?

YES NO X

BAS'IS: This change does not affect the design or operation of safety-related equipment and thus could not result in a i

different type of accident.

UNT-001-003 Revision 11.6 (1 of 2) 36

I 1

10 CFR PART 50.59 SAFETY EVALUATION CECKLIST PROCEDURE No.

N/A TITLE LP&L Pump and Valve Inservice Test Plan CHANGE NO.

1 Relief Request 3.1.43 (Deleted)

{

REVISION NO.

6 DELETION 7 YES NO X 6.

Will the possibility for a malfunction of a different type than any evaluated previously in the FSAR be created?

YES NO BASIS: This change does not alter the design or operation of safety-related eculpment and thus does not result in any different type of malfunction.

7.

Will the margin of safety as defined in the basis for any Technical Specification be reduced?

YES NO y BASIS: This change vill not reault in a decreased margin of safety as the operation and design of safety-related e~uipment is unaifected.

q 8.

Will the level of' Fire Protection be decreased as related to that in the approved Fire Protection Plan?

YES NO X BASIS: This change does not affect Fire Protection Pumps or valves, or any other Fire Protection equipment.

If the answer for any questions above is "YES", an unreviewed, safety question may be involved, and should be processed per UNT-1-004 ATTACH ADDITIONAL PAGES i

IF'NECESSARY.

,DATE 7

? [f?

PERFORED BY:

A f[

Signature

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1 1

UNT-001-003 Revision 11.6 (2 of 2) 37 l

10 CFR PART 50.59 SAFETY EVALUATION CHECKLIST j

1 PROCEDURE No.

N/A TIyLg LP&L Pump and Valve Inservice Test Plan CHANGE NO.

1 Relief Request 3.1.56 (Revised)

REVISION NO.

6 DELETION? YES NO X

1.

Will the probability of occurrence of an accident previously ca'1culated in the FSAR be increased?

YES NO X BASIS: This change clarifies the determination of operabiltiy ranges for valves. This change is more conservative than Section XI and accident probability is unaffected.

2.

Will the consequences of an accident previously evaluated in the FSAR be increased?

YES NO X BASIS: D is change clarifies the o'perability ranges of valves. The consequences of an accident are unaffected.

3.

Will the probability of occurrence of a malfunction of equipment important to safety previously calculated in the FSAR be increased?-

YES NO X BASIS: This change incorporates a more conservative approach to the evaluation of valve performance and corrective action. The probability of occurance of a malfunction is not increased.

4.

Will the consequences of a malfunction of equipment important to safety previously evaluated in the FSAR be-increased?'

YES NO X BASIS: This ch'ange presents a more conservative approach to the evaluation of valve performance and corrective action.

The consequences of a malfunction will not be increased.

5.

Will the possibility for an accident of a different type than any evaluated previously in the FSAR be created?

YES NO X BASIS: This chance does not alter the desten or operation of safety-related equipment, and thus does not result in a different type of accident.

UNT-001-003 Revision 11.6 (1 of 2) 36

10 CFR PART 50.59 SAFETY EVALUATION CHEGLIST PROCEDURE NO.

N/A TITLE LP&L Pump and Valve Inservice Test Plan CHANGE NO.

1 Relief Request 3.1.56 (Revised)

REVISION NO.

6 DELETION 7 YES NO X

6.

Will the possibility for a malfunction of a different type than any evaluated previously in the FSAR be created?

YES NO X BASIS: This change does not affect the design or operation of safety-related equipment, and thus does not result in any different type of malfunction.

7.

Will the margin of safety as defined in the basis for any Technical Specification be reduced?

YES NO X BASIS: This change will not result in a decreased marein of safety as the design and operation of safety-relate.d equipment is unaffected.

8.

Will the level of Fire Protection be decreased as related to that in the approved Fire Protection Plan?

YES NO X BASIS: Fire Protection valves will be monitored and evaluated more conservatively.

If the answer for any questions abcve is "YES", an unreviewed safety question may be involved, and should be processed per UNT-1-004 ATTACH ADDITIONAL PAGES II'NECESSARY.

PERFORMED BY:

DATE_7/d7/E7 N

Signature UNT-001-003 Revision 11.6 (2 of 2) 37

_______mm._

l LP&L Punp And Volva R vision 6 Ch. 1 Inzarvics Test Plcn TABLE OF CONTENTS l

l 1.0 PURPOSE l

2.0 REFERENCES

3.0 DEFINITIONS 4.0 RESPONSIBILITIES l

5.0 TEST PLAN 6.0 ATTACHMENTS LIST OF EFFECTIVE PAGES Title Revision 6 1-183 Revision 6 1

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W320858E 1

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LP&L~ Pump And Valve Revision 6 Ch. 1 Inservice Test Plan 1.0 PURPOSE The LP&L Pump and Valve Inservice Test Plan provides a description of the inservice testing plan for Waterford-3 Steam Electric Station for Safety-related ASME Boiler and Pressure Vessel Code Class 1, 2, and 3 pumps and valves in accordance with the requirements of subsections IWP and IWV of the ASME Boiler and Pressure Vessel Code Section XI,1980 Edition through the Winter 1981 Addenda (Reference 2.1).

2.0 REFERENCES

2.1 ASME Boiler and Pressure Vessel Code,Section XI, 1980 Edition Through Winter; 1981 Addenda, Subsections IWP and IWV.

2.2 Waterford 3 FSAR Section 3.9.6, Inservice Testing of Pumps and Valves 2.3 Waterford 3 Technical Specifications 4.0.5 2.4 10CFR50.55.a (g), Code of Federal Regulations 2.5 Draf t Regulatory Guide Task HS-901-4, Identification of Valves for Inclusion in Inservice Ter. ting Programs, Nov. 1981 2.6 Regulatory Guide 1.26, Revision 3 l

2.7 Waterford;3 POM Procedure, UNT-07-020, Administrative Procedure, i

Pump,and Valve Inservice Testing 1

2.8 NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs 2.9 NRC SER Related to IST Program and Requests for Relief, Docket NO. 50-382, dated February 7,1989.

3.0 DEFINITIONS None W320858E 2

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LP&L Pump And Valva Revision 6 Ch. 1 Insrrvica Tast Plcn 4.0 RESPONSIBILITIES 4.1 The Plant Manager-Nuclear is responsible for the approval of the test plan and any revisions made to it.

4.2 The Shift Technical Advisor (STA) Department is responsible for ensuring the proper development, assessment and improvements of this i

plan and for overseeing its implementation as follors:

i 4.2.1 Defining which pumps and valves are within Section XI i

jurisdiction per Reference 2.1, 2.3 and 2.5.

4.2.2 Preparation of relief requests for components which cannot be tested in accordance with Reference 2.1.

4.2.3 Ensuring that all implementing procedures are in accordance with this test plan.

4.2.4 Making changes to this plan to improve testing or incorporate station modifications.

4.3 The Operational Licensing Unit is responsible for transmitting Relief Requests and Plan revisions to the NRC.

5.0 TEST PLAN 5.1 GENERAL 5.1.1 This Test Plan is written in accordance with Reference 2.4.

References 2.5 and 2.6 were used for guidance in preparation of this plan. The Waterford 3 FSAR (Reference 2.2) and Plant Technical Specification 4.0.5 (Reference 2.3) reference this plan.

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Ravisica 6 Ch.:1.

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. Inservice Test Plan -

1.

5.1.2'LThis document.shall go-into effect beginning with baseline

' testing to establish reference data and shall then remain in effect through the first 120 month interval of commercial y

operation.

5.1.3.As a minimum, this plan will be reviewed and revised as necessary for compliance with:the ASME Code Lin effect 12 months prior to the end of the first 120 months of commerical

~

operation. Similarly, this plan will be reviewed and revised for each subsequent 120 month interval. Louisiana Power and.

Light Company reserves the right to submit plan revisions which may enhance or improve this pump and valve testing plan at any time within the effective period. Guidelines for revising the plan are contained'in Reference 2.7.

5.2 INSERVICE TESTING OF PUMPS.1. contains the table entitled " Pumps for Inservice Testing" which describes the inservice testing plan for pumps subject to the requirements of subsection IWP of Reference 2.1.

It provides identification of the pumps to be tested, the ASME Section III Code classes, drawing references, parameters to be' measured and test inte rvals. Attachment 6.2 contains the hydraulic circuit used-for the testing of each pump and the location and type of measurement for each of the required test quantities. Relief from the testing require-ments of Section XI is requested from the NRC where full compliance with the r,equirement of the Code is not practical. In such cases, specific information is provided in Attachment 6.3 which identifies the applicable code requirements, justification for the relief request, and the testing to be used as an alternate. When the code-required t

testing is performed in an unusual or complicated manner, clarifica-tions are included in Attachment 6.4 in order to explain how the requirements of Section XI are fulfilled.

