ML20211H086

Safety Evaluation for Proposed TS Changes to ASME Section XI Surveillance Testing

ML20211H086
Person / Time
Site:	FitzPatrick
Issue date:	09/26/1997
From:	POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20211H072	List: JAFP-97-0359, Informs That Util Is Revising TS Amend Application Submitted Under to Withdraw Proposed Changes to Sections 3.5.G & 4.5.G & SRs of Sections 4.7.A.5.a & 4.7.D.2.Revised TS & Se,Encl ML20211H080 ML20211H086
References
NUDOCS 9710060193
Download: ML20211H086 (51)

Text

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Attachm:nt 1113 JAFP 97 0359 SAFETY EVALUATION FOR PROPOSED TECHNICAL SPECIFICATION CHANGES TO ABME SECTION XI SURVEILL ANCE TESTING (JPTS 93 003) l l

New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT

Docket No. 50-333 DPR 59 9710060193 970926 PDR ADOCK 05000333 P PDR

Attachmont il to JAFP 97 0359 SAFETY EVALUATION FOR PROPOSED TECHNICAL SPECIFICATION CHANGES ASME_81.CTION XI Sl3VEILLANCE TESTING (JPTS 90 003)

1. DESCRIP_ TION OETHE PROPOSED.CHANRES The proposed change to the James A. FitzPatrick Technical Specifiutions (TS) incorporates the inservice testing requirements of Section XI of the American Society of Mechanical Engineers (ASME) Boller and Pressure Vessel (B&PV) Code and makes editorial corrections on the affected pages. The proposed change is described below.

Minor chaiges in format, such as type font, margins or hyphenation, are not described in this submittal. These changes are typographical in nature and do not affect the content of the Technical Specification.

incorporation of ASME Section XI

1. Revine page i to show Specification 3.1, Reactor Protection System, located on page 30i to reflect the renumbering of pages in item 2.

2. Renumber existing pages 30b,30c,30d,30e,30f and 30g to read 30c,30d, 30e,30f,30g and 301, respectively. The changes described in the following

' items 5 and 6 refer to these renumbered pages and indicate where new pages are inserted.

3. Add a new Surveillance Requirement 4.0.E to revised page 30a and new page 30b which reads as follows:

" E. Surveillance Requirements for inservice testing of components shall be applicable as follows:

1. Inservice testing of pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55alf),

except where specific written relief has been granted by the NRC pursuant to 10 CFR 50, Section 50.55a(f)(6)(i). The inservice testing and inspection program is based on an NRC approved edition of, and addenda to,Section XI of the ASME Boiler and Pressure Vessel Code which is in effect 12 months prior to the beginning of the inspection interval.

2. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice testing activities required by the Code and applicable Addenda shall be applicable as defined in Technical Specification 1.0.T.

)

o

Attachm:nt ll to JAFP 97 0359 SAFETY EVALUATION Page 2 of 18

3. The provisions of Specification 4.0.B are applicable to the frequencies specified in Technical Specification 1.0.T for performing inservice j testing activities, i 4.- Performance of the above inservice testing activities shall be in addition a to other specified Surveillance Requirements.

5. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification."

4. Add a new Bases Section 4.0.E to the newly created page "30h" which reads as follows:

"E. This specification ensures that inservice testing of pumps and valves will be performed in accordance with a periodically updated version of the FitzPatrick plant " Inservice Testing Program" and the " Weld and Support laservice inspection Program" to comply with Section XI of the ASME Boller and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a. The plant programs identify classifications required by 10CFR50.55a and Regulatory Guide 1.26. Request for relief from any of these requirements is provided in writing to the NRC and is not a part of these Technical Specifications.

This specification includes a reference to Technical Specification Section 1.0.T which defines the frequencies for performing the inservice testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda. This reference is provided to ensure consistency in surveillance intervals throughout these Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice testing activities.

Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda. For example, the requirements of Specification A.O.D to perform surveillance activities prior to entry lato an OPERATIONAL CONDITION or other specified applicability condition takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows pumps to be tested up to 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after return to normal operation. As another example, the Technical Specification definition of OPERABLE does not grant a grace period before a device that is not capable of performing its specified function is declared inoperable and takes precedance over the ASME Boiler and Pressure Vessel provision which allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared inoperable."

Attachm:nt il to JAFP 97-0359 -

SAFETY EVALUATl:N Page 3 of 18 5, On page 96, Surveillance Requirement 4.3.C.3:

a) R vise and reformat Surveillance Requirement 4.3.C.3 from:

"All control rods shall be determined operable once each operating cycle by demonstrating the se am discharge volume drain and vent valves operable when the scram test initiated by placing the mode switch in the SHUTDOWN position i; performed as required by Table 4.1-1 and by_ verifying that the drain and vent valves:

a. Close in less than 30 seconds after receipt of a signal for control rods to scram, and

b. Open when the scram signal is reset."

to "All control rods shall be determined operable by demonstrating the scram discharge volume drain and vent valves are:

lLQm Freauenev

a. Verified Open Once per 31 Days

b. Cycled Fully Closed and in accordance with the Open Inservice Testing Program -

c. Verified to close within 30 Once per 24 Months seconds after receipt of an actual or simulated scram signal and open when the actual or simulated scram signal is reset."

6. On page 105 and 106, Surveillance Requirement 4.4.A;-

a) Add a new Surveillance Requirement 4.4.A.1 which states the following:

"ligm Freauency -

Verify that each valve (manual, power operated, or Once per 31 Days i

automatic) in the system flow path that is not locked, sealed, or otherwise secured in position, is in the

= correct position."

L e &

Att chm:nt ll to JAFP 97 0359 SAFETY EVALUATl N Page 4 of 18 b) Change Surveillance Requirement 4,4.A.1 to 4.4.A.2, change format to lLem and Freauency as in 6.a above, and change frequency from: "At least Once per Month" to: "In accordance with the inservice Testing Program".

c) Change Surveillance Requirement 4.4.A.2 to 4.4.A 3, 4.4.A.4, 4.4.A.5, 4.4.A.6, and 4.4.A 7 and reformat to 112m and FreaufnGY as in 6.a above.

d) Change the frequency of Surveillance Requirements 4.4.A.3,4.4.A.4, and l 4,4.A.5 from "At least once during each operating cycle" to "Once par 24 months". ]

j e) Change frequency of Surveillance Requirements 4.4.A 6 and 4.4.A.7 from "At least once during each operating cycle" to "In accordance with the Inservice Testing Program".

l f) In Surveillance Requirement 4.4.A.7, delete the sentence reading "Both valves shall be inspected in the course of two operating cycles."

7. On page 109, Bases Section 3.4 A, replace the sentence:

l

' " Experience with pump operability indicates that monthly testing is adequate to detect if f ailures have occurred."

l with i

" Experience with pump operability indicates that periodic te, sting in accordance with the IST program is adequate to detect if degradation has occurred. Valves in the system fhwpath ere verified to be in the proper position on a monthly basis. This requirement does not apply to explosive valves or to valves that cannot be inadvertently misaligned such as check valves. Verifying the correct alignment for manual, power operated, or automatic valves in the system flow path provides assurance that proper flow paths will exist for system operation. The monthly trequency is based on engineering judgement and is supported by precedural controls governing valve operation that ensure correct valve positions."

8. On page 113, Surveillance Requirement 4.5.A.1; a) Replace "Once/3 Months" with "In accordance with the Inservice Testing Program" in Surveillance Requirement 4.5.A.1.b.

b) Delete Surveillance Requirement 4.5.A.1.c and replace with the following:

" Verify that each valve (inanual, power Once Per 31 Days operated, or autornatic) in the system flow path that is not locked, sealed, or otherwise secured in position, is in the correct position.

Attachment ll to JAFP 97-0359 SAFETY EVALUATION Page 5 of 18'

'c) Change the frequency of Surveillance Requirement 4.5.A.1.d from "once/ month" to "In accordance with the Inservice Testing Pro 0 ram".

d) Replace "31 days" with "In Accordance with the Inservice Testing Program" in Surveillance Requirement 4.5.A.1.g.

9. On pages 115a and 116, Surveillance Requirements 4.5.B.1; a) Change the format of Surveillanco Requirement 4.5.B.1 to ll2m and Freauency as in 6 a above.

b) Move the phrase "per Surveillance Requirement 4.5.A.3" from the 119m description to the Freauencv for Surveillance Requirement 4.5.B.1.a.

c) -In 4.5.B.1.b replace "a monthly" with "an" and add "In accordance with the Inservice Testing Program" under Freauency.

-d) Change 4.5.B.1.c.1" to "4.5.B.1.c", replace "a monthly" with "an" and add "In accordance with the Inservice Testing Program" under Freauencv.

e) Change "4.5.B.1.c.2" to "4.5.B.1.d", delete the phase "at least once every 3 ,

months and" from the llem e description and add "In accordance with the Inservice Testing Program" under Freauencv.

f) Add new Surveillance Requirement 4.5.B.1.e as follows:

"A verification that each valve Once per 31 Days -

(manual, power operated, or automatic) in the flowpath that is not locked, sealed, or otherwise secured in position, is-in the correct position."

g) Change "4.5.B.1.d" to "4.5.B.1.f", delete the phrase "during each five year period" in the item description and add "once per 5 years" under Frecuencv.

10. On pages 121 and'121a, Surveillance Requirement 4.5.E.1; a) Replace Surveillance Requirement 4.5.E.1.b with the following:

" Verify that each valve (manual, power Once per 31 Days operated, or automatic)in the system flow path that is not locked, sealed, or otherwise secured in position, is in the correct position."

7 4

Atttchm:nt ll to JAFP 97 0359 SAFETY EVALUATl:N Page 6 of 18 1

b) Change the frequency of Surveillance Requirement 4.5.E.1.c from )

"once/ month" to "Once per 92 days"..

c) For Surveillance Requirement 4.5.E.1.d, replace:

" Flow Rate Once/3 months" with

" Flow Rate Test - Once per 92 Days

- The RCIC pump shall deliver at least 400 gpm against a system head corresponding to a reactor vessel pressure of 1195 psig to 150 psig."

d) Replace "31 days" with "92 Days" in Surveillance Requirement 4.5.E.1.e.

11. On page 122, Surveillance Requirement 4.5.F; a) Revise the first sentence of Surveillance Requirement 4.5,F.1 to read:

"In accordance with the Inservice Testing Program perform a flowrate test on the required core spiay pump (s) and/or the RHR pump (s)."

