ML18095A660

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Proposed Tech Specs,Deleting Tech Spec Section 3.7.1.2, Surveillance Requirement 4.7.1.2.c & Removing Valve Numbers from Tech Spec Surveillance Requirement 4.7.1.2.a.4
ML18095A660
Person / Time
Site: Salem  
Issue date: 12/27/1990
From:
Public Service Enterprise Group
To:
Shared Package
ML18095A659 List:
References
NUDOCS 9101020411
Download: ML18095A660 (11)


Text

- --9io1020.q.11~?of227-----~

PDR ADOCK 05000272 P

PDR ATTACHMENT 2

9*

Pt.ANT SYSTEMS AUXILIARY F££DWATiR SYST9t LIMITING CONDITION FOR OPERATION 3.7*.1.Z At least titre. f~endent stau ;enentor auxilf*f"'I fffdwatai-,pumps

. f and usoc'f 1tad manual activation switches in tn. contral l'"OOll and f1ow p&ths snal1 be OPERA81.E with:

1Wo ftedwatar p...,s, 11cn ~ae1e* of b.ing pawend fT"m sei:aaratl v'fut bussas, and

b.

One fffdwatal" P&llP ~aa1.. of being powei"ed fT"m an OPERABLE Stllll supp 1 y sysi..

APl'LICASil.:iTY:. "2DES 1, Z and l~

ACTIOH:

a.

With one auxiliary ftedwate.- p~ 1nopen.C11, r.st.on th* *qui"d 1uxf 1f1ry fn<ftfatel'" p~s ta OPERABLE st.ltus within 7Z houl'"s OT" be in at 1eut HOT STAHOBY within th* nut 6 noun and fn HOT SHUTDOWN wi th1 n the fa 11 ~

ng S hou.-s.

  • b.

With be 1wd1fary fffdw1tar p~s inoperable be in at *ieast HOT STAHCBY within 6 noun and fn HOT SHUTDOWN within.th* following 6 hoUM.

~ c.

  • With thn* 1wci1iaroy. fHmi-atal'" p~s inoperacl e, fmedi1taly0 ;niti 1'te caM-eetive ac:tf on to 1"9Stc'l"t 1t ltut on* 1uxi li1ry feed'#ate.,. p~

to OPERASU s~tus u soon IS pau_ible.

"\\...

SURVEILLANCE REQUIREMENTS

4. 7.1.2 Eidt IYXilfary f~atar p~ shall be d111enstt1tcd OPERASL.i:
1.

At least one* peT" 31 days by:

l.

Y*ri fying that tach.atc~dri vtn puaq:> deve 1 o~s 1 di sc.narge pnssur. of ;n1tar than or. tqual to 1275 psig on ~i-rcul*tion f1ow.

Vel'"ifying that the stau tu~ine-al'"iven Quma *develops 1 dischaf"9e p!*essul'"e of ;natal'" than ol'" equa 1 ta l 500 psi g on ~; n:u l 1t ion J

2.

f1aw wtten ~e. secondary staUI s~oly p"ssu" fs ;niter than J.. ;;:;~; ;~~:;:~:~;;;;;::;~;;~; ;:~~!~~;;~;;icaDle. 1.

its cor1"9Ct position.

  • SAUM - UHIT I
    • . *** J/4 7-s

. Artendment No. 39

~.

At 1eut lllCI,_,. 11 8Dftttli *1"iftl ~

by:

1.

Ymfy1n; u.at ~

IUt.DMt1c **ht 1n u.. *ta"" d1-h*" p~

"°" p&tft ~tel ta 1tl C0""9C't position on I PWIP ~hCM~t

,,.... "" t.st signal.

1.

Y~'"1fy1ftl tn&t CQdi auzi1f1~ fleMti!" -

IUnJ IS duigfte<S au~tica11y ypon..c11pi of UCJ'I auz1Ha~

f o&Ofa t.eT" IC'tUat 1 on t91t 11gna1.

SALO!

  • UNii 1 Amendnent No. 39

INSERT A

4.

Verify the manual maintenance valves in the flow path to each steam generator are locked open.

PLANT SYSTEMS BASES U = maximum number of inoperable safety valves per operating steam line 109 = Power Range Neutron Flux-High Trip Setpoint for 4 loop operation 76 = Maximum percent of RATED THERMAL POWER pennissible by P-8 Setpoint fo.r 3 loop operation.

X = Total relieving capacity of all safety valves per steam line in lbs/hour

  • Y * -** Ma~imum reliev*fog capacity of any one safety valve in

. 1 os / ho~~ r 3/4. 7. 1.2 AUXi LIARY ~ EEDWA T ER SYSTEM The OPERABI LITY of t he auxiliary feedwater system -ensures that the Reactor Coolant System can be cooled down to less than 35d°F from normal operati ng conditfons in t f1e event of a total loss of off-site power.