.W320858E 4

LP&L Pump And Valve Revision 6 Ch. 1 Inservice Test Plan

+

5.3 INSERVICE TESTING OF VALVES 5.3.1.5 conttins the table entitled " Valves for Inservice Testing" which describes the inservice testing plan for valves subject to the requirements of subsection IWV of Reference 2.1.

It provides the identification of the valves to be tested by system, valve code classes, drawing references, test categories, size, types, positions, maximum stroke time limits, function, test requirements, and any alternate testing necessary. A legend of symbols is also provided in Attachment 6.5.

Relief from the testing requirements of Section XI is requested where full compliance with the requirements of the Code is nn' practical. In such cases, the table refers to a specific relief request number in Attachment 6.6 for the appropriate valves. The relief request provides specific information which identifies the applicable code requirements, justification for the relief request, and the testing to be-used as an alternate. The design of Waterford 3 does not include any valves which would be classified as ASHI Section XI Category D valves. When the code-required testing is performed in an unusual or complicated manner, clarifications are included in Attachment 6.7 in order to explain how the requirements of Section XI are fulfilled.

5.3.2 Some valves in this Test Plan have a fail-safe position. Both their normal and failure positions are tabulated. Valves with failure positions that are either closed or open are tested to l

those positions during the exercising tests.

5.3.3 The maximum stroke time limits contained in Attachment 6.5 are primarily based on the FSAR and Technical Specifications.

Valves may be tested using more conservative administrative limits based on individual valve performance.

W320858E 5

LP&L Pump And Vs1va-Revisica 6 Ch.'1 Inservice Test Plan 5.3.4 Valve testing is divided into two' categories. The first category includes valves that can be tested without major impact to plant operations. The second category in'ludes c

valves that must be tested during Cold Shutdown conditions.

Cold Shutdown testing.will commence no later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after' entering Cold Shutdown and continue until completed or; until the plant is' ready to return to power. -Completion of all valve testing is not a prerequisite.to return to power except as required by Plant' Technical Specification. Any testing not completed at one Cold Shutdown interval will be performed during the subsequent Cold Shutdown interval.

In the case of frequent Cold Shutdowns, valve testing will not be' performed more often than once every three (3) months.

NOTE Most. valve numbers have only three numerical digits with a few valves having four. Typically, the'four digit valves were added after the valves in that system had

'been given Unique Identification (UNID) numbers by LP&L.

Since valves are numbered according to their. relative location in the= flow path, a newly-added valve is given a fourth digit which maintains the unique numbering system and also reflects relative flow path position.

As an example, RC-3183 is situated between RC-318 and RC-3184..

6.0 ATTACHMENTS 6.1 Pumps for Inservice Testing 6.2 Pump Testing Flow Path 6.3 Requests for Relief from ASME Section XI Pump Testing Requirements 6.4 Clarification of Pump Testing Methods 6.5 Valves for Inservice Testing 6.6 Request for Relief from ASME Section XI Valve Testing Requirements 6.7 Clarification of Valve Testing Methods.

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'Rzvisica 6 Ch. 1

' Inservice Test-Plan 2.1: Requests for Relief from ASME Boiler and Pressure Vessel Code Section XI Pump Testing Requirements 2.1,1 Test Requirement Measure inlet pressure before pump startup and during the inservice test'.

Basis for Relief The Charging Pumps are positive displacement type _ pumps and do not have a performance curve like. centrifugal pumps.

Variations in inlet and differential pressure do not effect pump flow as long as the Net Positive Suction Head (NPSH) requirements of the pumps are fulfilled.' Each pump. inlet _has a pressure switch which will not allow the pump to start if-'

NPSH requirements are not met.

Alternate Testing Inlet pressure of the Charging Pumps will not be measured.

Since inlet pressure is not measured, differential pressure cannot be measured. As an alternate test, discharge pressure will be used for determining pump operability. If the dis-charge pressure is greater than or equal to RCS pressure, and measured flow is greater than or equal to 0.90 times the reYdrsaceflow,thepumpsareoperable.

Approval Relief granted per NRC SER dated February 7,1989..3 (1 of 5)

,W320858E 39

LP&L Pump And'Velva.

Revisien 6 Ch. 1-Inservico Test Plan 2.1.2 Test Requirement IWP-4120 requires that the full-scale range of each instrument-shall be three times the reference value or less.

Basis for Relief The Charging Pumps' discharge flow indicator does not comply with this requirement. Each of the three pumps produces a flow of 44 gpm. The flow gauge has a full-scale range of 150 gpm in order to accommodate three-pump flow, such as during safety injection operations. The full-scale. range is 3.4 times the reference value. The small difference between the code requirement and the range of this flow gauge is minor.

Alternate Testing The existing, installed flow indicator will be used for quarterly pump operability testing. The accuracy of the installed flow indicator is within Section XI requirements.

Approval Relief granted per NRC SER dated February 7,1989.

2.1.3 Test Requirement IWP-3100 requires that the resistance of the system shall be varied until either the measured differential pressure or the measured flow rate equals the corresponding reference value.

l.3 (2 of 5)

W320858E 40 I

I

't x

LP&L Pump And Volva R:visica 6 Ch. 1 Insarvica Test Plan L

Basis for Relief These systems have recirculation flow paths that contain l

either a restricting orifice or, in the case of the Boric Acid Pumps, a fully-open globe valve. The pumps that have a restricting orifict.are as follows: Containment Spray, High Pressure Safety Injection, Low Pressure Safety Injection, and Emergency Feedwater. The orifice limits flow through the recirculation line to a specific amount. The flow rate is therefore fixed and cannot be adjusted. The Boric Acid Pumps do not have a restricting orifice but do have a throttled and locked needle valve in parallel with a globe valve which can be positioned only in the fully-open or fully-closed position.

The recirculation flow rate is therefore fixed. When these pumps are tested usin6 these fixed-resistance' flow paths, the,

flow rates will be approximately the same each time the tests are conducted.

Alternate Testing Pump testing will be performed using fixed-resistance flow paths. Differential pressure, flow rate, and vibration are measured and compared to Alert and Required Action limits to determine pump operability.

~

Approval l-Relief granted per NRC SER dated February 7,1989.

,.3 (3 of 5)

W320858E 41 i-

l s

LP&L. Pump'And Valva-

-R:visica 6 Ch. 1

-Inservice Test Pica 2.1.4 Test Requirement IWP-4120 requires that the full scale range of each instrument shall be three times the reference value-or less. Subsection IWP-4110 sets the acceptable accuracy of pressure instruments at 1 2% full scale.

Basis for Relief The +2% full scale accuracy requirement-in conjunction with

-the allowable full ccale range of three~ times the reference value permits a reading that is off by up to 6% to be valid.

The Acceptable range for a given parameter can be exceeded solely due to allowable instrument accuracy, resulting in unnecessary' maintenance and additional testing.

It is desirable to use more accurate instruments when available to improve

. performance monitoring. Higher scale, more accurate instruments can be used to improve data acquisition and repeatability.

Alternate Testing

.To meet the intent of ASME Section XI and allow more flexible use of available gages, the pressure instrumentation used will provide an indicated accuracy of 6% or.better as determined by:

,F 11' scale Accuracy) (Full scale Range)

(

6% >

(Reference Value)

In no case will the range of a pressure instrument exceed 5 times the reference value..3 (4 of 5)

W320858E 42

LP&L; Pump And Velva.

Rsvision 6~Ch. 1.

Insarvics Test Pica L2.1;5 Test Requirement f-Measure bearing temperature annually.

Basis for Relief L

' Annual bearing temperature measurements'are an inefficient means of detecting actual or imminent bearing failure due to iU the rapid progression of the event.

. Alternate Testing The required vibration measurements taken during each test-

..are used to detect bearing degradation and failure.

i 9

4 E'.3 (5 of 5)

.W320858E 43

'4

_g 4.3 J

"LP&L Pump'And Velva; R:visica 6 Ch.J1, is <

~Insarvica Tast Plan hO'i 2.2 ' Clarifications'of Pump Testina Methods

'2.2.1 -This clarification deleted. Not' neces sa ry.

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'W320858E-44

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'R:visien 6 Ch.~ 1 Inservica Tzst Pica p

~~

-LEGEND OF SYMBOLS Legend for Valve Type j

BL - Ball' B-

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.CK - Check

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- Diaphragm GA. - Gate GL Globe N

- Needle PR - Pressure Relief or Safety

'ANG Angle i

Legend for Actuator Type A0 - Air Operated

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i:

j.5 (2 of 89) i l:

W320858E 46 l

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1

LP&L Pump'And. Valva R:visica 6 Ch. 1.

Inservice Test Plen Legend-for Valve Testing Requirements Q

- Exercise valves (full stroke) for operability at least once every three (3) months.