' b) Revise Surveillance Requirement 4.5.F.2 to read:

"In accordance with the Inservice Testing Program perform an operability test on the required core spray and/or LPCI motor operated valves."

c)- Add a new Surveillance Requirement,4.5.F.5, which reads as follows:

"Once per 31 days, verify that each valve (manual, power operated, or automatic) in the system flow path that is not locked, sealed, or otherwise secured in position, is in the correct position for the required RHR'and/or core spray system (s)."

1 Att: chm;nt ll to JAFP-97 0359 SAFETY EVALUATION Page 7 of 18

12. On page 132, Rases Section 4.5, replace in the second paragraph:

"To increase the availability of the individual components of the Core and Containment Cooling Systems the components which make up the system i.e., instrumentation, pumps, valve operators, etc., are tested more frequently. The instrumentation is functionally tested each month.

Likewise, the pumps and motor-operated valves are also tested quarterly to l assure their operability. The combination automatic actuation test and monthly tests of the pumps and valve operators is deemed to be adequate testing of these systems."

with "On a monthly basis, correct alignment shall be verified for manual, power operated, or automatic valves in ECCS and RCIC System flow paths to provide assurance that proper flow paths will exist for system operation.

For the HPCI and RCIC Systems, this requirement also includes the steam flow path for the turbines and the flow controller position. This surveillance sequirement does not apply N valves that cannot be inadvertently misaligned such as check valves, or to valves that are locked, sealed, or otherwise secured in position. A valve that receives an initiation signal is allowed to be in a non-accident position provided the valve will automatically reposition in the proper stroke time upon receipt of the initiation signal. The monthly frequency of this requirement is based upon engineering judgement and is supported by procedural controls governing valve operation that ensure correct valve positions. This frequency is further supported by the Inservice Testing Program, which demonstrates system pump and power operated valve operability. This combination of automatic actuation tests, periodic pump and valve testing, and monthly flow path verification is adequate to demonstrate operability of these systems."

13. On page 133, Bases Section 4.5, change the last three sentences in the paragraph at the top of the page from:

"Between the monthly intervals at which the lines are vented, instrumentation has been provided in the Core Spray System and LPCI System to monitor the presence of water in the discharge piping. This instrumentation will be calibrated on the same frequency as the safety system instrumentation. This period of periodic testing ensures that during the interval between the monthly checks the status of the discharge piping is monitored on a continuous basis."

to n -

Attachmtnt 11 to JAFP 97 0359 SAFETY EVALUATION Page 8 of 18-

" Instrumentation has been provided in the core Spray System and LPCI System to monitor the presence of water in the discharge piping. This instrumentation is functionally tested monthly to ensure that during the interval between the monthly checks the status of the discharge piping is monitored on a continuous basis."

14. On page 177, Surveillance Requirement 4.7.A.4:

a) Change Surveillance Requirement 4.7.A.4.a from:

"The pressure suppression chamber reactor building vacuum breakers and associated instrumentations including setpoint shall be checked for proper operation every three months."

to-

"The pressure suppression chamber-reactor building vacuum breakers shall be checked in accordance with the Inservice Testing Program."

l Add new Surveillance Requirement 4.7.A.4.b:

" b. Instrumentation associated with pressure suppression chamber-reactor building vacuum breakers shall be functionally tested once per 92 days."

15. - On oage 178, Surveillance Requirement 4.7.A.5:

a) Change Surveillance Requirement 4.7.A 5.c from:

"Once each operating cycle, each vacuum breaker valve shall be visually inspected to insure proper maintenance and operation."

to "Each vacuum breaker valve shall be visually inspected to insure proper maintenance and operation in accordance with the Inservice Testing

' Program."

16. ' On pages 185 and 186, Surveillance Requirement 4.7.D.1:

a) Change the format of Surveillance Requirement 4.7.D.1 to llem and Frecuency as in 6.a above.

Att: chm:nt 11 to JAFP-97-0359 SAFETY EVALUATIEN Page 9 of 18 b) Change Surveillance Requirement 4.7.D.1.a from:

"At least once per operating cycle, the operable isolation valves that are power operated and automatically initiated shall be tested form simulated automatic initiation and for closure time."

to "1 tem Freouencv

a. The operable isolation valves that are in accordance with the power operated and automatically initiated Inservice Testing Program shall be tested for automatic or simulated automatia initiation and for closure time."

c) Change Surveillance Requirement 4.7.D.1.b from:

"At least once per operating cycle, the instrument line excess flow check valves shall be tested for proper operation.'"

to

" Instrument line excess flow check valves in accordance with the shall be tested for proper operation." Inservice Testing Program d) Change Surveillance Requirement 4.7.D.1.c.(1) from:

"c. At least once per quarter:

(1.) All normally open power-operated isolation va.ves (except form the main stream line and Reactor Building Closed Loop Cooling Water System (RBCLCWS) power-operated isolation valves) shall be fully closed and reopened."

to "c. All normally open power-operated in accordance with the isolation valves (except for main Inservice Testing Program steam isolation valves) shall be fully closed and reopened."

e) Change Surveillance Requirement "4.7.D.1.(2)" to "4.7.D.1.d" and u;1ange text from:

"With the reactor at a reduced power level, fast close each main steam isolation valve, one at a time, and verify closure time."

to

- AttCchmont 11 ts JAFP 97 0359 SAFETY EVALUATION Page 10 of 18 "ltam - - Freauency With the reactor at a reduced power level, in accordance with the fast close each main steam isolation valve, Inservice Testing Program one at a time, and verify closure time."

f) Change Surveillance' Requirement "4.7.D.1.d" to "4.7.D.1.e" and change text -

from: .

"At least twice per week, the main steam line power-operated isolation I valves shall be exercised by partial closere'and subsequent reopening."

to l

l " Main steam isolation valves shall be Twice per Week exercised by partial closure and subsequent reopening."

g) Delete Surveillance Requirement 4.7.D.1.e.

17. On page 197, Bases for 4.7 D, primary containment isolation valves:

Delete naxt to last paragraph regarding test of RBCLCWS valves,

18. On page 240, Surveillance Requirement 4.11,D.1; a) Change "Once/3 months" to "In accordance with the Inservice Testing _

Program" in Surveillance Requirements 4.11.D.1.b and 'd.

b) Replace Surveillance Reauirement 4.11.D 1.c with the following:-

" Verify that each valve (manual, power Once per 31 Days operated, or automatic)in the system

-flow path that is not locked, sealed, or otherwise secured in position, is in the correct position."

Att: chm 2nt ll to JAFP-97 0359 SAFETY EVALUATION Page 11 of 18 Editorial Corrections

1. On page 105, Surveillance Requirement 4.4.A.2, delete the first sentence reading

" Demineralized water shall be recycled to the test tank." and revise the second j sentence to read: " Pump minimum flow rate of 50 gpm shall be verified against a -

system head of .2.1,275 psig using demineralized water from the test tank."

2. On page 109, in the fourth line of the third paragraph, replace "...every..." with

" . . .e ve r. . . " .

3. On page 113, replace the phrase "Once/each operating cycle" with "Once/ operating cycle" in Surveillance Requirement 4.5.A.1.f.

4. On page 115a, replace ":" with a "." at the end of Specification 3.5.B.1. I

5. On page 122a, Specification 3.5 G.a, renutnber specification "3.5.G.a" as specification "3.5.G.1."

6. On page 122a, Surveillance Requirement 4.5.G 3, replace "...to insure they..," to

"... to ensure they...".

7. On page 133, reference to " calibration" of instrumentation is removed t.nd wording changed for clarification to reflect a change that should have been part of Amendment 37.

8. On page 133 at the end of the first paragraph, replace "... bases." with "... basis,".

- 9. On page 240, Surveillance Requirement 4.11.D.1, replace the phrase "Each operating cycle" with "once/ operating cycle".

11. PURPOSE OF THE PROPOSED CHANGES GeneralIncorporation of ASME Section XI This proposed TS amendment incorporates the requirements of the NRC approved version of the Section XI ASME B&PV Code (Reference 1) for inspecting and testing of ASME B&PV Code class 1,2, and 3 components. The purpose of this change is to eliminate unnecessary testing at power, consistent with the Nuclear Regulatory Commission policy (Reference 2), by consolidating portions of the Technical Specification surveillance test program, inservice Test Program, and Weld and Support Inservice inspection Program. The changes will assure adequate testing for operability while eliminating component wear due to excessive testing.

Attachmont ll to JAFP 97-0359 SAFETY EVAt.UATION Page 12 of 18 i

10 CFR 50.55a(f) requires that the plant Inservice Testing and Inspection Programs be i revised periodically. The revised programs must use, to the extent practicable, the testing requirements contained in the latest edition and addenda of the ASME Code that is in effect 12 months prior to the revision. The current inservice Testing Program was I developed to meet ASME Section XI,1980 Edition through Winter 1981 Addenda, it will be revised for the third inspection interval (currently scheduled to begin September 1996). The wording of the proposed Section 4.0.E is general enough to accommodate changes to the inservice test program without requiring future TS changes. The proposed testing program for pumps and valves follows the requirements of ASME Section XI, Paragraph IWP 3400, " Frequency of inservice Tests," and Paragraph IWV-3400, " Inservice Tests, Category A and B Valvas." in addition, testing program also follows the guidance of NRC Standard Technical Specifications (Specification 5.5.7) and the NRC Standard Review Plan 3.9.6, " Inservice Testing of Pumps and Valves,"

which states in part, "The pump and valve test programs are acceptable if they meet the requirements for establishing reference values and the periodic testing schedule of IWP 3000 and IWV 3000, respectively, of Section XI of the ASME Code. The allowable ranges of inservice test quantities, corrective actions, and bearing temperature tests for pumps are established by IWP-3000 and IWP 4000. The pump test schedule in the plant technical specification is required to comply with these rules."

This change replaces the monthly Technical Specification surveillance requirement for l pumps and valves with the James A, FitzPatrick ASME B&PV Section XI Inservice Test Program (Reference 3)in a manner consistent with the Standard Technical Specifications (STS) (Reference 6). This change also revises other Surveillance Requirements to be consistent with the requirements of ASME Section XI(e.g.,

methodologies for determining reference data, acceptable calibration frequencies, testing of specific parameters, acceptance criteria, etc.). The effect will be to eliminate unnecessary testing of safety related pumps and valves, particularly during power operation.

