ML20117F466

Proposed Tech Specs,Modifying SRV Surveillance Test for Relief Mode of Operation

ML20117F466
Person / Time
Site:	Grand Gulf
Issue date:	05/09/1996
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20117F456	List: ML20117F454 ML20117F466
References
NUDOCS 9605170429
Download: ML20117F466 (17)

Text

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• GNRO 96-00037 Attachment 4 _

Page 1 of 12 j',)

4 SURVEILLANCE REQUIREMENTS (continued) l SURVEILLANCE FREQUENCY SR 3.4.4.2 ----------------- -NOTE--------------------

Valve actuation may be excluded. j Verify each required relief function S/RV 18 months actuates on an actual or simulated automatic initiation signal.

1 SR 3.4.4.3 -------- ----------NOTE--------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Re_\le.T- Node. Verify each required S/RV -opese when 18 months on a Oc.tontna. St&%e5 manually actuated. STAGGERED TEST

- - - - .- BASIS for each valve solenoid 9605170429 960509 PDR ADOCK 05000416 P PDR GRAND GULF 3.4-11 Amendment No. 120

. GNRO 96-00037 Attachmsnt 4 S/RVs l , Paga 2 of,12 8 3.4.4

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BASES SURVEILLANCE SR 3.4.4.1 (continued)

REQUIREMENTS Testing Program. The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.

The Frequency was selected because this Surveillance must be performed during shutdown conditions and is based on the time between refuelings.

SR 3.4.4.2 l l

The required relief function S/RVs are required to actuate automatically upon receipt of specific initiation signals. i A system functional test is performed to verify the i mechanical portions of the automatic relief function operate

! as designed when initiated either by an actual or simulated initiation signal.

The LOGIC SYSTEM FUNCTIONAL TEST in SR 3.3.6.5.4 overlaps this SR to provide complete testing of  !

l the safety function.

l The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the ,

Surveillance were performed with the reactor at power. '

Operating experience has shown these components usually pass the SR when performed at the 18 month Frequency. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

This SR is modified by a Note that excludes valve actuation.

This prevents an RPV pressure blowdown.

SR 3.4.4.3 ual actuation of each required S/RV is performed Ls ce.t verify he valve is functioning properly g blockage exists ' e valve discharge This can be

!g g demonstrated by the re o urbine control valves Ih = or bypass valves, by a e measured steam flow, or any other meth able to verify ste w (e.g.,

tailpi perature or pressure). Adequate re steam sure must be available to perform this test to avoi

, (continued) l GRAND GULF B 3.4-20 Revision No. 0 l

. ,. GNRO 96-00037 Attachment 4

, Paga 3 of,12 8 . .a

' BASES SURVEILLANCE SR 3.4.4.3 (continued) r, REQUIREMENTS

, aging the valve. Also, adequate steam flow must be 3 pas ng through the main turbine or turbine bypass y es to contin to control reactor pressure when the S/RV ivert steam flo upon opening. Sufficient time is th fore l _t, ws,eg_t allowed aft the required pressure and flow e achieved to perform this t . Adequate pressure at ch this test is SR 3.9,93.c BR51.5 s to be performed i onsistent with the essure recommended

-= by the valve manufac er. Plant st up is allowed prior to performing this test cause y e OPERABILITY and the i setpoints for overpressure o tion are verified, per ASME

requirements, prior to valv stallation. Therefore, this i SR is moditied by a Note at st es the Surveillance is not '

! required to be perfo until 12 rs after reactor steam i pressure and flow a adequate to per - the test. The

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> allowed r manual actuation af the required l 3 pressure is r hed is sufficient to achiev table i conditions r testing and provides a reasonab time to j complet e SR. If the valve fails to actuate only to

! the f ure of the solenoid but is capable of openin n j ov ressure, the safety function of the S/RV is consi d i ERABLE.

f The 18 month on a STAGGERED TEST BASIS Frequency ensures that each solenoid for each S/RV is alternately tested. The i 18 month Frequency was developed based on the S/RV tests j required by the ASME BM9r a.nd Pressure Vessel Code, I Section XI (Ref. 1). Operating experience has shown that these components usually pass the Surveillance when l'

performed at the 18 month Frequency. Therefore, the Frequency was concluded to be acceptable from a reliability

.; standpoint.