If one train of a redundant system is inoperable, then valves in the remaining train should not be cycled'since their failure would cause a loss of total system function.

- Remote valve position indicators are used to verify valve stem position.

CV -- Exercise check valves to the position required to fulfill.their function

~

at least once every three (3) months.

CC - Exercise valve (full stroke) for operability during each cold shutdown as allowed in Section XI, Article IWV-3522.

MT - Stroke time measurements are taken and compared to the stroke ~ time limiting value per Section XI Article IWV-3410. Trending of valve stroke times is perfdrmed per IWV-3417 - for valves with stroke time limits greater than two (2) seconds.

SRV - Safety and relief valves are tested per Section XI Article IWV-3510.

LT - Valves are leak tested per Appendix J to 10CFR50 at each refueling outage per relief request 3.1.55.

LTP - Containee,nt Purge valves are leak tested per plant Technical Specifications.

PIV - Reactor Coolant System Pressure Isolation valves are lesk tested per plant Technical Specifications.

LTO - Per IWV-3421, operational observations are used to demonstrate satisfac-tory performance of valves..5 (3 of 89)

W320858E 47

b-LPEL Fump And Valva Rnvision 6 Ch. 1 j

Inservico Test Plcn Legend for Alternate Valve Testina 1

CS - Exercise valve (full stroke) for operability during each cold shutdown and at each refueling outage.

. CSP -' Exercise valve (partial stroke) for operability at least once every three (3) months and exercise. valve (full stroke) at each cold shutdown.

CSR - Exercise check valve (partial stroke) at each cold shutdown and full stroke at each reactor refueling outage.

CSD - Exercise valve (full stroke) for operability during each cold shutdown if the system is depressurized.

RR - Exercise valve for operability at each reactor refueling outage.

PRR - Exercise check valve (partial stroke) quarterly, and full stroke at each reactor refueling outage.

NT - No testing required.

NST - No stroke time measurements are taken.

NPO - Seat leak tightness is demonstrated during normal plant operation.

TNT - Stroke times of these " rapid acting" valves are not trended due to very short st'roke times (less than or equal to 2 seconds).

ME - Valves are manually exercised quarterly.

DRR - Valves are disassembled and stroked during reactor refueling outages on -

a sampling basis..5 (4 of 89) 1 W320858E 48

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$;l....sn cc sLP&L Pump And V;1v3, R:visita 6 Ch 1 JI: service Tr t Plaa p

e,.,.

. r it

. 3.1. Requests' for Relief 'from 'ASME Boiler and Pressure Vessel Code '

4 1

Sect'on XI Valve Testing Requirements i

1 3.1.1 Test Requirement'

.IWV-3413(b) requires that the stroke time of all power-operated valves'shall be measured to the nearest.second for stroke

-times of 10 seconds or less. IWV-3417 requires that on any one test of power-operated valves, an increase in stroke time of'50% or more from the' previous test for valves with stroke times of 10 seconds or less, the test frequency shall te increased to once each month u-+.il corrective action is t.a ken ~.

Basli for Relief These solenoid-actuated valves have extremely short stroke times. Accurate measurement of these stroke times is not practical. In addition, the stroke times may vary from one test to another due to temperature and/or pressure variations.

l Alternate Testing These valves will be full-stroke tested. The stroke times will be measured to the nearest second and compared to the stroke time limit. Acceptance of the test will be based oniy on the ' stroke time limit and not on the "50%" criteria in IWV-3417. Valves that exceed their maximum stroke time limit of 2 seconds will be declared inoperable until corrective action is taken.

Approval

^

i Relief granted per NRC SER dated February 7, 1989.

,.6 (1 of 47)

'W320858E 134 i

} a y?Y yg M

~

D

f14-J" g;

- 3 c

g l Wi1

- LPE1 Pump And. Valva.'-

, R2visica'6 Ch.I

Inservica Test Ples;

.3

~

)

..j

!.o L3.1.2. Test Requirement, j

Exercise the valvee for operability at least once every three.

j (3) months.

")

i X,.'

Basis"for Relief _

- l w

.j The operability, testing (full-stroke) of these valves during; a_.

1

. normal l operation could cause a : loss of system function. -The j

i failure of these valves in a nonconservative position during i

1

a. cycling. test would cause the loss of the RCP seal water 1

_1-

.1 cooling function. The design of the valve will not facilitate

-]

. a partial-stroke test.

l l

i Alternate' Testing l

The valves will:Fe full-stroke tested for operability.at each-

- cold shutdown.

' Approval Relief granted per NRC SER dated February 7,1989.

1 l

p I

i l

l-1.

l.

l l.6 (2 of 47)

< - W320858E 135 4;

f n.

' 5,.

> ; p_:....

____.m.m__.__.__x_..u.-mm_.ami._--

m____-m_....-_.am

.m.

m_

a_ _ - _ _ _.

___m--___.

.m.____.-__

___m-

__a_

______m

___m._

.._._m

.am._,

1LP&L Pump And Valva Ravisien 6 Ch,1-

Inu rvica Tart Plcn-

~3.1.3 -Test Requirement

- IW-3417(b) and-IW-3523 state that when corrective action is

- required'as.a.respit of tests made during. cold'sh'utdoEn, the

' condition-shall be corrected before startup. A retest showing 1

- acceptable operation shall be'run following'any required'

- corrective action before the valve is returned to lervice.

Basis'for' Relief

-The plant Technical Specifications-prodide'the' requirements.

and plant conditions necessary for plant.startup, i.e., mode changes.

Alternate Testing The test. requirement will be satisfied before the valve is required for plant: operability as ' defined in the plant Techni-cal Specifications.

Approval.

i' Relief granted'per NRC SER dated February 7,1989.

u.

4.6 (3 of 47)

W320858E 136

pm

,u,

/LP&Il PM And V$1ves.

Revisica 6 Ch'1' I

~

Y

,' Inservice T:st Plen

Va

.e 3.1.4 This. relief request was replaced with-clarification 3.2.9 per p

NRC SER dated February.7, 1989.

3.1.5> Test Requirement

. Exercise valves for operability at least once'everylthree'(3)'

month's.

4, Basis for Relief.

Operability testing (full-stroke).of.these normally closed; valves during power operation would cause. concentrated boric.

q.

.g

. acid to be made available'to'the suction of the charging pumps. The charging pumps would inject the boric; acid into the Reactor Coolant System causing overboration and possibly' causing a plant shutdown..The design of the. valves.will not.

facilitate a' partial-stroke test.

Alternate Testing This valve will be full-stroke tested for operability at eachi cold shutdown.

Approval

. Relief granted per NRC SER dated February 7.- 1989.

f, ;

-1 Attechment 6.6 (4 of 47)

W320858E 137

.. _ = _. _ -_

-v 7

~

LLP&L Pump:And Valv2

~.Rzvisien 6 Ch 1 In2crvice Tact Plen

-6 1-3.1'6' Test Requirement Exercise check' valves for operability at least once every three (3)' months.-

Basis for Relief' Operability Testing..(full or partial stroking) of this normally_.

closed check' valve per IW-3520 requires flow verific'ation utilizing the flow of concentrated boric ~ acid to the suction of the Charging Pumps. During power operation, this flow verification would cause the~_ injection of the boric acid into the Reactor Coolant System causing overboration and possibly causing a plant shutdown.

Alternate Testing This valve will be full-strpke tested for operability at each',

cold shutdown with two Charging Pumps operating.

Approval Relief granted per NRC SER dated February 7,' 1989.

l

. +

1 i

j i

1

-.6 (5 of 47) l W320858E 138 L.

1 I.

Eb__ __ ____-

7 QJ V0:

LP&L' Pump And Valva

-R2visica 6 Ch 1

.Inservica Test'Plen.

3.1.7l Test Requirement-Exercise the valves for operability at least once every three

'(3) months.

,o Basis for Relief

-The operability testing (full stroke)'of these valves during:

normal. operation. could jeopardize the charging function' of the CVCS. Failure in a nonconservative'(closed) position-would eliminate the VCT as a source of RCS' charging and possibly cause a plant shutdown. Pressurizer level' control' would be: lost. In addition,_the' Regenerative Heat Exchanger-J.

would be subjected to unwanted thermal shock. The design of the valves.will not facilitate a partia?-stroke test.

Alternate Testing The valves will be full-stroke tested for operability at each cold shutdown.

Approval Relief grarted per NRC SER dated February 7,1989.

1 i

l..6 (6 of 47)

-W320858E 139 l

_m_-__.______

7_,__-

nr

,1 n'

LP&L: Pump 1And Volva LR:vinica'6 Ch'1 l

4Intervica Test Pl:n 3.1.8 : Test Requirement

- Exercise' valves for. operability!at least' once every three (3) months.

i i

'l Basis for Relief

=

The auxiliary pressurizer spray water temperature is approxi-

- mately-140 degrees F. cooler than normal pressurizer spray.