Editorial Corrections Changes identified in Section I of this amendment submittal as editorial changes can be grouped as:

1. Typographical / Punctuation Corrections The correction on page 115a will clarify the sentence by correcting the punctuation.

Attachmtnt ll to JAFP-97-0359.

SAFETY EVALUATION Page 13 of 18

- 2.- Editorial Changes Editorial changes have been made that clarify the Technical Specifications. They include clarification of the source of demineralized water for test of Standby Liquid Control pump testing (page 105), correction of a typographic error (page 109), _ 1 improvement of word usage (pages 113,122a,133, and 240), and correction to  !

numeration (page 122a). {

3. Correction of Bases (page 133) to reflect an earlier Technical Specification Amendment 1

Amendment 37 was issued on June 14,1978 and addressed, in part, the '

replacement of " keep-full" instrumentation ', .Jsure switches) with level switches on the high point vents on core spray and RHR (LPCI mode) discharge lines. The changes to Surveillance Requirement 4.5.G.4 reflected that the level switches do not require calibration. However, changes to the associated Bases on page 133 l were overlooked. The changes to Bases page 133 provide clarification.

L l

111. SAFETY IMPLICATIONS OF THE PROPOSED CHANGES Incomoration of ASME Section XI This amendment replaces the existing Technical Specifications Surveillance test requirements for pumps and valves with the requirements and criteria of ASME Section XI. This revises the testing frequency of pumps and valves to be consistent with

-ASME Section XI. This change is both administrative and technicalin nature. The replacement of multiple individual test requirements with a single requirement (Section 4.0 E) is an administrative change which has a negligible impact on plant operations and safety. The extension of the specified surveillance intervals from monthly to quarterly is a technical change.

Reactor Core Isolation Cooling (RCIC) system pump and valve testing (which is not part of the Inservice Testing Program) is also changed from monthly to once per 92 days.

This makes RCIC testing consistent with ASME Section XI testing of ECCS.

The FitzPatrick Technical Specifications contain, in part, monthly pump and valve surveillance test requirements for the following systems:

• Standby Liquid Control System (4.4.A)

• Core Spray System and Residual Heat Removal System (4.5.A)

• Containment Cooling (4.5.B)'

• High Pressure Coolant Injection (4.5.C)

• Reactor Core isolation Cooling System (4.5.E)

• Emergency Core Cooling System - Cold Condition (4.5.F)

Attachmtnt 11 to JAFP-97-0359 SAFETY EVALUATION Page 14 of 18

• Primary Containment isolation Valves (4.7.D)

• Pressure Suppression Chamber Reactor Building and Pressure Suppression Chamber Drywell Vacuum Breakers (4.7.A.4 & 5) e Emergency Service Water System (4.11.D)

These Technical Specifications generally require that pumps and valves be tested once per month. These monthly surveillance tests (i.e., a pump functional test and a valve stroke test), demonstrate system availability by operating the starting circuits and verifying proper equipment operation. They are replaced by the requirements imposed by the new Surveillance Requirement, 4.C.E (except for RCIC), which incorporates the FitzPatrick inservice testing program, and will result in a quarterly testing cycle in place of the existing monthly tests. Retained are the pump functional tests which demonstrate punip hydraulic performance by confirming an established discharge flow rate or discharge pressure. These tests and tests on other components (e.g., injection line testable check valves) have been revised to require quarterly testing. RCIC pump-

. functional tests and RCIC system motor operated valve testing has been revised to quarterly which is consistent with ECCS system testing and Standard Technical Specifications (Reference 6). A monthly verification is being incorporated to check proper valve position of valves that are not locked, sealed, or otherwise secured in position to provide assurance that a proper system flow path will exist for system operation.

A review of the FitzPatrick FSAR and the Technical Specifications indicates no design basis licensing criteria which would preclude surveillance test extension.

In the late 1960s General Electric (GE), used simplified probabilistic techniques to establish a logical basis for both surveillance test intervals and the allowable outage times for BWR technical specifications. GE Report APED-5736 (Reference 5) and a 1968 article from the magazine Nuclear Safety (Reference 6) provide an in-depth discussion of these modeling techniques. These two documents were used as the rationale for the Bases Sections of the FitzPatrick Technical Specifications for the test intervals specified. These studies established the connection between system availability as a function of f ailure rates, repair times, and the duration between operability tests. They concluded that frequent system testing would provide greater assurance of system operability since the likelihood of detecting a component suffering from degradation prior to failure was increased.

These studies did not recognize the reduction on system availability due to the fact that a system is consiaered unavailable while being tested in a mode that prevents automatic operation. A trade-off exists between the confidence in system operability due to frequent testing and system unavailability due to testing. Also, this approach did not recognize that a component which is repeatedly tested would experience further wear and degradation compared to a component which is in a static condition awaiting operation.

Att:chmInt ll to JAFP 97-0359 SAFETY EVALUATION Page 15 of 18 Following issuance of the FitzPatrick Operating License, both the Standard Technical Specifications (STS) and the ASME Code were revised tc require quarterly pump and valve testing. These changes were based, in part, on concerns for accelerated component aging due to excessive testing bnd on a better understanding of the {

relationship between test frequency and component / system availability. These changes I eliminated unnecessary monthly tests which are a burden on plant personnel and result in unnecessary additional wear on the components and equipment in the safety systems, and also reduced the risk of plant transients associated with testing at power.

A reduction in testing would, therefore, provide the benefits of reducing system unavailability and the associated possibility of a plant transient during such testing at power and reducing component degradation due to extensive testing and the need for down time during component maintenance. Additionally, the ASME tests measure changes in pump and valve performance. Degradation can be detected and corrective action (i.e., further testing, repair, etc.) implemented to provide continuous assurance l that saft y equipment can fulfi!! their intended functions.

The proposed Section 4.0.E is consistent with the STS (Reference 6) for the requirement that the Technical Specifications take precedence whenever they are more stringent. However, the proposed TS Section 4.0.E differs from the STS in that the proposed Section 4.0.E allows deviations from the ASME Section XI code where relief l

has been granted by the NRC. The STS does not address the mechanism to obtain relief. This deviation reflects current practice and is consistent with 10 CFR 50.55a.

Editorial Corrections Various editorial or administrative changes to pages which were the subject of this amendment submittal are raade to improve the consistency and clarity of the Technical Specifications. These have no adverse safety significance.

IV. EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION Operation of the FitzPatrick plant in accordance with the proposed Amendment would not involve a significant hazards consideration as defined in 10 CFR 50.92, since it would not:

1. involve a significant increase in the probability or consequences of an accident previously evaluated.

The changes identified in this proposed amendment revise surveillance testing for various systems based upon the Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code. None of these changes involves a hardware modification to the plant, a change to system operation, a change to the manner in which the system is used, or a change in the ability of the system to perform its intended function.

Att: chm:nt il to JAFP 97 0359 SAFETY EVALUATION Page 16 of 18 The use of Section XI of the ASME B&PV Code as a basis for establishing surveillance testing and acceptance criteria will not alter existing accident analyses. This has been acknowledged and accepted by the NRC in the Standard Technical Specifications. The change to surveillance testing frequencies reduces testing at power, increases the availability of systems important to the mitigation of a DBA, and minimizes component degradatior, due to excessive testing. The ASME B&PV Code,Section XI testing tracks component performance allowing identification of component degradation and the code specifies that if a pump parameter enters the alert range, then the testing frequency is doubled until the cause of the degradation is determined and the condition corrected. Similarly, if a valve stroke time degrades, the valve testing frequency is increased to once per month until the cause is determined and the enndition corrected.

The editorial changes are strictly non technical in nature with no effect on existing analyses. They clarify the Technical Specifications by improving the legibility of this document.

2. create the possibility of a new or different kind of accident from those previously evaluated.

l The proposed changes involve no hardware changes, no changes to the operation of the systems, and do not change the ability of the systems to perform their l intended functions. The use of ASME Section XI as the basis for testing involves the same testing alignments and practices previously used as part of either the IST program or Technical Specification Surveillance Requirements. The editorial changes have no effect on plant practices.

3. involve a significant reduction in the margin of safety.

There are no hardware modifications, changes to system werations, or effect on the ability of systems to perform their intended function associated with the proposed changes. The proposed changes to reference pump and valve testing to Section XI of the ASME B&PV Code and remove individual Surveillance Requirements in the Technical Specifications does not relax any controls or limitations, The resulting reduction in test frequency, while reducing the possibility of detecting a degraded component prior to failure is offset by the increased availability of systems important to plant safety and an associated reduction in component wear and degradation due to excessive testing.

Additionally, the ASME testing program evaluates components for degraded performance and willidentify such degradation early. There are no safety margins associated with the editorial corrections.

Att:chment 11 to JAFP 97-0359 SAFETY EVALUATION Page 17 of 18 V. IMPLEMENTATION OF THE PROPOSED CHANGES Implementation of the proposed changes will not adversely affect the ALARA or Firc Protection Program at the FitzPatrick plant, nor will the changes impact the environment. The results of these changes are expected to reduce the occupational

- doses to plant personnel since it e number of tests performed in radiation areas will be -l reduced. The proposed change will not change the testing process currently in place to meet ASME Section XI requirements and therefore can have no impact on the Fire Protection program or the environment.

VI CONCLUSION THs change, as proposed, does not constitute an unreviewed safety question as definod in 10 CFR 50.59. That is, it:

1. will not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report;

2. will not increase the possibility for an accident or malfunction of a type different from any evaluated previously in the safety analysis report; and

3. will not reduce the margin of safety as defined in the basis for any technical specification._

The change involves no significant hazards consideration, as defined in 10 CFR 50.92.

Attachm:nt ll to JAFP-97-0359 1 SAFETY..EVALUATl3N Page 18 of 18 Vil; REFERENCES

1. . ASME Boiler and Pressure Vessel Code,Section XI;-1980 Edition through Winter

-1981, Articles lWP and IWV.

2. < SECY-88 304, " Policy issue Regarding Staff Actions to Reduce Testing at- ,i Power", dated October 26,1988. "

3.- Inservice-Testing Program for James A. FitzPatrick Nuclean Power Plant, Second _

I Inservice Interval, Revision ~4, dated May 1,1991.- I i.

4.. APED 5736, " Guidelines for Determining Safe Test intervals and Repair Times for  ;

Engineered-Safeguards," dated April.1969.  !

i

( 5.1 " Reliability of Engineered Safety Features as a Function of Testing Frequency,"

Nuclear Safetv Vol.= 9, No. 4, July - August,1968.