REFERENCES 1. ASME, Boiler and Pressure Vessel Code, Sections III I and XI.

2. UFSAR, Section 5.2.2.2.3.

3. UFSAR, Section 15.

GRAND GULF B 3.4-21 Revision No. 0

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,, GNRO 96-00037 Attachment 4

. Page 4 of 12 1 SR 3.4.4.3.a BASES Insert A manual actuation of each required S/RV (those valves removed and replaced to satisfy SR 3.4.4.1.) is performed to verify that the valve is functioning properly. This SR can be demonstrated by one of two methods. If performed by method 1), plant startup is allowed prior to performing this test because valve OPERABILITY and the setpoints for overpressure protection are verified, per ASME requirements, prior to valve installation. Therefore, this SR is modified by a Note that states the surveillance is not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test. The 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> allowed for manual actuation after the required pressure is reached is suffici nt to achieve stable conditions for testing and provides a reasoneale time to complete the SR. If performed by method 2), valve OPERABILITY has l been demonstrated for all installed S/RVs based upon the successful operation of a test sample of S/RVs.

1) Manual actuation of the S/RV, with verification of the response of the turbine control valves or bypass valves, by a change in the measured steam flow, or any other method suitable to verify steam flow (e.g., tailpipe temperature or pressure).

Adequate reactor steam pressure must be available to perform this test to avoid damaging the valve. Also, adequate steam flow must be passing through the main turbine or turbine bypass valves to continue to control reactor pressure when the S/RVs divert steam flow upon opening. Sufficient time is therefore allowed after the required pressure and flow are achieved to perform this test. Adequate pressure at which this test is to be performed is consistent with the pressure recommended by the valve manufacturer.

2) The sample population of S/RVs tested each refueling outage to satisfy SR 3.4.4.1 will be stroked in the relief mode during "as-found" testing to verify proper operation of the S/RV. The successful performance of the test sample of S/RVs provides reasonable assurance that the remaining installed S/RVs will perform in a similar fashion. After the S/RVs are replaced, the relief-mode actuator of the newly-installed S/RVs will be uncoupled from the S/RV stem, and cycled to ensure that no damage has occurred to the S/RV during transportation and installation. This verifies that each replaced S/RV will properly perform its intended function.

If the valve fails to actuate due only to the failure cf the solenoid j but is capable of opening on overpressure, the safety function of the S/RV is considered OPERABLE.

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. GNRO 96-00037 Attachment 4 l

Page 5 of 12

, . ECCS -Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

! SURVEILLANCE FREQUENCY l l'

SR 3.5.1.5 -..-...............N0TE-------------------.

Vessel injection / spray may be excluded. i Verify each ECCS injection / spray subsystem 18 months actuates on an actual or simulated i automatic initiation signal.

1 SR 3.5.1.6 .-..............---N0TE-------------------.

Valve actuation may be excluded.

i l Verify the ADS actuates on an actual or 18 months l

] simulated automatic initiation signal.

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! SR 3.5.1.7 -------------------NOTE--------------------

I Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> '

i after reactor steam pressure and flow are 1 adequate to perform the test.  !

j m .- _ m Verify ea ADS valve when manually 18 months on a

[Re.\le;9-Me actuated. STAGGERED TEST

! x.tootoe. s tsto% e5 BASIS for each 3

h w=7= valve solenoid SR 3.5.1.8 Verify the ECCS RESPONSE TIME for the HPCS 18 months System is within limits.

ECC 2rati

. ,. GNRO 96-00037 Attachment 4 3 3.5.

Page 6 of 12 BASES i

SURVEILLANCE SR 3.5.1.6 REQUIREMENTS

) (continued) The ADS designated S/RVs are required to actuate I i

I automatically upon receipt of specific initiation signals.