Each electric dri ven auxiliary feedwater pump is capable of deliver-ing a total feedwater flow of 440 gpm at a pressure of 1150 psig to the entrance of the steam generators.

The steam driven auxiliary feedwater pump i s capable of deliveiing a total feedwater flow of 880 gpm at a press u: e of 1150 psig to the entrance of the steam generators.

This capacity i s sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less than 350°F when the Residual Heat Removal System may be placed into operation.

r""7Js ~"-' J3 3/4.7.l.3 AUXILIARY FEED STORAGE TANK The OPERABILITY of the auxiliary feed storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with steam discharge to the atmosphere concurrent with total loss of off-site power.

The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.

SALEM - UNIT 1 B 3/4 7-2

  • ~

INSERT B The flow path to each steam generator is ensured by maintaining all manual maintenance valves locked open.

A spool piece consisting of a length of pipe may be used as an equivalent to a locked open manual valve.

The manual valves in the flow path are: lAFl, 11AF3, 12AF3, 13AF3, llAFlO, 12AF10, 13AF10, 14AF10, 11AF20, 12AF20, 13AF20, 14AF20, 11AF22, 12AF22, 13AF22, 14AF22, 11AF86, 12AF86, 13AF86, and 14AF86.

-e PUNT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7. 1.2 At least three independent steam generator auxiliary feedwater pumps and associated manual activation switches in the control room and flow paths shall be OPERABLE with:

a.

Two feedwater pumps, each capable of being powered from separat.e vital busses, and

b.

One feedwater pump capable of being powered from an OPERABLE steam supply system.

APPLICABILITY:

MODES 1, 2 and 3.

ACTION:

a.

With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b.

With two auxiliary feedwater pumps inoperable be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

c.

With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.

SURVEILLANCE REQUIREMENTS 4.7. 1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE:

a.

At least once per 31 days by:

1.

Verifying that each motor-driven pump develops a discharge pressure of greater than or equal to 1275 psig on recirculation flow.

2.

Verifying that the steam turbine-driven pump develops a discharge pressure of greater than or equal to 1500 psig on recirculation flow when the secondary steam supply pressure is greater than 750 psig.

The provisions of Specification 4.0.4 are not applicable.

3.

Verifying that each non-automatic valve in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position.

SALEM - UNIT 2 3/4 7_-5

_J

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) i 2-AF2Q lA~ Q~

, ~

~W~~~5i~~~2~

2A;;,F!O, 23AF10,

b.

At least once per 18 months during shutdown by:

l.

Verifying that each automatic valve in the motor driven pump flow path actuates to its correct position on a pump discharge pressure test signal.

2.

Verifying that each auxiliary feedwater pump starts as designed automatically upon receipt of each auxiliary feedwater actuation test signal.

SALEM - UNIT 2 3/4 7-;_6*

INSERT A

4.

Verify the manual maintenance valves in the flow path to each steam generator are locked open.

--1

'I PLANT SYSTEMS BASES.

U = maximum number of inoperable safety valves per operating steam 1 ine 109 = Power Range Neutron Flux-High Trip Setpoint for 4 loop operation 76 = Maximum percent of RATED THERMAL POWER permissible by P-8 Setpoint

, for 3 loop operation*

X =Total relieving capacity of all safety valves per steam line in lbs/hour Y = Maximum relieving capacity of any one safety valve in lbs/hour 3/4.7. 1.2 AUXILIARY FEEDWATER SYSTEM The OPERABILITY of the auxiliary feedwater system ensures that the Reactor Coolant Syst~m can be cooled down to less than 350°F from normal operating conditions in the event of a total loss of offsite power.

Each electric driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 440 gpm at a pressure of 1150 psig to the entrance of the steam generators.

The steam driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 880 gpm at a pressure of 1150 psig to the entrance of ttle-steam generators.

This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less than 350°F when the Residual Heat

  • Removal System may be placed into operation.
rrJ*s* £re 1 !J 3/4.7. 1.3 AUXILIARY FEED STORAGE TANK The OPERABILITY of the auxiliary feed storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with steam discharge to the atmosphere concurrent with total loss of offsite power.

The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.

SALEM - UNIT 2 B 3/4 7-2

INSERT B The flow path to each steam generator is ensured by maintaining all manual maintenance valves locked open.

A spool piece consisting of a length of pipe may be used as an equivalent to a locked open manual valve.

The manual valves in the flow path are: 2AF1, 21AF3, 22AF3, 23AF3, 21AF10, 22AF10, 23AF10, 24AF10, 21AF20, 22AF20, 23AF20, 24AF20, 21AF22, 22AF22, 23AF22, 24AF22, 21AF86, 22AF86, 23AF86, and 24AF86.