. ~ 6. NUREG-1433, " Standard Technical Specifications _for General Electric Boiling _

Water Reactors (BWR/4)", Revision 1, dated April i995.-

7. _ NYPA letter, J. C.' Brons to NRC, dated November 20,1989 regarding definition of the terms Demonstrate and Verify for the Technical Specifications (JPN 076).

8. NRC letter, D. LaBarge to J.C. Brons, dated January 3,1990, transmitting Technical Specification Amendment 148.

9. James A. FitzPr. trick Nuclear Power Plant Updated Final Safety Analysis Report, Sections 4.8; 6.0, and 9.7.1.

10. James A; FitzPatrick' Nuclear Power Plant Safety Evaluation Report (SER), dated.

November 20,1972,= and Supplements.

, p .-

AttschmInt til to JAFP-97-0359 PROPOSED TECHNICAL SPECIFICATION CHANGES ASME SECTION XI SURVEILLANCE TESTING Me.RKUP OF TECHNICAL SPECIFICATION PAGE]

(JPTS 93-003) 1 New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR 59

. JAFNPP ,

TECHNICAL SPECIFICATIONS TABLE OF CONTENTS PARA 1.0 Definitions 1 LIMmNG SAFETY SAFETY LIMITS SY1 TEM.SEITINGS 1.1 Fuel Cladding integrity 2.1 7 1.2 Reactor Coolant System 2.2 27 SURVEILLANCE 3 );

LIMITING CONDmONS FOR OPERATION REQUIREhENTS 3.0 General 4.0 30 3.1 Reactor Protection System 4.1 3 l 3.2 Instrumentation 4.2 49 A. Primary Containment lacistion Functions A. 49

8. Core and Containment Cooling Systems - B. 50

, initiation and Control C. Control Rod Block Actuation C. 50 D. Radiation Monitoring Systems - Isolation D. 50 and initiation Functions E. Drywell Leak Detection E. 53 F. Feedwater Pump Turbine and Main Turbine Trio F. 53 G. Recirculation Pump Trip G. 53 H. Accident Monitoring instrumentation H. 53

l. 4kV Emergency Bus Undervoltage Trip 1. 53 ,

J. Remote Shutdown Capability J. 54 3.3 Reactiwty Control 4.3 88 A. Reactivity Limitations A. 88

s. Control Mods s. 91 C. Screm insertion T'unes C. 95 D. Reactivity Anomalies D. 96 3.4 Standby Liquid Control System 4.4 105 A. Normal Operation A. 105

8. . Operation With inoperable Components 5. 106 C. Sodium Pentaborate Solution C. 107 3.5 Core and Containment Cooling Systems 4.5 112 A. Core. Spray and LPCI Systems A. 112

8. Containment Cooling Mode of the RHR B. 115 System C. HPCI System C. 117 D. Automatic Depressurization System (ADS) D. 119 E. Reactor Core Isolation Cooling (RCIC) E. 121 System Amendment No. * *^ * * ' * * * * ^^ "" " -997-A

- . - . - - - . < _ _ . . . . - . - - - - - - - . - - . - ~ . _ - - - - - . - . _ _

- JAFNP? ,

~

3.0 Conhnued 4.0 Conhnued D. Entry into an OPERATIONAL CONDITION (mcde) or other that a Survedance Requwement has not been pedormed The speched condition shaN not be made when the constioas for the ACTION requwements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to Limshng Condition for Operation are not met and the associated pemut the completion of the survedance when the aNowable ACTION requires a shutdown if toy are not met within a outage time Erruts of the ACTION requirements are less than 24 anared time interval Entry into an OPERATIONAL hours. Survetlance requirements do not have to be performed i

CONDITION (mode) or specilled condelon may be made in on inoperable e=W accordance with ACTION .+3 ' __e when coniormance to them permits continued operation of he facety for an unRmsted D. Entry into en OPERATIONAL CONDITION (mode) shaN not be l period of time. This provision shat not prevent passage through made unless the SurvelRance Requwemone(s) associated with the OPERATIONAL CONDITIONS (modes) required to comply with Umiting Condemn for Operation have been pedormed withm the ACTION requirements. Exceptions to those requkements are appecabic surveisance interval or as otherwise spec.1 This

stated in the indvidual aparaicasinns. provision shen not prevent passage through cr to Operational Modes as required to compty with ACTION Requwements.

E. When a system, subsystem, train, component or deuce is -

I delsmined to be inoperable solely harasema its emergency poner source is inoperable, or scioly hacanssa its normal power source 1 is inoperable, it may be considered OPERABLE for the purpose \

of satisfying the ge6c._6 of its appecable Limbing Conselon ^3 5 4 _' 4 AW M g- -f l

for Operation, provided. (1) its correcpondng nonnel or emergency power source is OPERABLE; and (2) as of its redundant system (s), subsystem (s), train (s), component (s) and { g),() , g c,o ,o y ,,o y j; 3 device (s) are OPERABLE, or ukewise satisfy the respirements of this specifirmainst _ Unless both condelnns (1) and ;2) are satisNed, the unit shes be placed in COLD SHUTDOWN wiQin o ed ) 44 6 3o bh /

I' the fogowing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This specincation is not apr4icable when in Cold Shutdown or Refuel Mode.

F. Equipment removed from service or declared inoperable to i j comp 6y with required actions may be retumed to service under administrative control srJeb; to perform terling required to demorstrate its operabihty or the operabNity of other equipment This is an exception to LCO 3.0.B.

Amendment No. %, 1/ 4, 1/8, 227 30a

JAF9ePP 3.0 B&SES A. This specification states the mM et each W D. Canunued in tenne of stelined OPERATIONAL CONDfTION knodel and is provided to doensees speelAssBy when each specificoden is the status of the plant hofere or after an OPERATIONAL I'

. appEcolde. CONDITION emedel change. Therefore in this case, entry into an OPERATIONAL COMOITION imedel er other armas a

8. This specNication elefines Wiese condelens necessary to conde6en sney be mode in accordance with the provisions of I I

cere= cesnpEence with the sanns of an induidual Umising the ACTION requirements. The prowessons of this :;::r-:= ion Condden for Opasselon and esseelseed ACTIOff seguirement. should not, however, he interpreeed as endorsing the fadure to esercios good pectice in restenne myseenes or components to 4 OPERABLE statutb hofere startup. ,_st-C. This specincetion dsEnessee Wie ACTION to be taken for ci,cu,,,etences not 4,ece, ,,e.ided for b. Wie ACnON

} .

rue.psians to this prowielen niey be snede for a simited number  !

statesnents and whose occurrense wouAd wistoso the intent of a the W Under the tenues of SpareAlemale= 3.0, the of specificeelens when startup with inoperoide espapment  !

facWty le to be placed in COLD SHINDOWff wipiin the would not aNect plant safety. These ear.pa.ans are stated in feBowing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. It is esonened Wiet the unit is brought to the ACTION seseements of the approprisee :;::=-: :': .

the seguired OPERATIONAL COfENTION istedet wishin the seguired simies by pompey inteiseine and conving out she E. This armeiseania= dsEneseos what additional conessens must appropriate ACDON steemmer;t. he sosiefied to pensult aperation to continue, ceneistent with the ACTION statenients for pouwer sources, when a normal er 4 This _;: 7 :": . provides shot enery ines are OPERASLE esnergency power eeurce is not OPERASLE. It specifscaNy {

D.

pehlbits opersaien when ene dwooien is inoperaide because its ,

COfENTION tunealot sumust he made with del she fim complement of seguised myseesne, espdposent er components nennel er emergency power source is inoperable and a OPERAeLE and ibl et scher paramotors as speciAnd in the synese, subsyseem, erein, component er device in another (

~

umhing Candleiens for Operesien being nest without regard for eBwision is inoperehts for anseher reason y -

, eBoweben devissions and out of sendce powissens conseined in ,

The provielens of this W permet the ACTION C em ACT90N senemments. statesnents associeged whh indwidual systems, subsystems.

The intent of this previelen is to insure shot facSty opereuen is erame, components er devices to be consessent with the ACTION seasement of the =amaa=*ed electrical power source.

not inielmeed with eithev required equipment er systems .

It aEeurs opereeien to be gewerned by she rime inoperehte er other Emits being exceeded. CompEence with ACTION g1 a r_- shot pennit continued operosion of the faclety for an unsmised period of time provideo sa ecceptable level of setety for canonued opereeien wished the $W to 30c. (T4 7 neosso Awwi Amendment No. g, % -+84-- ..

Pm 3hb )

U 306

- . - - - - - - - - - - - ---.~ -- - - - - - - - ..- - - - - - - - - -

, t I

JacNPP r i

l 3.0 BASES - Continued l

E. Continued E. Continued i

limits of the ACTION statement associated with the Limiting As a further example, Specification 3.9.A. requires in poet that i

Condition for Operation for the normal or emergency power two 115KV lires and reserve station transformers be available.

source, and not by the individual ACTION statements for each The Af' TION statement provides a 7 day out-of-service time j system, subsystem, train, component or device that is when both required offsite circuits are not OPERAKE. If the j

- determined to be inoperable solely h=eauma of the inoperability defenstion of OPERABLE were apphed without consideration of of its normal or emergency power source. Specification 3.0.E., au , subsystems, trains.

components and devices by the inoperable normal  !

For exasaple, Specification 3.9.A. requires in part that both power sources, both of the offsite circuts, would also be i emergency diesel generator systems be OPERA 8LE. The inoperable. This would dictate invoking the applicable ACTION ACTION statement provides for a 7 day out-of-service time . statements for each of the applicable LCOs. However, the 3

when emergersey dessel generator system A or 8 is not provisione of Specsfication 3.0.E. pernwt the time limits for l OPERABLE. If the definition of OpfRA8LE were appEed continued operation to lie consistent with the ACTION  !

without considermion of f;: A:^!:; 3.0.E., aN systems, statement for.the inoperoide nonnel power sources instead,  !

subsystems, trains, components and devices supplied by the provided the other speciJed conditeens are satisfied. In this  ;

inoperable emergency power source, diesel generator syraem case, this would mean that for one division the emergency A or B, would also be inoperside. This wondd aCctate inweking power source must be OPERABLE los must be the components ,

the applicable ACTION statements for each of the app 5calde suppEed by the esnergency power sourcel and all redundant Limiting Conditions for Operction. However, the previolons of systems, subsystems, trains, comrenents and devices in the i Specification 3.0.E. permit the time limits for continued other dwielen must be OPERABLE, or likewise satisfy i operation to be consistent with the ACTION statement for the f;::~-: ^1 . 3.0.E. ii.e., be cepetin of performing their design j inoperstdo emergency diesel generator system insteed, functions and hows an emergency power source OPERABLE).

provided the other specified conditions are satisfied. If they In other words, both emergency power sources A and 8 must are not satisfied, shutdown is required in accordance with this be OPERA 8LE and eA redundant systems, subsystems, trains, specification. components and devices in both divisions must also be OPERABLE. If these condaiens are not satisfied, shutdown is i required in accordance wiWe Weis specification.  !