A system functional test is performed to demonstrate that 1

the mechanical portions of the ADS function (i.e.,

solenoids) operate as designed when initiated either by an actual or simulated initiation signal causing proper actuation of all the required componen,ts. SR 3.5.1.7 and the LOGIC SYSTEM FUNCTIONAL TEST performed in LCO 3.3.5.1 i overlap this Surveillance to pro <ide complete testing of the j assumed safety function.

i The 18 month Frequency is based on ite need to perform this i Surveillance under the conditions that apply during a plant j outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

i i Operating experience has shown that these components usually pass the SR when perfomed at the 18 month Frequency, which is based on the refueling cycle. Therefore, the Frequency 1

was concluded to be acceptable from a reliability j standpoint.

i i

This SR is modified by a Note that' excludes valve actuation. ,

This prevents an RPV pressure blowdown. l I

l SR 3.5.1.7 nual actuation of each ADS valve is performed to verif j tha e valve and solenoids are functioning properly 1 that no ockage exists in the S/RV discharge line his j is demonst ed by the response of the turbine i

bypass valve, trol or 3 DN a change in the measured s flow, or by any other method table to verify ste ow (e.g.,

i ' R 3.5.h l.ci. %51.5 tailpipe temperature ressure). quate reactor steam pressure must be availab to per rm this test to avoid i damaging the valve. Also, a ate steam flow must be l passing through the main ine turbine bypass valves to

! continue to control or pressur en the ADS valves divert steam flow n opening. Suffic t time is i therefore allo , after the required press and flow are

achieved, erform this test. Adequate pres e at which i this t is to be performed is consistent-with th ressure i rec nded by the valve manufacturer. Reactor start is j owed prior to performing this test because valve i

3 (continued)

GRAND GULF B 3.5-12 Revision No. 1 4

4

,j ECCS-Oct rating

) _ ,. GNRO 96-00037 Attachment 4 8 3.5.1 j ,,

Page 7 of 12

), BASES 1

SURVEILLANCE SR 3.5.1.7 (continued)

REQUIREMENTS I  : !

BILITY and the setpoints for overpressure protecti are ve , per ASME requirements, prior to v i

i L s a.e t installation. efore, this SR is mod y a Note that

N 3,5,)1,q D sES states the Surve111an not re to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after react ressure and flow are j adequate to perform est. SR 3. . nd the LOGIC SYSTEM FUNCT T performed in LCO 3.3. . riap this l j Sury ce to provide complete testing of the ass l ety function.

i I The Frequency of 18 months on a STAGGERED TEST BASIS ensures that both solenoids for each ADS valve are alternately tested. The Frequency is based on the need to per9rm this i

i Surveillance under the conditions that apply just t ior to i or during a startup from a plant outage and the pountial i for unplanned transients. Operating experience has shown that these components usually pass the SR when performed at the 18 month Frequency, which is based on the refueling

! cycle. Therefore, the Frequency was concluded to be j

acceptable from a reliability standpoint.

1 SR 3.5.1.8  !

1 4

l This SR ensures that the HPCS System response time is less 4

than or equal to the maximum value assumed in the accident i

analysis. Specific testing of the ECCS actuatinn l

l instrumentation inputs into the HPCS System ECCS SYSTEM i RESPONSE TIME is not required by this SR. Specific response j

i time testing of this instrumentation is not required since these actuation channels are only assumed to respond within j the diesel generator start time; therefore, sufficient margin exists in the diesel generator 10 second start time

when compared to the typical channel response time

! i (milliseconds) so as to assure adequate response without a '

i specific measurement test. The diesel generator starting and any sequence loading delays must be added to the HPCS )'

i

' System equipment response times to obtain the HPCS System ECCS SYSTEM RESPONSE TIME. The acceptance criterion for the

.HPCS System ECCS SYSTEM RESPONSE TIME is :s; 27 seconds.

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i, (continued) j GRAND GULF B 3.5-13 Revision No. 1 4

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,, GNRO 96-00037 Attachmtnt 4 j Page 8 of 12 SR 3.5.1.7.a BASES Insert A manual actuation of each required ADS valve (those valves removed j l and replaced to satisfy SR 3.4.4.1.) is performed to verify that the l valve is functioning properly. This SR can be demonstrated by one of two methods. If performed by method 1), plant startup is allowed prior to performing this test because valve OPERABILITY and the setpoints for overpressure protection are verified, per ASME l requirements, prior to valve installation. Therefore, this SR is  !

modified by a Note that states the Surveillance is not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test. The 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> allowed for manual actuation after the required pressure is reached is sufficient to  !