Operability. testing (full stroke) of these normally closed.

'j valves ~during power operation-would result in initiation of-i auxiliary. pressurizer spray which would induce. unnecessary l

thermal' shock in the pressurizer and associated piping and nozzles.

In addition, the introduction of.this cooler water'

.into the pressurizer will result in undesired primary pressure-

transients. The design of.the valves will not facilitate la partial-stroke test.

Alternate Testing The valves will be full-stroke tested for operability either duridh cold shutdcrn or during normal plant cooldown approach m ing cold shutdcen.

Approval Relief granted per NRC SER dated February 7,1989.

..6 (7 of 47)

LW320858E 140 1

)

3

'LP&L Pump"And Valvi

=Rzvisica'6'Ch 1:

Inservico.Tcst Plc2 11 3.1.9 Test Requirement:

~

IWV-3413(b): requires that the stroke time of all power-operated valves shall be measured'to the nearest second.for stroke times of -10 secoo$s or less..IWV-3417' requires that on any.one test of power-operated valves, an increase;in stroke; y

~ time of 50% or more from the previous test for valves withi stroke times of 10 seconds or less,.the test frequency shall be increased to once'each month unti1' corrective: action is taken.

y Basis for Relief These solenoid-actuated valves have extremely short stroke' times. Accurate measurement of these stroke times is not practical. In addition, the stroke times may vary from one test to another due to temperature and/or pressure variationsi Alternate Testing These valves 1will be full-stroke exercised either during cold-shutdown or during normal plant cooldown approaching cold shutdown. The stroke times will be measured to the nearest second and compared to the stroke time limit. Acceptance of

~

the test will be based only on the stroke time limit and not on the "50%" criteria in IWV-3417.

Approval Re,11ef granted per NRC SER. dated February 7,.1989.

.-.6 (8 of 47)

W320858E.

141 1.

Li _ _________ __ _

p, 3;

~'

~

~

lLP&L Pump'And* Valva Rivision 6 Ch 1 Inservisa Tcat Plcn 3.1.10 Test Requirement Exercise check valves for operability at.least once every three (3) months..

Bar.is'for Relief

' * ~

Operability testing (full or partia11 stroking). of these normally closed check valves per IWV-3520 requires flow verification utilizing the auxiliary pressurizer spray flow path. The auxiliary pressurizer spray water. temperature is approximately 140 degrees F cooler that normal' pressurizer spray. Operability testing of these check valves during.

c, power operation would induce unnecessary. thermal shock in the pressurizer and associated piping and nozzles.

In addition,-

. the' introduction of this cooler water into the pressurizer will result in undesired primary pressure transients.

Alternate Testing-The valves will be full-stroke tested for operability.either during cold' shutdown or during normal plant cooldown approach '

'ing cold shutdown with at least two Charging Pumps operating..

Approval Relief ' granted per NRC SER dated February 7,1989.

3.1.11 This: relief request was deleted at NRC meeting, October 24, 1984.

i

-1 l.6 (9 of 47)

W320858E 142 1

_Q_____

.LP&L Pump And Valva R;visica 6 Ch 1-Ic2crvic2 Tect Plcn' 3.1.12 Test Requirement Exercise check valves for operability at least once every three (3) months.

Basas for Relief The operability testing (full-stroke) of these normally closed check valves per IWV-3520 requires. flow verification into the RCS. These valves cannot be full-stroke exercised during power operation because the pumps cannot overcome RCS pressure.

During cold shutdown, these valves cannot be full-stroke exercised because design flow cannot be verified through the valves unless all LOCA test conditions can be met (i.e.,

suction from the RWSP through the pumps to the RCS with the RCS at atmospheric pres =ure).

Alternate Testing These valves will be partial-stroke exercised quarterly (coincident with pump testing) and full-stroke exercised during each refueling outage.

Approval Relief granted per NRC SER dated February 7,1989.

..6 (10 of 47)

W320858E 143

-a y-,

3 4

  1. y 3 ELP&L Pump'And Valv v-Revisicn 6'Ch 1' 4

' Inservica' Tast Ples =

~

t i

T

3.1.13 L Test Requirement'-

L Exercise' check valves for operability at least'once every-L; three1(3)fmonths.

I 1

I

.)

u Basis for Relief

- The operability' testing (full-stroke) of these normally closed

- check valves per.IWV-3520 requires flow verification under LPSI into the RC'.

These valves cannot be full-stroke exer-1 I

~

cised during power operation because the.LPSI pumps. cannot

)

.I overcome RCS pressure. Partial-stroking.these valves, using j

flow into containment, then back to the RWSP through a drain i

valve, would defeat the safety function of RCS Pressure Isolation Valves. During cold shutdown, these valves cannot be full-stroke exercised because design flow cannot be veri-fied through the valves unless all LOCA test conditions can be-met (i.e., suction from the RWSP. through both pumps to the RCS

'with the RCS at atmospheric pressure)

Alternate Testing These valves will be partial-stroke tested during each cold

~

shutdown.and full-stroked using LPSI design' flow during each refueling outage.

Approval Relief granted per NRC SER-dated February 7,1989.

I.6 (Il of 47)

L W320858E 144 1.

r e

I-LP&L Pump And V51v2

.Ravision 6 Ch 1-0 1 ;

py, ^

'Inservica Test: Plca I

13.1.14 > Test Requirement' Exercise check valves for. operability at -least once every.

.three (3) months.

Basis'for Relief The operability testing (full-stroke) of these normally-closed check valves per'IWV-3520 requires flow verification into the-RCS. These valves cannot be full-stroke exercised"during.

power operation because the ' IPSI pumps. cannot overcome RCS pressure. During power. operation, partial stroking these valves, using HPSI flow. into containment then back to the.

RWSP.through a drain valve, would defeat the safety function of RCS Pressure Isolation Valves (PIV's). During cold shut-

.down, these valves cannot be full-stroke etercised because design flow cannot be verified through the valves unless all

.LOCA test conditions can be met (i.e., suction from the RWSP through two HPSI pumps to the'RCS with the RCS at atmospheric pressure). Also, during cold shutdown, these' valves cannot be

. partial-stroke exercised because such testing would induce unwanted thermal shock to the safety injection nozzles and -

piping. Partial-stroke exercising'at cold shutdowns also increases the possibility of overpressurizing the RCS at low temperature.

Alternate Testing These valves will be full-stroke exercised during each refuel-

.ing outage.

Approval Relief granted per NRC SER dated February 7,1989.

,.6 (12 of 47)

W320858E 145

= _ _

LP&L. Pump And Valva R vision 6 Ch 1' si Intervica T2:t Plen 3.1.15 Test Requirement:

Exercise valves for operability at least once every three (3) months.

Basis for Relief The operability testing of these valves during normal. operation would cause a loss of system function. Stroking the valves

.would cause a decrease in safety injection tank (SIT) nitrogen pressure. The failure of one of these valves in a nonconser-vative (open) position would cause the associated SIT to become inoperable. Valve design does not facilitate partial-stroke testing.

Alternate Testing These valves wi'.1 be full-stroke tested for operability during each cold shutdown.

Approval Relief granted per NRC SER dated February 7, 1989.

1 l.6 (13 of 47)

W320858E 146

cm,-- -

g

-i i

L

(

fLP&L Pump' And Valvaf Revisies 6 Ch 11 P

' Inservice Test Plen e.

n H

i i*

3.I'.16 Test Requites *gt

[,

. Exercise check valves for operability at least once:every-k three (3) months.

o Basis for Relief The operability. testing of tnese.normally closed' check valves.

per. IWV-3520 during normal operation or cold shutdown is not -

pra ctical. During normal operation, these. valves cannot Le' full-stroke exercised because the safety injection tanks (SIT's) cannot overcome RCS pressure. The valves'cannot'be partial-stroke exercised during normal operation without making the SIT's ' inoperable, thus placing the plant in an li unsafe condition. During cold shutdown, these valves cannot' be fully or partially stroked without overpressurizing the RCS. During refueling ottages, these valves cannot.be full -

stroke exercised at SIT operating pressure without possibly causing internal core damage due to excessive flow rates. '

.i Alternate Testing.

The SIT's have four discharge check valves. Three are spring-v loaded and will be treated as one group. The other one is non-spring-loaded and will be treated as another group. One check valve-from each group will be disassembled'and 2anually exercised to its full-open position during each refueling outage on a staggered sampling basis. The two groups of check valves are as follows:

Group 1 Group 2 (Spring-Loaded)

(Non-Spring-Loaded)

SI-329A SI-330A I

SI-329B SI-330B Approval 1

Relief granted per NRC SER dated February 7,1989.