In Cold Shutdown and Refuel 94 odes Specsfication 3.0.E. is i not applicetde, and thus the individual ACTION statement for i I I each "Ppse.aia= Limiting Condiesen for Operation in these OPERATIONAL CONDITIONS imodes) snust be adhered to.

TYYT nfotidb GRdM PMei *SQc, Amendment No. pd -l%-

Soc

~

m j

JAFNPP 3.0 Bases - Contmuod o _

F. LCO 3.0.F estatsehes the ailowance for restonne

( equiprnent to service under administrative controle when it I has boon removed froen service or doctored inoperable to i

comply with required actions. The solo purpose of 4ss Specification'is to provide en ==earaiari to LCO 3.0.8 to asow testing to demonstrate: del the operabi5ty of the equipment being returned to service; er (14 the operaietty of other equipment.

The admmistrative controis ensure the time the equipment j is retumed to service in confect with the requirements of k the required actions is hmited to the time shmolutely l l necessary to perform the agowed testing. This Specification does not provide time to perform any other preventive or corrective snaintenance.

An example of demonstrating the operabikty of the equipment being returned to service is roeponing a g containment isoletfon velve that has boon closed to comply I

l with the required actions and must he reopened to perforrn f .

the testing.

l l

An example of demonstrating the operal6ty of other equipment is taking an inoperstdo channel or trip system out of the tripped condtion to prevent the trip function frorn

) occurring during the perfonnance of testing on another

(

)

channelin the other trip system. A similar example of demonstrating the operability of other equipment is taking en inoperable chonnel or trip system out of the tripped condition to permit the logic to function and indicate the appropriate response during the performance of testing on another channel in the some trip system. 3pe I QTdvT nuov6Dff20rst pecg 30 eg Amendment No. 83r488r336 -4N--

@p

. t

, l l

JAFNPP l 4.0 BASES A. This specification provides that survedlance activities necessary to insure the Limstene Conditions for Operation are requirement wM be identehod als mi egion. An mM l met end will be performed during the OPERATk;NAL of en exception when the test " m twwal is nm opocsissed in i CONDITIONS Imodest for which the Limetint Conditiene for reguistions is the Note in SpeciNcmimi S.20, *Presrowy Operation are oppilceMs. Provisoons for additional Centenment Leekage Rees Testing Progren,* mfuch essesso i

surveillance actewities to be perfonned witt'eut regard to the "The povesione of Spacofication 4.0.5 de not apply to the i apphcable OPERATIONAL CONDITIONS Pwdeel are provids:1 test k ; : A speciNed in the Prisnwy Centeinseemit i in the individual SurvelEence Requiremera Leekage Rote Tesems Program." This micopteeriis papwided i i because the pogrom streedy includes powisions for extensson of intprvels. -

1 l

8. Specification 4.0.8 establiehos the limit for which the specified time interval for Survel Nonce Requirements eney bei C extended. It pennits en sNoweblo extenoien of the nennel This specsfication estehushes the failure to perform a surweenance interwel to facultate survedience schoshding and SumeMonce Reaguirement withm the eBowed surwelRence  !

consideration of plant operating conditions that may not be interval, defmed by the powisions of Specs 6ceteen 4.0.8, es suitable for conducting the surveillance to.g., troneient a condition that conostutes a feture to nueet the ,

I conditions or other ongoing summence w meintenance OPERASILITY requirements for e Limiting Condiesen for

. activities). It sloe powidos Hesdbluty to accessnedste the Operemon. Under the povimiens of this specification, lon;pth of a fuel cycle for sumomences that are perfanneel at systems and components are meoumed to be OPERASLE each refueling outage and are epocified with a 24 neonth when SumeMones Requirements hows been seasofectorty I' aurvedience :atervel. It is not intended that this povision be - performed within the speclNod dee' interval. h, used repostetNy as e convenience to entend surveieonce nothing in this provision is to be consensed as implying that interweis beyond thct specNied for aumomences that am not systeme er coniponents are OPERASLE when they are faand performed during refuehng outages. The limitatier of this w h to be inoperable silheugh sem sensating the Sumainence Requirements. Tids specNicosion else C.M specification is bened on engineering judgement and the that the ACTION requirements are appEceble when recogrwtion that the most probable result of any portcular ourwanenc being performed is the wenfication of SumelEence Requimments hows not boon completed wishen conformance with the Sunemence Rogsirmnents. The En* the ellowed numeMance interwel and that the time Enuts of

- Wie ACTION regdrentents egiply fran the poet in tinw it is on extension of the normel surveMonce interval ensures that identdied that a swweMonce hos not been perfenned and not the reliability confirmed by numeMonce activities is not i ficandy reduced below that obtained from the specNied at Ww h Wet the eRowed numel5ence was escoeded. I Completion of the SurweMones Requisement within the I surwellence interval. The saceptione to Specification 4.0.5 we W,oesi sunsemences for svhich the 25% extenoien of the elloweble outage time Emits of the ACTION requirements imavel specinal dose not apply. These s=-::; Le are resteros compilence with the requirements ait Specification l 4.0.C. However, this does not negate Wien fact Wiet the '

stated in the inspwidual Technical W. De We to % perfenned Wm numedience within the alknval requirements of regulations take precedence over the aumedience interwel, defined by the provimiens of k E:7 . Therefore, when a test interwel a,s Specification 4.0.8, was a violation of the OPERASILITY I

Taichnical

,,,,cifimi ir "Ithe -; " ^1 , the test interwel cannot be extended under the prowiesons of 4.0.8, and the survesuence requerements of a Limstmg Condetion for Opmention thet is  ;

subject to enforcement action. Further. the failure to Amendment No. ...... ... --- ,,

-- -- j S h 30r (u _a 3 )

l l

i

f

- JAFNPP I

4.0 BASES - Continued C. Coe tinued r.. Continued perform a survestance within the provissons of Specification 4.0.8 is a violation of a Technical Specification restumnent Surveillence Requirements de nog hows to be performed on and is, therefore, a reportable event under the requirements inoperable equipment because the ACTION requirements of 10 CFR 50.734aH2HiH88 because it is a condition define the remodel enesoures that apply. However, the f prohetzted by the plant Technical Specifications. Survedience Requirements hows to be met to demonstrate that inopwable equipment has been restored to OPERABLE

i status. .

) If the alloweble outage time limits of the ACTION .

LJ requirements are less then 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or a shutdown is

• required to comply with ACTION requirements, a 24-hour D.

enowance is provisied to permit a doisy in :.C . e.4 the This specification estabbshoe the requirement that aN i ACTION requirements. This provides on adequate time limit opphcable surveMonces must be met before entry into an 1 to complete Survedience Roguerements that hows not been OPERATIONAL CONDITION or other conre ition of operation performed. The purpose of this agowance is to permd the specsfied in the ApphcablIity statement. The purpees et this completion of a surveiEence before a shutdown is rogured to specsfication is to ensure that system and component comply with ACTION requirements or before other remodel OPERASILITY requeemente er peremotor limits are met measures would be required that may preclude completion of before artry into an OPERATIONAL CONDfTION or other a a surveillance, The basis for this sNowance 6 specified conehtien associated with plant shutdown so wen as etertup.

consMieration for plant som, adequete planning, availability of personnel, the time required to-perform the Under the provisione of this specrfication, the appbceblo survedience and the safety significence of the py in SurveNience Reguirements must be performed withm the completing the required survoeNonce. This provision also provides a tiene limit for the completion of Survedience specified survedience ir:tervel to ensure that the Limiting Requerements that become applicalde as a consequence of Conshtsons for Operation are met during initisi plant startup or f-:% -@ e plant eutage.

OPERATIONAL CONDITION imodel changes imposed by ACTION requirements and for completing Survoinence Requeroments that are applicable when an exception to the When a shutdown is required to comply with ACTION requirements, the prowissons of this specification do not requirements of Specification 4.0.C is allowed. If a surveillence is not completed within the 24-hour allowance, apply because this would deley placing the facitety in a lower i CONDITION of operation.

the time limits of the ACTION requirements are appbcable at that time. When,a surveillance is perfonned & the

24. hour allowance and the Sunminence Regurernents are not met, the time limits of the ACTION requerements are applicable et the time the survoisence is termeneted.

Amendment No.19. Si. St. ? ^^. ? S2. ? !3. 22? -3M- T 30DJ b a# b v 30d 20F J l - _ - - _ _ _ . -

I JAFNPP 4.0 BASES - Continued E. . This specification ensures that inservice inspection of applicability condition takes prece%nce over the ASME Boiler and components and inservice testing of pumps and volves Preseure Vessel Code provision which allows pumps to be tested up will be performed in accordance with a periodically . to 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after retum to normal operation. As another example, updated version of the FitzPatrick plant

• Inservice Testmg the Technical Specirc.t;0r. definition of OPERABLE does not g ant a Program" to comply with Section XI of the ASME Boiler grace period before a device that is not capable of performing its and Pressure Vessel Code and Addenda as required by 10 specified function is declared inoperable and takes precedence over CFR 50.55a. The plant program identifies classifications the ASME Boiler and Pressure Vessel provision which allows a valve required by 10CFR50.55a and Regulatory Guide 1.26. to be incapable of performing its specified function for up to 24 Request for relief from any of these requirements is hours before being declared inoperable.

provided in writing to the NRC and is not a part of these Technical Specifications.

This specificatien includes a reference to Technical Specification Section 1.0.T which defines the frequencies for performing the inservice inspection and testing activities required by Section XI of the ASME Boiler and -

Pressure Vessel Code and applicable Addenda. This reference is provided to ensure consistency in surveillance intervals throughout these Technical .

Specifications and to remove any rmbiguities relative to the frequencies for performing the required "mservk:e inspection and testing activities.