! achieve stable conditions for testing and provides a reasonable time to complete the SR. If performed by method 2), valve OPERABILITY has been demonstrated for all installed ADS valves based upon the successful operation of a test sample of S/RVs. l l

1) Manual actuation of the ADS valve, with verification of the l l response of the turbine control valves or bypass valves, by a l l

change in the measured steam flow, or any other method suitable to verify steam flow (e.g., tailpipe temperature or pressure).

Adequate reactor steam pressure n.ust be available to perform this test to avoid damaging the valve. Also, adequate steam flow must be passing through the main turbine or turbine bypass i valves to continue to control reactor pressure when the ADS {

valves divert steam flow upon opening. Sufficient time is I therefore allowed after the required pressure and flow are I achieved to perform this test. Adequate pressure at which this  !

l test is to be performed is consistent with the pressure

! recommended by the valve manufacturer.

I

2) The sample population of S/RVs tested each refueling outage to satisfy SR 3.4.4.1 will be stroked in the relief mode during l "as-found" testing to verify proper operation of the S/RV. The successful performance of the test sample of S/RVs provides reasonable assurance that all ADS valves will perform in a similar fashion. After the S/RVs are replaced, the relief-mode actuator of the newly-installed S/RVs will be uncoupled from the S/RV stem, and cycled to ensure that no damage has occurred to-the S/RV during transportation and installation. This verifies that each replaced S/RV will properly perform its intended function.

SR 3.5.1.6 and the LOGIC SYSTEM FUNCTIONAL TEST performed in LCO 3.3.5.1 overlap this surveillance to provide complete testing of the assumed safety function.

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.- LLS Valves l

,, GNRO 96-00037 Attachment 4 3.6.1.6 l Page 9 of 12 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.6.1 ..............----N0TE------------------.

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

- :t _ _ _

RE. pine & g

_ _ _m Verify each LLS valve when manually 18 months on a (ge_i;e,f mockc h actuated. STAGGERED TEST mm gmg3T BASIS for each 4__-- =J valve solenoid SR 3.6.1.6.2 ..............----N0TE---------------....

Valve actuation may be excluded.

Verify the LLS System actuates on an 18 months actual or simulated automatic initiation signal.

GRAND GULF 3.6-21 Amendment No. 120

, . . dNRO 96-00037 Attachmsnt 4 LLS Valves

, , ' Page 10 of 12 B 3.6.1.6

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' BASES (continued)

LC0 Six LLS valves are required to be OPERABLE to satisfy the assumptions of the safety analysis (Ref. 2). The requirements of this LCO are applicable to the mechanical and electrical / pneumatic capability of the LLS valves to function for controlling the opening and closing of the S/RVs.

APPLICABILITY In MODES 1, 2, and 3, an event could cause pressurization of the reactor and opening of S/RVs. In MODES 4 and 5, the probability and consequences of these events are reduced due to the pressure and temperature limitations in these MODES. '

Therefore, maintaining the LLS valves OPERABLE is not required in MODE 4 or 5.

ACTIONS A.1 With one LLS valve inoperable, the remaining OPERABLE LLS valves are adequate to perform the designed function.

However, the overall reliability is reduced. The 14 day Completion Time takes into account the redundant capability afforded by the remaining LLS S/RVs and the low probability of an event in which'the remaining LLS S/RV capability would be inadequate.

Ii B.1 and 8.2 If two or more LLS valves are inoperable or if the inoperable LLS valve cannot be restored to OPERABLE. status within the required Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and to MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.6.1.6.1 REQUIREMENTS hat 5=5R 3 4 gt'i'et G M S.3 tuation of each LLS valve is performed to vad fy that the va ve nu ;;;5aidJL_are fnarthr,;ny properly and

' that no blockana -Sta in Ine Viive,Nsharadine. i This

=.. ue oemonstrated by the response of the turbine cune.d (continued) l GRAND GULF B 3.6-33 Revision No. 0 l _. .. -. . -

. ,, GNRO 96-00037 Attachment 4 LLS Valves Pago 11 of 12 B 3.6.1.6

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BASES SURVEILLANCE SR 3.6.1.6.1 (continued)