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.3.1.17 :-

This relief' request was deleted:st NRC meeting, October 24,-

l1984. Valves SI-331-A & B and SI-332 A1&'B were also deleted W

i-yh from this Test Plan.

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L3.1.18 Test Requirement-t Exere:ise check valves for operability at,least once every

'three (3) months.-

~l l

Basis'for' Relief i

The operability.' testing (ful1~or partial stroke) of these.

.J normally closed check' valves per IW-3520. during normal

l operation is not: practical. During'. normal operation,:these-valves cannot be full-stroke' exercised because neither the-i l

LPSI pumps, HPSI pumps.nor safety. injection tanks (SIT's) can~~

,l overcome RCS pressure. Partial-stroking these valves during-l power operation-using charging flow would induce unwanted-thermal shock to safety injection nozzles and piping. During.

cold shutdown, these' valves cannot be full-stroke tested unless all-LOCA test conditions can be met.

Fulfilling LOCA test conditior.s would require removing the Reactor: Pressure.

j i

Vessel (RPV). head. However, these valves are partial-stroke tested during each cold shutdown using normal shutdown cooling-l flow.

l Alternate Testing i

1 One check valve'from the following group will-be' disassembled'

.l

' and manually exercised to' its full-open position during each

'j refueling outage on a staggered sampling bas'is:

l 1

SI:-335A SI-335B SI-336A j

SI-336B l

Approval Relief granted per NRC SER dated February 7, 1989.

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1.6 (16 of 47)

.W320858E 149 l

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Rrvisica 6 Ch 1-E

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3.1.'19 Test Requirement-Exercise valves' for operability 'at least_ once.every.three.(3)'

months.

Basis-for' Relief 4

1The operability testing (full'or: partial stroke) of these g

valves during power' operation cannot,be accomplished because

~

the valves are interlocked with an RCS pressure signal'which

. prohibits the valves from opening' at an RCS pressure greater -

than 400 psig.

' Alternate Testing' g'

The valves will be full-stroke tested for operability at each-cold shutdown.

Approval Relief granted per NRC SER dated February 7, 1989.

1 i.6 (17 of 47)

-W320858E 150 I

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Rzvisles 6 Ch-1

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3.1.201 Test Requirement' m

Exercise check valves for operability at least once every.

three (3)' months.

Basis for Relief The' operability -testing (full or partial stroke) of these normally closed check valves per IWV-3520 during power opera-tion is not practical. Exercising these valves requires flow verification into the RCS. During' power operation the HPSI pumps cannot overcome RCS pressure and therefore cannot!

deliver any flow. Partial-stroking these salves during power operation.using charging-flow would induce unwanted thermal shock to Safety injection nozzles and piping. During cold shutdown, these valves cannot be full-stroke exercised because design flow cannot be verified through the valves unless all LOCA test' conditions'can be met (i.e., suction from the RWSP through two pumps to. the RCS with the RCS at atmospheric pressure). Also, during cold shutdown, these valves cannot be partial-stroke exercised because such testing would induce unwanted thermal shock to the safety injection nozzles and piping. Partial-stroke exercising at cold shutdowns also increases the possibility of overpressurizing the RCS at low ll temperature.

I 1

1 Alternate Testing j

3 These valves will be full-stroke exercised during each~ refuel-

.)

, ing outage.

Approval Relief granted per NRC SER dated February 7,1989.

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".6 (18 of 47)

W320858E 151

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3.1.212; Test Requirement'

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~three (3) months.

Exercise check. valves for. operability at'least'once every i h

.! s'

' Basis for Relief

The operability testing (full-stroke) = of these normally closed check valves' per IW-3520 during-power ' operation is not '

practical.. Full' stroke exercising requires; flow verification from the SIS Sump through a HPSI pump into the RCS with the

~

g RCS at atmospheric conditions. During' power operation and:

. f; cold shut' downs,lthese test conditions cannot be met. During jp

-any mode of operation (including power operation, cold shut-q hfb down'and refueling outages), the pumping of. unknown-quality

[

t water into the RCS defeats the purpose of primary water U

g chemistry controls and could cause violation of plant.Techni--

h cal S. specifications. The only possible means of providing flow through these valves'is through the check valve' test connec-

l tion. However, flow through the 3/4 inch. test line.only-1 verifies a partial-stroke test. The small amount ~of water:

that could be pumped through the test' connection would not prove operability nor increase plant safety.

i

' Alternate Testing

'One of these two check valves vill be disassembled and manually exercised by hand to.its full-open position at each refueling.

3 outage on a staggered sampling basis.

Approval Relief granted per NRC SER dated February 7,1989.

T.6 (19 of 47)

W320858E 152

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,LP&L Pump And,Velva.

Rsvisica 6 Ch l' Inasrvic2 Tm:t P1:n 3.1.22. Test Requirement I

Exercise check valves for operability.at least once every three (3). months.

Basis for Relief The only positive means of exercising'(full-stroke)'this normally closed check valve is by directing' Emergency Feedwater.

- (EW) flow into the Steam knerators. The initiation of EW q

during power operation would-result in unwanted thermal shock.

j

to the secondary' portions of the Steam Generators, including:

~

]

feedwater nozzles and associated piping up to and including the EW-to-W connection. An introduction of cold water into

'the secondary system will also cause power transients.

Partial-stroke testing at power could be performed by providing EW flow through the valve then through the drain / recirculation line back to the Condensate Storage Pool. However, sud '

'l testing would cause the diversion of EW flow from the intended -

flow path to a non-safety, non-seismic line assuming that EW flow were then required due to a plant condition' change.

Alternate Testing After leaving cold shutdown and prior to entering Mode 2 (Startup), EW flow will be directed through the valve.at the design flow rate of the EW system. Verification of this flow through the valve will provide assurance that the valve has opened sufficiently to perform its function (full-stroke).

Approval Relief granted per NRC SER dated February 7,1989..6 (20 of 47)

W320858E 153

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3.1.23: ' Test Requirement 1

d Exercise check valves for operability at least once every

)

J three (3) months.

R Basis for Relief The only positive means of exercising (full or partial stroke) this normally closed check valve is by directing Emergency Feedwater (EFW) flow'into the Steam Generators. 'The initiation of EFW during power operation would result in unwanted thermal shock to the secondary portions of the Steam Generetors,

-)

including feedwater' nozzles and associated piping.up to and.

~

including the EFW-to-FW connection. An introduction of cold water into.the secondary system will' also cause power tran-

.l sients. The operation of the Turbine-driven EFW pump during cold shutdowns is not possible because steam for the turbine.

is not available. Partial-stroke testing atfpower could be performed by providing EFW flow through the' valve then fthrough -

the drain / recirculation line back to the Condensate-Storage Pool.. However,'such testing would cause the diversion of EFW flow from the intended flow path to'a non-safety, non-seismic line assuming that Elli flow were then required due to a plant condition change.

Alternate Testing EFW flow will be directed through the valve at-the design flow rate of the EFW system during a mode of operation after

,.les'ving cold shutdown and prior to entering Mode 2 (Startup) l in which steam is available.

Verification of this flow through the valve will provide assurance that the valve has opened sufficiently to perform its function (full-stroke).

Approval Relief granted per NRC SER dated February 7,1989..6 (21 of 47)

W320858E 154 1.

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LP&L Pump And Velva R7,visien 6 Ch 1 in32rvica T st P1 n l

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3.1.24 Test Requirement Exercise check valves for operability at least once every three (3) months.

'I Basis for Relief The operability testing (full-stroke) of these normally closed check valves per IWV-3520 requires flow verification into the RCS. These valves cannot be full-stroke exercised during power operation because the pumps cannot overcome RCS pressure.

During cold shutdown, these valves cannot be full-stroke-exercised because design flow cannot be verified through the valves unless all LOCA test conditions can be met (i.e.,

suction from the RWSP through the pumps to the RCS with the RCS at atmospheric pressure).

Alternate Testing These valves will be partial-stroke exercised quarterly and at cold shutdown by operating the LPSI Pumps in the Shutdown Cooling Warm-up Loop and full-stroke exercised during each refueling outage.

App rova_1_

Relief granted per NRC SER dated February 7,1989.

3.1.25 This relief request was deleted during NRC conference call, November 20, 1984.

l l.6 (22 of 47)

W320858E 155 l

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.Incarvica Test Plcn

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.3.1.26: Test-Requirement-Exercise valves for operability at least' once every three (3).

months.

is Basis for Relief g

The safety function of these-valves is to prevent the' loss of EFW by closing. The operability testing (full stroke) of these valves during normal operation is not~ practical.-

Tull-stroke exercising requires an interruption of feedwater to the Steam Generators which would result in a plant shutdown.