Under the terms of this specification, the more restrictive d*

requirements of the Techrucal Specifications take precedence over the ASME Boiler and Pressure Vessel &$

Code and applicable /.ddenda. For example, the 9 -

p g. '

requirements of Specification 4.0.D to perform surveillance activities prior to entry into an OPERATIONAL CONDITION or other specified Amendment No.

3Oh -

x ._ .__ ______ ,.

JAFNPP ,

8

• 3.1 LIMITING CONDITIONS FOR OPERATION 4.1 SURVEILLANCE REQUIREMENTS , 3.1 REACTOR PROTECTION SYSTEM 4.1 REACTOR PROTECTION SYSTEM -  !

< Anch::stuhtv: Anchcatubty:

i Applies to the wistrumentation and associated ds*veces which Appises to the survostlence of the instrumentation and essociated j initiate the reactor screm. devices which initiate reactor scram. .

Otgecteve: Oteactrve: -

j To assure the operability of the Reactor Protection System. To specify the type of fresquencY of survedience to be apphed to the I protection instrumentetson.

Saecification: Saeceiscatson. j A. The setpoents and menwnum number of instrument A. Instrumentation systems sheE be functionally tested and calitwated i channels per trip system that must be operable for sech as indicated in Tables 4.1-1 and 4.1-2 r::; :r.cf.

position of the reector mode swetch, shell be as shown in Table 3.1 1. TM w h of h mw pm pm @ h listed below shou be domeneersted to be within its limit once per i 24 months. Neutron detectors are enempt from reopense time  !

testeng. Each test shoe include et least one chonnel in each trip i sys*em. AE channels in both trip systems sheE be tested wethin I two test interweis. j

1. Reactor High Pressure 602-3PT-55A, 8. C, Di

• l l

2. Drywe5 High Ptoseure 006PT-12A, B, C, D) i

3. Reactor Water Level-Lew (L3) 002-3LT-101 A, B, C, Di

• l I

4. Mein Steam Line isolossen Velve Cleeure j j

(29PNS-80A2, 82, C2, D2)  ;

(29PNS-86A2, 82, C2, D2)  !

5. Turbine Stop Velve Closure 194PNS-101,102,103,104)  !  :

6. Turbine Control Valve Fest Closure 194PS-2OOA,8. C Di l  !

• 7. APRM Fiwod High Neutron Flum

8. APRM Flow Referenced Neutron Flum i  !

• Sensor is etwneneted from respones time testing for the RPS actuot" '

logic circuits. Response time testing and conformance to the test  !

acceptance criteria for the remainong channel components includes t ' l unit and relay logic. j i

Amendment No. 33 O bi ( Yrx! m04 ) '

30g k

f i

.. - - - _ _ . - _ _ -_-____-_--__._--_:_-_.__l

JAFNPP 3.3.C (cont'd) 4.3.C Icont'd)

The average of the scam insertion times for the ttwee 2. At 16-week intervals,10 percent of the opos3Me control l

2. '

fastest operabis contrei rods of all groups of four control rod dnwes sheE be scram timed abows 950 pois. The ses l rods in a two-by-two array shen be no yester then: control rod drives should not be tested each interval. l Whenever such scram time measurements are snens, an Average Scram evaluation shen be made to provede reasonable assurance Control Rod ,

that proper control rod dnwe performona is being Notch Poesteen Insertion Time ISacandal memsamed.

Ohaarved 46 0.361 38 0.977 24 2.112 04 3.764

3. The maxwnum scram insertion time for 90 percent 3. AN control rods sheE be detennsnod operable M --gay demoneerstang the scram discherge weiume [u[

overy h insertion of any operable control red shed not exceed dram and went welwearispersede when the scran test 7.00 sec. wutseted by placene the snede awelch in the SHUTDOWN poestion is perfonned as required by Table 4.1-1 and by verifying that the drain and went wolves: g q ~

Ife es. <epsmy  ;

Close in less then 30 seconds after recept of a sognef i

f. a. for control rode to screen, and L. Ye>r.kd oftA. Once (Le 3 I cN y s 4

~

Cycled LUy closcA

'^ " " b^* N b~

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w n,.'~:.e. r<6' t Re[wJ ~d ec(f n,kly ~Le fm- mya ,

s C J 4, elo,e wL coa p ,.t-t _ g, l'0' k cA<d <s L & Liff. '

c. -

l soGn of suonds u]vrI or Jiu5; <<aie

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98

- - .. .- .- -.~ . - - . . - . - - .. .. - . . . -. .-.. - -. - . . - - - - - . . . . ..

t JAYa . .

l 3.4 LIMITInc Co#01Tipus_rpa_9PERATigg 4.4 sytyE1.LrANCE_REQUlamswTs 3.4 gingepY L1041D_f0MTROL SYSTEM 4.4 STAMERY3 10uto_rggTmQL SYSTEM

&nglicability: Aprilsekl%Ity .

Applies to the operating status of the Standby Liquid Applies to the periodic testing requirements for the Control System. Standby Liquid Control System.

8 ObJtSilYe. .

t To assure the availability of a system with the To verify the operability of the Standby Liquid f

capability to shut down the reacter and malatels the control System. -

shutdown condittom without control reds.

Specifications Erecificati g:

A. Normal OmerAtles .

A. Norms 1 Operatl.a During periods when feel is is the reacter and The operab!!!ty of the Staedb T prior to startup from a cold condition, the LI 9eld Control System Standby Ligold Control System shall be operable shall be verified by performence of'the following tests except as specified in 3.4.8 below. This system g, ( A w se u S IC pq mucy g need not be operable when the reactor is la the [ M . @ least SSER agar man cold condition, all rods are in11y laserted and I Specification 3.3.A is met. p Cseelseralisedweer"-11herecycledtoe.ne)

.-. . .i y mi. - f,o. r.t. of c

r-r-D /dit e48 d-1~ --

y pm ,

1. shall he verified agalast a system head of .2 C A5 2'yng ,,3 ,, ,J b 1 '

j A ,375 pol g uSt, @ . .bda*** _ m W1rurmM O M f

.s"" " " W

%Y.de 2 t c.wfliiii 5 r.ti cN m Naamally initiate the system, except the C%c4 m(4, i emplosivs valves and

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N rnow 4-o lOlo Ammadment No ttfr-105

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8 i es > .

3 3]

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iw. Ill1iHid }in} [1 !! ii s t. , u e x'v r. .

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JM9epP A'.WS requirements are satisled at all concerarassons abo.e The relief waiwes in the Standby s ssgued Control System potect 10 wesght percent for a minunum enrichment of 34.7 atom the system pagung and peestowe W punaps, wbsch ase percent of B-10. c_ _ E- "i dessened for 1,500 peig, from overpaeosuse. The pressure relief welwes decharge back to the seensApy bguid Figure 3.4-1 shours the posessissable region of operasson on a control pump mar *== line.

sodsum pontaborate ankaaion welunee versus concentrasson ~

paph. This curve was developed for 34.7% ennched B-10' B. Oseratsen with inesordie Cameenents and a pumping rate of 50 syssi. Each point on this curve provides a seeinsmum of $60 pens of equivalent nasaural beron in Ordy one of two standby Inquid conesel pumgang crcusts is

. the reactor weseel upon ingscenen of SLC solusson. At a needed for operassen. If one circuit is inoperable, these is ne

=d eaa volusses of 2200 geRens, a weight concentrasson of imenedete threat to shuedoen capabihty, ased seeceer operassen 13% sodsum pensabersee, ennched to 34.7% boron-10 is asesy conennue diaries repairs. Assurance shot she semesung needed to sneet shutdoum seguirements. The mesmessusn syssent wiB perfessus its funchen is obtained by vessfying passip storaes volume of she solution is 4700 gesons w aiicle is the operabshty in the operskie circuit at doest deny.

not overflow volume in she St.C tank.

C. Seehum Pentaharane Schauen Baron concentration, isotopic ensichment of baron-10, solusson temperature, and volume ese chected on a frequency adeguese To guard agesnst pe=ry*=a===i, she mamann, sncludwig Wrt in to assure a high seemiulity of operasson of the system shoned it she pump sucasen piping,is kept at least 10*F above 2c-. wish sump operability indicates saturassen teniperseuse. Figure 3.4-2 showes the soeurasson ever --

temperseuse inclushng 10*F senergen es a functeen of sodiumi gger4 - _ $, tydesng ingdesguetpo afesept'if fy have =- pensaborate solussen concentrateen. Tank heater and heet

- - =

(pccurydd.4 0 -

t:acan, system a,e ,,oweded io assu,e czy _a .ish h,s The ordy practical time to test the Standby LMgued Control requerement. The set posess $ct the automatic actuasaon of the sank foseer asui host teacing system are estabisshed based on System is during a refuehng outage and by iniemeion frosn local -

stations. Because components of the systeen are checked the saluesen concentrasson. Teenperature and Augued level alarms for the sysessa annuncasse iri she control recm. f%suno perioshceEy as descnised above, a funcesonal test of she enews systeen en a frequency of sseere shen once overy 24 sseenehs is operatuisty is checked en a fresguanc, 30 assuse a high unnecessary. A test of empleeswo charges frossa one ' reheimhty of operacion af the syseesse should it over he segueed.

manufactunng beach is senede to assure that the charges are seassfactory. A contenuous check of the isnne circuit contanusty is provided by pilot lights in the control roosn.

Amendment wo. : . ::e es 6 109 -

JAFhN

• Iri sed (

3.5 (cont'd) 4.5 (cont'dl

b. Flow Mete Test - months ,

- spr.y -

shsE deirwer et leest 4,265 gym egemet a system heed correseenene to e reacter vessel m prenews groceer then  ;

or ogust to 113 pel eberre pnmery .

$Dp containment pressure.

c. ( /Orwelmodeh

d. Motor Operated Vohre

e. Core Sprey Hooder ap Insenacenesten Check Onceddoy Comesse Oncer3 menehs Test Oncer3 snenehn -

t f.

~

Logic Syseena Re6er to Tekte 4.2-2 [ ,l 1,

Functional Test I N  !

g. Testable Check (Tested for opershility l

< Velves any time the reacter is L

in the cold con 6 teen i exceeding 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if opershEity tests have not boon performed .

during the procedmg 31 i Amenefinant No. ^^. * 'a, w 233-113

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' 3.5 'ICont'd) 4.5 ICont'dl l E. Reacter Care lanission CoeEns 1R00 System E. Haacter Care leeinhan Ceedinqn IftOO Sveamet

1. The RCIC Systeer. sher be operette whenever there 1. ROC System seetmg shes he performed as fenews is irredeted fuel in the reacter vessel and the reactor provided a reacter steem suppfy is eveneMe. It i preneure is grooter then 150 pois and reacter caelent steem is not evenette et the time the survoinence  !