REQUIREMENTS

- bypass valve, by a change in the measured steam flow, by other method that is suitable to verify steam I

w (e.g., ilpipe temperature or pressure). Adequa reactor steam pre re must be available to perform th test to l avoid damagin the valve. Also, adequate s m flow must be passing through main turbine or tur e bypass valves to 4 wses.t continue to control actor pressure en the LLS valves l

l SR 3'6'1'l.'i.ci BR5E S divert steam flow upon ning. quate pressure at which '

this test is to be perform consistent with the pressure recommended by the valve l turer. The 18 month Frequency was develope ased on S/RV tests required by the ASME Boiler and essure Vessel e,Section XI (Ref. 3) . The F uency of 18 months o STAGGERED TEST BASIS ensure at each solenoid for each is alternate tested. Operating experience has wr esse compo s usually pass the Surveillance when per th d at month Frequency. Therefore, the Frequency was neluded to be acceptable from a reliability standpoin steam pressure is required in order to perform the Surve e, however, and steam may not be availa ring a unit outag , e Surveillance may be perfo uring the shutdown prior to o startup follo a unit outage.

Unit startup is allowed p t orming this test because valve OPERABILITY oints for overpressure protection are ver by Reference r to valve installatio er adequate reactor steam p re and flow eached, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> are allowed to prepare orm the test.

] SR 3.6.1.6.2 The LLS designed S/RVs are required to actuate automatically l upon receipt of specific initiation signals. A system functional test is performed to verify that the mechanical portions (i.e., solenoids) of the automatic LLS function operate as designed when initiated either by an actual or simulated automatic initiation signal. The LOGIC SYSTEM FUNCTIONAL TEST in SR 3.3.6.5.4 overlaps this SR to provide complete testing of the safety function.

(continued)

GRAND GULF B 3.6-34 Revision No. O

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, o GNRO 96-00037 Attachment 4 l Page 12 of 12 l

SR 3.6.1.6.1.a BASES Insert l

l A manual actuation of each required LLS valve (those valves removed and replaced to satisfy SR 3.4.4.1.) is performed to verify that the valve is functioning properly. This SR can be demonstrated by one of two methods. If performed by method 1), plant startup is allowed prior to performing this test because valve OPERABILITY and the setpoints for overpressure protection are verified, per ASME requirements, prior to valve installation. Therefore, this SR is modified by a Note that states the Surveillance is not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test. The 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> allowed for manual actuation after the required pressure is reached is sufficient to achieve stable conditions for testing and provides a reasonable time l to complete the SR. If performed by method 2), valve OPERABILITY has i

been demonstrated for all installed LLS valves based upon the j successful operation of a test sample of S/RVs.

1) Manual actuation of the LLS valve, with verification of the response of the turbine control valves or bypass valves, by a change in the measured steam flow, or any other method suitable

! to verify steam flow (e.g., tailpipe temperature or pressure).

Adequate reactor steam pressure must be available to perform this test to avoid damaging the valve. Also, adequate steam flow must be passing through the main turbine or turbine bypass l valves to continue to control reactor pressure when the LLS l valves divert steam flow upon opening. Sufficient time is l

therefore allowed after the required pressure and flow are achieved to perform this test. Adequate pressure at which this test is to be performed is consistent with the pressure recommended by the valve manufacturer.

2) The sample population of S/RVs tested each refueling outage 1 l to satisfy SR 3.4.4.1 will be stroked in the relief mode during "as-found" testing to verify proper operation of the S/RV. The successful performance of the test sample of S/RVs provides reasonable assurance that all LLS valves will perform in a similar fashion. After the S/RVs are replaced, the relief-mode actuator of the newly-installed S/RVs will be uncoupled from the .

S/RV stem, and cycled to ensure that no damage has occurred to i the S/RV during transportation and installation. This verifies that each replaced S/RV will properly perform its intended function.

l The frequency of 18 months on a STAGGERED TEST BASIS ensures that l each solenoid for each S/RV is alternately tested. Operating I

experience has shown these components usually pass the Surveillance

when performed at the 18 month Frequency. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

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