- Alternate' Testing These valves will be partial-stroke tested (10% stroke) for.

operability _ quarterly and full-stroke tested.during each cold shutdown.

- Approval Relief granted per NRC SER dated February 7,1989.

3.1.27 Test Requirement Exercise valves for operability at least once every_ three (3) months.

. Basis for Relief The operability testing (full lor partial stroke) of these normally closed valves during power operation is not practical, Stroking the valves would induce unwanted secondary and

.p[imary transients. Failure of the valves in a nonconserva-tive (open) position would force a plant shutdown.

Alternate Testing These valves will be full-stroke tested for operability during each cold shutdown.

Approval Relief granted per NRC SER dated February 7,1989..6 (23 of 47)

W320858E 156

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LP&L Pump And Volva-

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s 3.1'.281 This :- relief request was. deleted 'at-NRC' meetiag, October 24,-

g 1984.

3.1.29 Test Requirement Exercise valves for ' operability at least.once every three..(3),

montrs.

Basis'for Relief The operability testing.(full-stroke) of these normally-open valves during power-operation is not practical. Full stroking the valve will cause a plant shutdown.

Alternate Testing.

These valves will be partial-stroke tested (10% stroke) for..

operability quarterly and full-stroke tested during each. cold >

shutdown.

Approval Relief granted per NRC SER dated February 7, 1989.

..6 (24 of 47) 0'L W320858E 157

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1P&L Pump And Valv2:

Revisien 6 Ch'1 Icarrvica T:st Pics 3.1.30' Test Requirement-Exercise' check valves for operability at least once eve y three (3) months.

Basis for Relief The operability testing (full or partial stroke) of these normally closed check valves per IWV-3520 during power opera-tion or cold shutdown is not practical. Stroking these valves with flow would require the spraying of containment resulting in unnecessary equipment damage. Valve disassembly (manual full-stroke) during power' operation is not practical because the valves are inside containment. During cold shutdown, valve disassembly would regulre draining a portion of the system which is beyond the scope of cold shutdown testing. An air test for flow verification would require either draining a portion of the system or risking the possibility of wetting equipment inside containment. Therefore, the air test is impractical. In general, performing any test during power operation which lowers the water level in the spray header below.r149.5 feet MSL elevation places the plant under a Limiting Condition for Operation (LCO) and may result in a plant shutdown.

Alternate Testing One of these two check valves will be disassembled and manually exercised by hand to its full-open position at each refueling

.out'ge on a staggered sampling basis.

a Approval Relief granted per NRC SER dated February 7, 1989.

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l.6 (25 of 47)

W320858E 158 i

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1.P&L Pump And Valve

Rsvisics 6 Ch 1.

' Icatrvice Tast Plais c l ',

-3.3.31 Test Requirement l

l' Esercise valves for operability et least once every three (3)

months.

Basis for Relief

-The operability testing (full stroke) of these valves during I

normal operation would jeopardize the RCP cooling function.

. Cycling of the valves would. interrupt the CCW supply to the reactor coolant pumps. Also, the failure of the valves in a

'nonconservative position during the cycling test would result in a-loss of the system function. The design of the valves t..-

does not facilitate a partial-stroke test.

Alternate Testing u

I3 The valves will be full-stroke tested for operability during each cold shutdown.

Approval Relief granted per NRC SER dated Tebruary 7.1989.

1 4

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1.6 (26 of 47)

W320858E 159 A

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3.1.32 Tast R:quirement l

Exercise valves for operability at least once every three (3)

' months.

Basis for Relief Tue operability testing (full stroke) of this valve during normal operation would cause an interruption ci instrument air supply to instruments and r quipment within containment.

Also, a failure in a nonconservative position during a cycling test would cause a complete loss of instrument air supply to the containment. The loss of Instrument Air to Containment would cause the Letdown Isolation Valves, CVC-101 and CVC-103, to fail closed. These CVC valves are not stroked closed during power operation, as explained in relief request 3.1.7.

Therefore, this Instrument Air Isolation valve cannot be stroked closed at power. The design of the valve will not facilitate a partial-stroke test.

Alternate Testing The valves will be full-stroke tested for operability during each cold shutdown.

Approval Relief granted per FRC SER dated February 7,1989.

..6 (27 of 47)

W320858E 160 L,

.LP&L Pump And V;1va'.

R2visita 6 Ch 1 1 <

I02rvica Tcst. Plea 3.3.33-. Test'Requiremeg Exercise check valves for operability at least'once every' thr'ee-(3) months.

Basis for Relief Due to plant design, it is not practical to verify by any positive means, neither directly nor indirectly, the operabi-lity.of these normally open check valves per the requirements of IW-3522(a).

Alternate Test'ing Valve closure will be verified during the performance of the leak-rate tests at each refueling outage.

Approval

~

Relief granted per NRC SER dated February 7,1989.

3.1.34 This relief request was deleted per NRC dated February 7, 1989.

1 1

ti

?.6 (28 of 47)

W320858E.

161 a__

L..

LP&L' Pump And V;lve
R;vis'ie:n 6 Ch' 1 p.

Instrvici Tsat Plc2 li

\\;

l 3.1.35' Test Requirement Exercise. check valves for operability at least once every three (3) months.

1 1

Basis for Relief The operability testing (full.'or partial stroke) during normal' l.'

operation or cold shutdown of these valves provides no assur-ance of an increase in safety. The valves are containment isolation valves which are normally closed'and passive.

Alternate Testing The valves' closed position will be verified during the performance of the leak-rate tests at each refueling outage.

Approval

. Relief granted per NRC SER dated February 7,.1989.

~3.1.361 This relief request was deleted at NRC meeting, October 24, 1984. Valves NG-161 A & B and.NG-162 A & B were also deleted from this Test' Plan.

4

..6 (29 of 47)

'W320858E 162

LP&L'PumpLAnd V 1v2'

-RIvicita 6 Ch 1 I::c rvica Tsst-Plea 3.1.37 Test Requirement Exercise valves 'for operability at least once every three (3) ~

months.

Basis for Relief The operability testing (full stroke) of these valves during

-normal operation could cause a loss of system function.

A-

~

failure while cycling in a nonconservative (closed) position would cause a loss of the containment atmosphere r:41ation monitoring system. The valve design does not facilitate a-partial-stroke test.

Alternate Testing

' The valves will be full-stroke tested for operability at each cold shutdown.

Approval Felief granted per NRC SER dated February 7, 1989.

3.1.38 Test Requirement The stroke time of all power-operated valves shall be-measured.

Basis for Relief No physical means exists to measure the stroke times of these solenoid-operated valves. These valves do not have position indicators.

In addition, the stems are not visible from the exterior of the valves. Also, there is no critical limit on

- 'the stroke time. Valve design does not facilitate partial-stroke testing.

Alternate Testing Verification of normal sample flow through the appropriate Hydrogen Analyzer demonstrates that the valves move from a closed to an open position.

Approval l

Relief granted per NRC SER dated February 7,1989.

1.6 (30 of 47)

W320E58E 163

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W LP&L Pump And.Vilva,

'Rivisisn 6'Ch 1 11

-Inn rvica Test Picta'-

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3.1.39 Test Requirement 1

IW-3522(b) requires. that for normally-closed.chsk valves

.that are stroke'd without flow, a mechanicai exerciser shall

~

be used and the, torque values must be w'ithin certain limits.

]

l Basis for Relief

-l Due to; valve design, a mechanical exerciser cannot be used.

al l

~!

Alternate Testing These valves, will be manually exercised by hand to-their..

1 full-open position quarterly.

i i

Approval Relief. granted per NRC SER dated February 7,1989.

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1.6 (31 of 47)

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LInarrvica Tset'Plco-L 3.1.40 Test Requirement Exercise check valves for operability at least once every

'three (3) months.

l Basic for Relief' Operability testing (full stroke)'of.these normally-closed check valves per IWV-3520 requires flow verification utilizing the emergency boration flow path to the suction of.the Charging-Pumps with at least two Charging Pumps in operation. During power operation, this flow verification would.cause the injection of concentrated boric acid into the Reactor Coolant System causing overboration and possibly causing a plant shutdown. Partial-stroke testing would require L flow verifica-tion from the BAM Tanks to the RWSP. Putting highly-concen.

trated boric acid into lines.that are not heat traced could result in clogging of the' lines thereby causing a loss of;one of'the three emergency boration flow paths. Although the line (3CH3-27A/B) to the RWSP could be. flushed with Primary Make-up Water, it would be very unwise to routinely do so..The plant would be placed in a position of having to rely on a non-safety system (PNU) to protect a safety system (RWSP suction).

In addition, line 3CH3-26A/B could not be flushed without inject-ing a slug of highly-borated water and some quantity of unborated PMU water into the RCS via at least one Charging Pump, thereby, causing Primary reactivity changes.