4 temperature is greater then 212*F encept from the test le schedu8ed to be performed, the test sheE he  !

time that the ROC System is mode or found to be performed wishes een days of continuous operonen  :

inoperatie for any ressen, centinued reacter power from the time steem hacemos eveilable.  !

operoglen is permisoitte during the m- :S.,7  !

~

days unions the system le mode operehle earter llagt Freenency gi provided that during those 7 days the HPQ System j. [

is operskie. e. " Simulate'dA$stematic Once por 24 heenthe ) i Actussen land Restert'l -

i l 2. If the en _* .._.^. of 3.5.E cannot be snet, the Test g 6sec 0] l I reacter shsE he pieced ire the caid condtion and i preneure lose then 150 pois within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. h. OpershiEty j- Oncohnen)th 6

3. Low power phyeles testing and reactor operator c. nesser Opereced Volve Operskulty {Oncehnenth Nk MA3 training shen be persnitted with inoperehte Y  ;

J

, compenants as specNieri tri 3.5.E.2 above, provided l

! . that reacter cosient temperature le s212*F. d. @ Rete Oncel3 monthe Q3 ' # _* 9 [

4 The RCIC system is not resguired to be operatie ,

s. Testotle Check Tested for'opereldty I i

during hydreesseic pressure and seekage teseing wish veeves any time the reactor is i

,e.eter comient tenperetures between 212*F and in the cold condiesen i 3OO'F and irredeced fuel in the reacter woosel +-n

_" , 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. if

{

provided e5 control rede are inserted. opershEty tes's howe i not been perfersned  !

egf [, f. t.egic System Once per 24 nAonths <j

pD Functional Test

~

s ___

, Autometic restart on a low water level sognet which I is M::;M to a high water level trip.

f

'I An one,nont No. M. "?. "". t - >

, 121 f f

L i

cl-mm fog <. /$ /

S. <

JAFNPP 3.5 (cont'd) 4.5 (cont'd) 066 I"'#'/"

, C -

RCIC pump shell deliver at feest 400 gpm for a system j gk [,y,[ d on head correspondog to a reactor pressure of 1,195 poig to 150 psig.

J g~)v gyl-

2. When it is determined that the RCIC System is inoperable et a time when it is required to be operable, t.w HPCI System shall be verified to be operable immedietely and deity thereafter.

Amendment No. 40, liS,

! I JAF90PP I

L 35(conr4 45 (conr4 I F. ECCS ColdCondson F. ECCSCoksConteson .

i 5 s

i 1. A miniseen of two sour preneure Esnargency Core swwenance of sie km preseme ECCS sysesens reemras ['

! by35F.1 anss3M.2 shes be as sosouss-coasne sesyssoms shes be operanse whenever

) arradiened tuas as h she summor, em sencear is in om '

j ooks coneson, and wask la being personness wah the 3, _ _ n . . . .,,,,, ,,,,,, ,,,, ,,, d 3 .,nso j

poenness sur eshiing the semmor veseed. an se saphes Core spray pump (s) and/or the RHR

• j pumpqu$. Ee6 Core spray pump shes aestver at

! 2. 4 minimum of one km pressee Emergency Com Inest 42gunagdnet a syneene heess l

L Cocene emeyssen shes he opuese whenmer Dst"g cosasponeng to a sensor weessi pseeswe grossar enessend tuss is h sie seactor, she sencear is h the then er ages so 113 pai above primary contWnment coks coneson, and no wak h behe personned wah C preemme. Ems RHR pump shsA ds5ver at Isamt j

the poteness Sor esinkg om sensor wesed. seio gpsn sessne a syssem head conosponene to a sensor wesent to primary conesinment moorentes

3. C-- 4 CoreCocengsesystemsmenot premmeeor > appsks.

! C -'

superus to im eparende presided shas sw eencear 2.

seen on e u ra p h u s venees head is removed, su msey is Gooded, em ComSpur IPCs nicear apassedh spena euse poos esses == semoved, sus en weser l 3. r one eachsheswee ommepsemasonpoos. seer Issuseasethenadashsenaeanceweh

& 3.so.C. issua is spesser eien or soms to saas a. whenever i

' the now psemeno Eccs subsystems are angned to e m m e sseessen p oca.

4- Wahem sagdomenesof 35F.1.35F.2,or35F.3 sion sumperidairesnesasons andas 4. Ches each shst vesy a minknum of 324 inches of operasore wah ou poseness sur denhg om sencear muser as meestse h she condenesse storaes Terms weses. nossore a teens one system to opersbee IC83) "h'"' 8" Com spray syneemM is asynd assue wapen 4 hans or enesmash seconday 88 8* 8***-

Coreshmens kesymy wamn ine ness a hours.

(d. (Jaa rua St %ys,s'a>ry ro**r <*:s 4 As.% (,see4enareL,.pcnegnr e94stordb eK gg ( 8ber-eesser,C) saf wt 444.is pers y)pse-7" t

\

t% e6er" LOCndb,14et4b :.sq. eyeg9rangsg fitunin9D en pes arscal, es aan vrst ee&decr E04' W '71084 #d t. Ydd, Ad'det.a,srgb RrY $

j W N o j , f . y dB , 1 [4 L d

• "Ohst ees4 spuy sysw,.r6),

t , _. . _ t

i as(conr.4 45 :conrd) l G. Masnienance of Fibed Dadurge Pipe G. Maineenance of fired Die $arge Pipe Whenever core spray subsystems, LPCI subsystems, HPCI, or The foRowing sunmEence requkements shes be assered to, in acsC are required to be opersbee, the ds&arge pping fram the

, purm dscharge d these systems to the last block wafve sher be order F) assure that the demerge piping of the core spray .!

ased. subsystem, LPCI subsystem, HPCI, and RCIC am ERed

1. Every mores prior to see teseng af sie LPCI seheystem Rom and aner the Mme Ihd the pump dedierge piping of the NPCI, RCIC, LPCI, or Core Spray Systems cannot be and com spray asheystem, the de@sege piping of these l mauntainedin a filled systems shsA tm wanted kom the high point, and weser

' sour observed.

i i

i i

t Amendment No- 468-122a

- f l  !

r l

l- JARIPP 3.5 (cont'd) 4.5 (cont'd) i t  !

j corwistion, that pump shell be considered inoperstdo for 2. T- ": 2.e any period where the LPCI subsys ~.ans or cose

1. purposes of satisfying C:?-:M: 3.5.A. 3.5.C, and 3.5.E. spray subsystems have not been meantained in a fiBod  !

condition: the discharge papng of the aHoceed suhoystem j j:

i ,

sheE be vented from the high poet of the syneem and j i water Roar observed. i

3. Whenever the HPCI or HOC System is lined up to take j suction from the condensate storage tank, the dischesgo j i piping of the HPCI or ROC shot be wented from the high

!; poent of the system, and weser flow observed on e

! montfey beeis. ,

! 4. The level swstches located on the Core Spray and HHR

< System discharge pipng high points wtuch monitor those l Iinoefo ' 'they are fuS sheE be functioneEy tossed '

[

l

each month. I

! U 4

! H. Averman Planer Linear Hast Generaman Raae IAPLHGRI H. Averapa Planer Lineer. Head Generasson Rats (APLHGRI i

j Dunng power operemon, the APLHGR for each type of fuel as Ths AF_HGR for each type of fuel as a function of average a function of amiel humaean and sworage pioner exposure sheE pioner exposure sheE be determened daily dunng reactor

. be wettun Iimets beood on applicetdo APLHGR limit welues operamon at z.25% reemd thorsnel power.

i which have been approved for the respectswo fuel and lettice i types. These values are specsfied in the Core Operating Limsts  ;

j Report. If at anyeime during reactor power operemon greater

• l then 25% of rated power it is decennsnod that the limiang ['

l value for APLHGR is being esscoeded, acteen sher then be

irutioted withen 15 rninutes to restore operosion to withun the presenbod limits. If the APLHGR is not retumed to within the l presenbod lensts within two (2) hours, the seector power shes be reduced to less then 25% of rated power within the next j four hours, or until the APLHGR is retumed to within the prescribed limits. .

l 1

t Amendment No. [ ,Jd,1 1/,yd,3gd,483-123  ;

[

I

1 i

i i  !

i' JAFfrP l

}

4.5 BASES }i The testing interval for the Care and Centeswnent Cootng The HCIC New rete is described in the UFSAR. The near roses to

. Systems is beood on e quantitative r.ai.histy ensfyase, industry be deEvered to the reeceer core for HPCI. the LPCI snede of RHR.

! procace, i f. . :-^, and practecetty. The Emergency Core and CS see booed en the SAFEfUGESTR LOCA eno6voie. The near li CoeEng Syseeme have not been designed to be fuBy testohle rates for the LPCI snodo of RHR and CS are essedilleI by a 10  !

during operation. For exemple, the core sprey final oduusesen percent reducteen from the SAFEfUGESTR LOCA enelysis. The 4 wolves do not open uneB s== rear presense has fasen to 450 pois: reducsono ete momed ase e sensiehety anneyeso aGammagLAtacame thus, during operceien even if feigh drywe5 presse e were hWE-83473GI pertenseed. for to paramoeore used in teso  ;

simusseed, the Anel volwoo would not open. In to caos of the SAFEfUGESTR analyse.  !

HPCI, outeenselc inieleelen during pourer operossen weedd result -

I

, in pumping cold weser into the seector vesnes which is not The CS ourwesence segunement inesudoe sn esoweneo fw eyseen  !

desirehle. lookege in,eddesere to Wes Asur rete required to be de5wesed to the [

'S reacter case. The look rees fresse the core sprey pipmg inside the  !

The systema wlE he autess==dramy sceusted once per ~l4 sseenehe. reactor but outsido the core shreesd is soeumed in the UFSAR and l In the case, of Wes Core Sprey Systone, condonomes storage tank indudes a known less of lose then 20 gysse fresse the 114 inch l

weger wM he pumped to ehm - - " as wanhr the demetor ent hele in the rose sprey T-host connoceen in each of the core morey heeder.f To the ;. - ,.1,^of:,of] the loops, and in des S leep, e potenesol edeseensi less of less then l

7 the and C :_ L,u c 40 sysse from a clemehes reper wheee senscoural weld covers ordy i iNfI  ! Indwidua[l --

Systeme - g; c:__  : _.h. sseeke up e 5JS et the ceceselesence of the pipe. Seeh of

- ef inekage acce he te -- .those idensdeed i

- e,erseers. e/" system - opeector.ooe.

y  :.=Q==

. : --- . f c.n.e.