Alternate Testing Full-stroke operability testing of these valves will be accomplished during each cold shutdown by providing flow individually from each Boric Acid Pump to the suction of the Charging Pumps with at least two charging Pumps in operation.

Approval Relief granted per NRC SER dated February 7, 1989..6 (32 of 47)

W320858E 165

__._y Irsarvic2. 700t. Plc3 3.1.41:-T5st Requirement P

}'

Exercise check. valves.for operability at least once-every.

I three (3) months.

I:

'i Basis for Relief The operability testing (full or partial stroking) of this I'

check valve during normal operation requires that all' charging flow be diverted. from the normal flow path through this valve.

l' Failure of this valve in a nonconservative.(closed) position causes chargingito be secured, thereby putting the plant in an i

-undesirable and potentially. unsafe condition. In addition, L.

the securing of charging flow will cause a rapid temperature

. increase in the Regenerative and Letdown heat exchangers.and-

. associated piping, possibly. inducing thermal shock. Also, securing of charging flow with charging pump (s) running will cause the lifting of the. safety valves on the discharge of the" charging pump (s), thereby increasing the possibility of. gas:

L binding the pump (s).

l Alternate Testing This check valve will be full-stroke tested for operability at each cold shutdown with at least two Charging Pumps; operating.

l Approval Re; lief granted per NRC SER dated' February 7, 1989.

l

..6 (33 of 47)

W320858E 166 l

b

F-R:;visiec 6 Ch 1

]

LP&L Pump And Velva Inwrvico Tast Plea 3.1.42 T_ent Requirement Exercise valves for operability at least once every three-(3) months.

Basis for Relief Operability testing (full-stroke) of these normally-closed valves during power operation would cause a loss of reactor coolant which would produce unwanted pressure.and. level changea'in the Reactor Coolant System. These pilot-operated solenoid valves, which are installed with RCS pressure under the pilot disc, have historically have a " burping" problem at other nuclear plants. With the RCS pressurized, opening either valve produces a pressure surge in the line which causes the:other valve to pop open, thereby opening a line from the RCS to the Quench Tank. The valves can generally be.

' closed after flow stabilizes in the vent line.

Operability testing (full-stroke) during cold shutdown with the RCS pressurized produces the same effects as testing at power except that the amount of water lost would be less.

Plant Technical Specification 4.4.10, which is based on NUREG-0737 and Generic Letter No. 83-37, requires that these valves be stroked and flow be verified at least once per 18 months during cold shutdown or refueling. Testing these valves more frequently, such as during each cold shutdown wi.th the RCS pressurized, produces some undesirable effects.

Fir example, the water and gases vented from the RCS to the Quench Tank are contaminated with radioactive material.

Routinely venting the RCS would cause an increase in radiation and contamination levels inside containment, particularly if the Quench Tank rupture disc pressure is exceeded.

In addition, due to valve design, routinely opening these valves greatly increases the probability of them sticking open which will overfill the Quench Tank and dump contaminated water on the containment floor. However, these valves can be safely exercised during cold shutdown if the RCS is depressurized.

Valve design does not facilitate partial-stroke testing..6 (34 of 47)

W320858E 167 l

l

-__ __ L :_ _.-

LP&L Pump And V 21v2 R;visica 6 Ch 1 Ins:rvica Tcst Plea 3.1.42 Alternate Testing The valves will be full-stroke tested for operability during each cold shutdown if the Reactor Coolant System is depres-surized below 200 psia. Otherwise, these valves will be full stroked at cold shutdown or refueling at least once per 18 months per plant Technical Specification 4.4.10.

Approval Relief granted per NRC SER dated February 7,1989.

3.1.43 The Relief Request was deleted.

i l

).6 (35 of 47)

)

W320858E 168 i

___.__m._.m.

..________.___..-________.__._._____m____..

I' LLPsL' Pump And, Valva RIvisies 6 Ch 1

'In32rvica Test Plen l-l

~ 3.1.44' Test Requirement

[

[g Exercise check valves for operability at least once every three (3) months.

Basis for Relief-The operability testing (full-stroke) of these normally-closed check valves per IWV-3520 during power operation is not

- practical.. Full-stroke exercising requires verification of-full-design steam flow from the Main Steam line to the EFW-Pump A/B Turbine. Full flow of steam through these lines-and valves cannot be obtained unless the EFW Pump A/B is delivering-full design flow of water to the Steam Generators. During power. operation, the EFW Pump A/B can be' operated only in the minimum recirculation mode.

Alternate Testing During power operation, steam for.the EFW Pump A/B' quarterly test will be supplied through one of these valves. Then the other valve will be used to supply steam. Acceptable pump tests verify that each check valve partially strokes. These check valves will be full-stroke tested for operability while the EFW Pump A/B provides design flow to the Steam Generators after leaving cold shutdown and prior to' entering Mode 2 (Startup).

Approval

- ' Relief granted per NRC SER dated February 7,1989.

s.6 (36 of 47)

W320858E 169

In :rvic] Tast Plcn 3.1.45 This r211 f requ:st w:s d:1stcd during NRC c nfer nca call,

=

November 20, 1984.

l 1.6 (37 of 47) l l

W320858E 170 i

l

'.LP&L Pump And V:1vs R:vietta 6 Ch 1' In23rvica Test Plcn i '

3.1.461 Test Requirement-Exercise valves for operability at least once every three-(3)

. months.

B e

Bas'is for Relief The. operability testing'(full stroke):of.these normally-open valves during power operation'could cause a loss of system function. The design of the Feedwater System is such that'in h

the event of a Reactor Trip' Override (RTO) the Main Feedwater-

. Control' valves close and these Main Feedwater Control Bypass.

valves go to a position that allows a flow equal to.5% of normal Main Feedwater. This reduced flow' rate causes a

-gradual cool-down of the primary systems. Failure of one of these Bypass valves in a nonconservative (closed) position coincident with an RTO would require initiation of Emergency-Feedwater flow to the Steam Generators which is undesirable because of thermal shock'and power transientsi s.

Partial stroking of these valves at power also possibly produces undesired power transients.

Alternate Testing These valves will be full-stroke tested during each cold shutdown.

Apbroval

. Relief granted per NRC SER dated February 7, 1989.

>.6 (38 of 47)

W320858E 171

___m

- - _ ~

'Intarvica Tast Plco-f 3.1.47 T:st R:quirrment.

IW-3522(b) requires: that for. normally-closed.' check valves that 'are stroked.without. flow, a. mechanical exerciser shall'

^

be used and the torque. values'must be within certain: limits.

Basis for Relief-

'Due to valve design, a' mechanical exerciser cannot be used;

' Alternate Testing These valves will be manually exercised:L/ hand to their full-open' position during each cold shutdown.

Approval Relief' granted per NRC SER dated February 7,.1989.

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l 13.1.48 Test' Requirement-Exercise ~ check valves for operability at least once every.

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three (3) months.

Basis for Relief The CAR system is designed for post-accident containment-dilution and, as such,,is not designed for operation while

~the unit is at power.

(This system is a back-up system to

~

the Hydrogen Recombiners.) In addition,-operability testing (full or' partial stroke) of these normally-closed check

~

valves per IWV-3520 requires flow verification utilizing the CAR make-up fans with the manual butterfly valves open.

Since the isolation valves in line with these check valves do not-receive a CIAS, there exists a possible'unmonitored radiation release path should a Containment Isolation occur -

while the testing was in progress. Manual stroking of the-check valves at power could place the plant in an unsafe condition. Failure of.one of these check valves in a

- nonconservative (open) position would negate the double Containment Isolation valve principle.

Alternate Testing These check valves will be manually full-stroked for operability during each cold shutdown.

Approval

,.Re1ie'f granted per NRC SER dated February 7,1989.

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L3.1.49;TestRequirement)

-g Exercise' check valves ' for ~ operability at' least once every -

th'ree (3)' months.

,s Basis for Relief Operability testing (fullt or partial stroke) of 'these: normally-closed check valves per IWV-3520 requires flow verification from the Annulus into'the Containment. The Annulus would have to be pressurized to accomplish any flow test.

The Annulus is,

required by plant Technical Specifications to be maintained at~

a vacuum. Therefore, flow testing requires that,the plant-routinely exceed Technical Specification limits. -Manual.

strokicg of the check valves at power could place the plant!in?

an unsafe __ condition. Failure of one of-these check' valves:in-a nonconservative (open) position would negate the. double Containment Isolation valve principle.

Alternate Testing These check valves will be' manually full-stroked for operabi-lity during each cold shutdown.

Approval Relief granted per NRC SER dated February 7, 1989.

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'3.1.50 This relief request was deleted...

3.1.51. Test Requirement Exercise valves for' operability at least once.every three (3)

. months.

r-Basis for Relief The safety function of these valves is to' prevent the loss of.

EFW by closing. The operability testing'(full stroke) of these valves during normal operation;is'not practical. Full-stroke exercising requires an interruption of fe* Gater to the' Steam Generators which would result in a p'..nt shutdown.

A

' Alternate Testing These valves will be partial-stroke: tested for operability during the' course of normal plant' operations,-although the frequency cannot be specified as stated'in IW-3414. They will be full-stroked tested during each cold shutdown.

< Approval Relief granted per NRC SER dated February 7,1989.

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-3.1.52 Test Requirement-The stroke time of all power-operated valves shall' be measured.

F.

Basis for Relief No physical means exists to measure the' stroke times of these-r t:

soleniod-operated valves. These valves do not have position-I.

~ indicators. In; addition, the stems:are not visible from the I.

exterior of the valves. Also, there is no critical limit on the stroke time. Valve design does not~ facilitate partial-stroke testing.

Alternate Testing

~ Verification of flow from the appropriate Nitrogen Accumulator demonstrates-that the valve moves'from a closed to an open

-position.

Approval Relief granted per NRC SER dated February'7,1989.

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3.1-.53 Test Requirement.

Exercise. check. valves to the' position required to. fulfill-

'their safety function at lease once every three (3) months.

Basis for Relief One of the Safety functions of these check valves, MS-402A-

-and MS-402B, is to close in.the event of a Main Steam Line Break (MSLB) with valves MS-401A and MS-401B open..If a MSLB occurs, both MS-401A and MS-401B go fully open and-remain-there. The check valve closest to the broken line must hold Main Steam pressure from the. unaffected Steam Generator. and prevent the diversion of Main Steam flow away from the EFW Pump A/B Turbine. Testing of these check valves to verify-that they.are closed and capable of holding pressure requires that the downstream side of the checks be pressurized and the' upstream side be vented to atmosphere with MS-401A and MS-401B open. This cannot be performed during normal power operatlon since the upstream side is pressurized with Main Steam.

Alternate Testing These check valves will be pressure tested with air to verify they are closed and capable of holding pressure with the upstream side vented to atmosphere. This testing.will be performeil during each cold shutdown.

Approval Relief granted per NRC SER dated February 7, 1989.

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a 3.1.54 This Relief Request deleted per NRC SER dated February 7,.

1989.. Pressure regulating valves NG-611,. NG-612, NG-711,,

NG-712,- NG-811, NG-812, NG-911,;NG-912 were' deleted from program per NRC SER dated February 7, 1989.

3.1.55' Test Requirement'

. IW-3421 through IW-3425 Basis for Relief Leak test procedures and requirements for containment isolation -

valves specified in 10CFR 50, Appendix-J are equivalent to the requirements of IW-3421 through IW-3425..

Alternate Testing Containment isolation valves will be tested using.10 CFR 50, Appendix J.

The analysis of leakage rates and corrective action requirements of IW-3426 and IW-3427 (a) will be followed.

Approval Relief granted per Generic Letter 89-04.

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b LP&L Pump And Vciva R;vicirn 6 Ch 1 Ins rvica.Ta;t Plcn 3.1.56 Test Requirement IWV-3417 requires that for power operated valves, if an increase in stroke time of 25% or more from the previous test for valves with full-stroke times greater than 10 sec. or 50%

or more for valves with full stroke times less than or equal to 10 sec. is observed, test frequency shall be increased to once each month until corrective action is taken.

Basis for Relief Measuring changes in stroke times from a reference value based on individual valve performance as opposed to measuring changes from the previous test is better for several reasons:

1.

Simplifies implementation of Alert limits (increased frequency testing criteria) and Required Action limits because the limits do not change following each test.

2.

By basing corrective action on a 25% increase from previous test, valves could degrade " acceptably" by 20% each test with no required action until the absoute limit was reached. Corrective action based on deviation from a reference value eliminates this possibility.

3. -Pump testing and valve testing will share similar corrective action implementation, resulting in a more consistent IST Program.

4.

Allows better analysis of valvp* performance and trend information..6 (46 of 47)

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3.1.56 Alternate Testing' A. reference stroke time value is assigned to each valve which is stroke time' tested. Alert limits are established based on.

historical valve performance and expected allowable deviations. Exceeding the Alert' limit indicates a degraded:

valve which is.still operable..;but must be addressed.

Required Action limits are established to indicate a' valve which has substantially degraded and corrective action must i

be taken before the valve reaches a condition-where there is a higher probability of failure to perform its safety function.

Valves will be timed to the second whenever possible.

As performance' data accumulates,. reference values'.and applicable limits (Alert and Required Action) may be adjusted -

.to ensure actual valve degradation.is-detected.

Valves that exceed the Alert limit will be. tested monthly l

(increased frequency testing) until corrective action is taken, 3 consecutive tests indicate a single timing anomaly, or an engineering evaluation justifies changing the reference

-value and applicable limits. Rapid acting valves will have a Required Action limit of 2 seconds with no Alert limit.

~

,. Valves that exceed the Required Action limit will be declared inoperable until corrective action is taken. Corrective action may be repair or replacement, or an engineering evaluati,on which justifies changing the current reference value and applicable limits, not to exceed the maximum stroke.

time limit listed in Attachment 6.5.

1 1'

Approval l

Relief granted per Generic Letter 89-04.

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~3.2 Clarification of Valve Testing Methods 3.2.1 Deleted.

3.2.2 Code Requirement IWV-3522(b) requires that confirmation that the disk moves away from the seat shall be by visual observation, by electri cal signal, by appropriate piessure indications, or by other i

positive means.

Test Method Due to plant design, the operability of this normally closed check valve cannot be determined by any of the specific methods allowed in IWV-3522(b). The only positive means of demonstrating operability is by verification of flow such that the valve moves to perform its function. This valve will be tested quarterly coincident with the charging pump test provided the pump is cperable. A successful pump test which demonstrates that the pump is operable also demonstrates that the discharge check valve is operable.

3.2.3 Code Requirement IWV-3522(b) requires that confirmation that the disk moves away from the seat shall be by visual observation, by electri-cal signal, by pressure indications or by other positive means.

Test Method i

i Due to plant design, the operability of these normally closed check valves cannot be determined by any of the specific methods allowed in IWV-3522(b). The 'only positive means of demonstrating operability is by verification of flow such that the valves move to perform their function. During power

]

operation, the pumps will be operated to provide design flow in the recirculation path back to the RWSP, thereby full I

i stroking these valves..7 (1 of 3)

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3.2.4 This clarification' deleted. Replaced.with Relief Request 3.1. 24. :

3.2.5 Code Requirement.

l IW-3421 requires that Category A. valves shall be leak-tested, except that valves which function in the course of plant operation in a. manner that demonstrates functionally adequate-seat. tightness need not be leak-tested.

Testing Method' The seat' tightness of these valves is demonstrated to-be functionally adequate during normal plant operation. The safety injection tanks (SIT's) are monitored for pressure per Technical Specification 4.5.1.1.

Ability to maintain pressure =

in the SIT's indicates tdequate seat tightness of these valves.

3.2.6 This clarification deleted. Replaced with. Relief Request 3.1.44.

3.2.7 Code Requirement Exercise valves for operability at least once every three (3) months.

Test Method-Op;erability testing of these valves will be accomplished quarterly. However, prior to performing the tests, the operators will verify that at least two CCW pumps are operat-ing and that valve alignments provide CCW flow through at least one dry cooling tower and through line 3CC18-11A/B.

.This line provides CCW flow to the Fuel Pool Heat Exchanger, Letdown Heat Exchanger, CEDM Cooling coils and all Reactor Coolant Pump seal coolers..7 (2 of 3)

W320858E 182

_=- _ _ - _ _ = _ _ - _ _ - _ _ - _ _ - _ _.

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,c LP&L Pump lAnd Volv2-Rsvisien'6 Ch 1-Ins *rvice Test Plen :

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3.2.8. Code Requirement Exercise valves for operability. at least once every three (3) months.

-Test Method-Operability testing of'these valves will be. accomplished' quarterly..However,.these valves do not have position indica -

tors to provide. direct evidence of stem movement. Instead, the disk movement'shall be.-demonstrated by verifying normal-sample ~ flow through the appropriate Hydrogen Analyzer.

Establishment of norma 1' sample flow' demonstrates thatithe

-valves move.to perform their function. The. reclosure of each valve will be. demonstrated by verification of the " low flow" alarm on the appropriate-Ilyarogen' Analyzer 3.2.9 Code Requirement IWV-3417(a) gives increased frequency testing. criteria for ji valves experiencing an increase in stroke' time until

' corrective action is taken.

L Test-Method

~For valves identified as being-tested only *during cold shutdown,. these valves will be repaired or the plant placed in a -condition which allows monthly testing until corrective action is taken.

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