1 2 _ _ ; ::. le " ,___ 4

.the each see stee wee and the core shroud. Therefore flow leet through the=e look sources does not cenerthuse to core cosEng. . li i and snoter ^~ ,._:2 The ^

each to their , _ r. --

[

autosnetit.  :*_. and tests of pennpo and ' f The surveimonce regsivements to ensure shut the 6scharge ppmg ,

I g valve is to te9d ng of toes of the case sprey. LPCI snede of the HHR HPCI, and MCIC l (systems.

Systems are Idled provideo for a wouel sheerwassen that weeer  !

flows from a high point went. This ensures that {

With cosnpenente er subsystems out-of-service, overeN core and i conesinment coesng reneheity is sneintained by verNving the -

4 operatenty of the remaining cesang oguipment. Coneeseent with

, W. desiniesen of operehse in section 4.o.C. demonstrete meano conduct a test to show verify sneens that the e==ar-sed

[ Aoa  %

surveMonce activities have lysen entiefectormy performed withwe g"4 j

) the specified time interval.

f)C l i

f I

Amendment No. P, a t=, r M 13'  !

4 i

-. . _ _ . __ _ _ _ _ _ _ __ . _ __ _ - _ l

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!"I i1 1i 1-lI f3$l!!all! h i

_ . _ _ _ _ _ _ _ - . _ . . . . _ _ _ _ . _ _ _ . _ . . _ _ . _ _ _ . . . ~ . - . . . _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ . . _ _ _ _ --

t JAF9FP i

I 3.7 (cert'd) 4.7 (cont'd) 4 -

i breaker is sooner enade operable, provided that the repair precedwo does not veelste pnenery contamsnent inemytty.

5. Pressure Suppresseen Chamber - Drywe5 Vacuum 5. Pressure Suppresonen Chamber - Drywe5 Vacuusn j; Breakers Breakers 1

l. a. When pnneery containneont insegnty is regaired a5 a. Each drywe5 suppreessen chamber wecuum breaker i dryweg suppreenien chamber wecuum beoekers shsE sheE he seescised through en opensne - cieseng cycle he operehis and poemened in the sugy caesed m er h;<.

, .posaien except during asseine and as specisind in 3.7.A.5.h below. .

i j h. One dryweE suppresseen chamber wecuum breaker b. When it is decennsned shot one vacuum breaker is i sney be non-hdy cieeed se long as it is desemained eseperahie Ier lugy closing when operability is i to be not sseere then 1

• epen as indicosed by the regered, the aposette breakers sheE he meercased 4

peession hghts. immediately, and every 15 days theseeleer until she inoperehle wolve has been resumed to nonstel senace. ,

M - & yt

c. One dryweg suppreseien chamber wecuusn breaker i

sney be detonseined to be inoperable for opening.

c. [Once ser 24 MJnech war === breaker volve sheE he weemeEy anopoceed to insure proper

/

sseeintenance end ; - _p

d. Deleted (pg( d. A leek test of she drywe5 to suppreeseen chamber structure sheE he cardM ence per 24 sseenehs; she acc.panum leek reso is 50.2a in. weserAsein,

/gf f

over a 10 seein pened, with the drywe5 at 1 paid.

I 1

Amendment No. !3', !"2 ,232 178

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

t

l

' 3.7 (cont'd) 4.7 (cont'd)

c. Secondary contamment capebility to mentain a 1/4 in. of water vacuum under calm wind condmons with a fator train flow rate of not more then 6.000 cim, sheE be demonstrated once por 24 months

^

prior to refueling.

D. Pnmary Cantainment lealahan Valves D. Primanr Cantainment laalaban Vahms Whenever primary contomment integnty is rogured por 1. The pnmery contamment isoletion veiwes surveiEence 1.

3.7.A.2, contomment isolomon volves and all "wietrument shall be performed as foEows: -

line escess flow check volves shen be -:- :r:, except IS jt

a. por 24 months operable isoistoon volves as ,::5:f in 3.7.D.2. The contomment vont and purge valves shen be ionsted to opening angles less then or that are power coereced and autr cc _1: ; inseasted 1 equel to that specsfied below: sheE be tested for sonulated automatic inescon and for closure time.

htaximum Omeninn Angis 7W Vahre Number 27AOV-111 40' b. Spe- 24 months. _ line excess flow check volves sheE be tested for proper ,

27AOV-112 40' 40' operation.

27AOV-113 p 27AOV-114 50'

• 27AOV-115 50*= c. M once per quartJer- ~

27AOV-118 27AOV-117 50' 50'

] D .

(1. All normally open power-operated isolation a:id #

27AOV-118 50' b M [g imecept for the mein ser or Budding Closed Loop

.4 _

-o System (ft9CLCWS) power-:n _^_Q bew h

([7 vsNost sheB Bio fully closed and ee-u J.

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F 7 tnserf b

Amendment No. ?"i, 173, * ^", 2?'" 489-1M 185

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0.7 BASES (cont'd) i i r

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j The mein steem line imeleteen valves are functeone5y tooted on ,

e more frequent interval to estehlish a high doyee of l j j

.reliesshty. i 1 [

4 The pnmery contamment is penetrated by severei emell

[

diameter instrument Enos connoceed to the reactor coolant system. Each instmment line conteens e 0.25 in. restricang

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onfice inside the primary containment and on escess flown l check volve outside the pnmery contenment. t

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t i'

The ftSCLCWS volves are adM from the guetterly survenence requirements becoues closure of these volves wiE siuninete the coolerA fleur to the dryweE air and recirculopon j

-c; :sor coaters. without coehng water. the drywes air  ;

and equipment temperature wiB mereses and may cause damage to the equipment dunne nennes pient opersoons. .

l 1

j Therefore, testang of these volves would only be conducted in l

( the cold condibon.  ;

A list of containment isoletson velves, encludmg a brief i description of each wolwe is included in Sechen 7.3 of the i updatsd FSAR. _

i

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2

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I f

Amendment No. t Si, t M. M2 fi 147

- . _. . .- . . . -- -. _ .. .. - ._. .- . __ _. .l

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

t JAFNPP - ,

i 3.11 (cont'd) 4.11 (Cont'd) i D. Emergency Sarwico Water System D. Ennersency Service Weser Sussom t

1. To ensure adequate equipment and ores cochng, both ESW 1. SurweiEence of the ESW system shen be perfemed as  !

j systems shen be operoMe when the requirements of feBows: } l specdication 3.5.A and 3.5.8 must be setsofied, except es  ;

h i specified below in W 3.11.D.2. h i

s. Simulated Automatic Once overy 24 moinha l Actuation Test t Qou<r c-)  ;

- b. Flow Rate Test - Each montheN Esw p shen desver et loost 1500 gym to its  !

I i respectwo loop. The pump ,

total doweloped head shsE be l

grosser then or aquel to the i

! corresponding point on the

' pump curve, reduced by o (

memimum of 7%, for the j measured flow.

(s*c 6 )

c. AGp caw oncenonth w l t

l

d. Motor Operated nsEn Q j l -

veh,es i

i

-j

Amendment No. 71, t2t 222, N

< 240 j i

- Attachment lll to JAFP 97 0359 MA%KUP OF TECHNICAL SPECIFICATION PAagg INSERTS (Pg.1 of 3) latetLA E. Surveillance Requirements for inservice testing of components shall be applicable as follows:

l

1. Inservice testing of pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(f), except where specific written relief has been granted by the NRC pursuant to 10 CFR 50, Section 50.55a(f)(6)(i). The inservice testing and inspection program is based en an NRC approved edition of, and addenda to,Section XI of the ASME Boller and Pressure Vessel Code which is in effect 12 months or less prior to the beginning of the inspection interval.

2. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the insarvice testing activities required by the Code and applicable Addenda shall be applicable as defined in Technical Specification 1.0.T.

3. The provisions of Specification 4.0.B are applicable to the frequencies specified in Technical Specification 1.0.T for performing inservice testing activities.

4. - Performance of the above inservice testing activities shall be in addition to other specified Surveillance Requirements.

5. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

Insert 8 Verify each valve (manual, power operated, or Once per 31 automatic) in the system flowpath that is not Days locked, sealed or otherwise secured in position, is in the correct position.

r g ~

l Attachment lll to JAFP 97-0359 MARKUP OF TECHNICAL SPECIFICATION PAGES l INSERTS (Pg. 2 of 3)

Insert C in accordance with the inservice Testing Program, insert D periodic testing in accordance with the IST Prog.am is adequate to detect if degradation has occurred, ' Valves in the system flowpath are verified to be in the proper position on a monthly basis. This requirement does not apply to explosive valves or to valves that cannot be Int.dvertently misaligned, such as check valves. Verifying the correct alignment of manual, power operated, or automatic valves in the system flowpath provides assurance that the proper flowpath will exist for system operation The monthly frequency is based on engineering judgement and is supported by procedural controls governing valve operation that ensure correct valve positions, insen M Flow Rate Test - The RCIC pump shall deliver at Once per 92 least 400 gpm against a system head Days corresponding to a reactor vessel pressure of 1195 psig to 150 psig.

Attachment lli to JAFP 97 0359 MARKUP GF TECHNICAL SPECJEICATION PAGEft INSERTS (Pg. 3 of 3)

I insert F On a monthly basis, correct alignment shall be verified for manual, power operated, or automatic valves in ECCS and RCIC System flow paths to provide assurance that proper l flow paths will exist for system operation. For the HPCI and RCIC Systems, this l requirement also includes the steam flow path for the turbines and the flow controller L position. This surveillance requirement does not apply to valves that cannot be i-5 inadvertently misaligned such as check valves, or to valves that are locked, sealed, or otherwise secured in position. ' A valve that receives an initiation signal is allowed to be in a non accident position provided the valve will automatically reposition in the proper stroke time upon receipt of the initiation signal. The monthly frequency of this requirement is based upon engineering judgement and is supported by procedural controls governing valve operation that ensure correct valve positions. This frequency is further supported by the inservice Testing Program, which demonstrates system pump and power operated valve operability. This combination of automatic actuation tests, periodic pump and valve testing, and monthly flow path verification is adequate to demonstrate operability of these systems.

,