ML18101B024

Proposed Tech Specs,Representing Changes to RCS - Chemistry Spec 3/4.4.7 & Spec 3/4.4.8

ML18101B024
Person / Time
Site:	Salem
Issue date:	09/28/1995
From:	Public Service Enterprise Group
To:
Shared Package
ML18101B023	List: ML18101B022 ML18101B024
References
NUDOCS 9510050021
Download: ML18101B024 (12)

Text

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• LIMITlNG CONJ)ITIONS FQR OP£RAT!ON MlJ) SURYEII,L\NCE REOUIRDj£NIS SECI!ON 3/4 4 WCIOR COOL\NI sxsms 3/4.4.l R!ACTOR COOL\NT LOOPS AND COOLANT CIRCULATION Stareu~ and Power Operation 3/4 4-l Hot Standby 3/4 4-2 Hoc Shutdown 3/4 4.3 Cold Shutdown 3/4 4-3b 3/4.4.2.l SAFETY VALVES

• SHUTDOWN 3/4 4-4 3/4.4.2.2 SAFETY VALVES

• OPERATING 3/4 4-4&

3/4.4.3 RELIEF VALVES 3/4 4-5 3/4.4.4 PR!SSlJlUZEll 3/4 4-6 3/4.4.5 STEAK GENERATORS 3/4 4.7 3/4.4.6 REACTOR COOLANT SYSTEM LF.AKAGE Leakage Detection System 3/4 4-14 Operational Leakage 3/4 4-15 Pressure Isolation Valves 3/4 4-16&

f CHEMISTR.Y SPECIFIC ACTIVITY 3/4.4. 9 PR!SstlR!/TEMPERATtlll! LIMITS Reactor Coolant System 3/4 4-24 Pressurizer 3/4 4-29

<;>v*rpressur* Protection Syste... 3/4 4-30 3/4.4.10 STR.UC'IURAL INT!Gl.ITY ASMI Coda Clas* l, 2, and 3 Components 3/4 4-32 3/4.4.ll IHT!liTIONALLY BIANK 3/4 4.34 3/4.4.12 HEAD VENTS 3/4 4-35

! i SALEK

• UNIT l v ..\menclllenc No. 101 I ]

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9510050021 950928

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BASES S,ECTION 3/4. 3 e

INSTRtJHgNIATION INDEX*

I 3/4.3.l PROTECTlvE INSTRUMENTATION B 3/4 3-l 3/4.3.2 ENGINEERED SAFETY FEATURES (ESF)

INSTRUMENTATION B 3/4 3-l 3/4.3.3 MONITORING INSTRUMENTATION B 3/4 3-l 3/4.3.4 TUR!INE OVERSPEED PROTECTION B 3/4 3-4 I

3/4.4 REACTOR COOJ.ANT SYSTEM 3/4.4.1 REACTOR COOIANT ioc>PS AND COOIANT CIRCUlATION B 3/4 4-1 3/4.4.2 SAFETY VALVES B 3/4 4-la 3/4.4.3 RELIEF VALVES B 3/4 4-la 3/4.4.4 PRESSURIZER.. B 3/4 4-2 3/4.4.5 STEAM GENERATORS B 3/4 4-2 ...')

.I

/JJ5£tlT B _.,.3/4. 4. 6 REACTOR COOIANT SYSTEM LEAICAGE B 3/4 4-3

. ~3/4.4.7 CHEMISTRY B 3/4 4;:>

3/4.4.8 SPECIFIC ACTIVITY B 3/4 4*5 3/4.4.9 PRESSURE/TEMPERATURE LIMITS B 3/4 4*6 3/4.4.10 STRUCTURAL INTEGRITY B 3/4 4-17 3/4.4.11 BIANK B 3/4 4-17 3/4.4.12 REACTOR VESSEL HEAD VENTS B 3/4 4*17

"'*"'\

9 SALEM

• UNIT 1 XII Allenmaent No.ll~

CHEMISTRY LIMITING CONDITION FOR 0 3.4.7 The Reactor Coolant Syst chemistry shall maintained within the limits specified in Table 3.4-APPLICABILI ACTION:

MODES 1, 2, 3 and 4

a. With any one or more c istry par er in excess of its Steady State Limit bu within its r nsi t Limit, restore the Parameter to within ts Steady S te Limi within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT TANOBY with'n t nex 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within e foll owing,, 0 ho rs.

b.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and At all With the concentration of ither chlori Coolari System in excess of its Steady tate Limit or more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or in excess of

• s Transient Limit, reduce th pressurizer pre sure to < 500 psi ' if applicable, d perform an engineering ev. uation to dete ne the effects of he out-of-lim t condition the structural ntegrity of the Reac r Coolant Sys m; determine that the Reactor oolant System remains acceptable for. ontinued operation prior. to increasing the press rizer pressure a ave 500 psig or prior o proceeding to MODE 4.

4.4.7 Te Reactor Coolant System chemistry shall be detennined to be within he limits by analysis of those parameters at the frequencies spec ied in Table 4.4-3.

SALEM - UNIT 1

~D INSEfi.I

TRANSIENT PARAMETER LIMIT DISSOLVED OXYGEN * ~ 1.00 ppm CHLORIDE {1.so ppm FLUORIDE ~ 1.50 ppm t applicable with Tavg/!. 250°F.

I SALEM~ 1

e*

T BLE 4.4-3 REACTOR COOLANT SYSTEM .

. . SAMPLE AND ALYSIS FRE UENCY PARAMETER DISSOLVED OXYGEN ~~-

_.-CHl:0R"I1)~-- . .*

FLUORIDE

~-

• 7Notuirecl with Tavg -

r < 250 F SALE~ 1

_J

REACTOR COOLANT SYStEM

'BASES 3/4.4.6.2 OPERATIONAL LEAKAGE (Continued)

The CONTROLLED LEAKAGE limitation restricts operation when the total flow from the reactor coolant pump seals exceeds 40 GPM with valve 1CV71 fully closed at a nominal RCS pressure of 2230 psig. This limitation ensures that in the event of a LOCA, the safety injection flow will not be less than assumed in the accident analyses.

The total steam generator tube leakage limit of 1 GPM for all steam generators {but not more than 500 gpd for any steam generator) ensures that the dosage contribution from the tube leakage will be limited to a small fraction*of Par.t 100 limits in the event of either a stel'm genera-tor tube rupture or steam line break. The 1 GPM limit is consistent with .

the as~umpdons *u~ui in *the an!lysis nf these accidents. The 500 gpd =

1eakage 1_ iini*t* ;p~r. s.te&r11 9ene1 ator ."en~_L(res that steam generator tube . ""

integrity is n""-irit~.fofe,engineering evaluation/a determine e effects of the o t*of-limit condit'..on on the structur integrity of e Reactor Coolant ystem; determine hat the Reacto Coolant System remains acceptable f continued operati n prior to in reasing the pr surizer pressure abov 500 psig or prior i proceeding to MODE 4. 1 1

4.4.8 The Reactor Coolant System chemistry s 11 be determined to be ~ithin the limits by an ysis of those parameters at the frequencies specified in Table 4.4-3.

SALEM - UNIT 2

TABLE 3.4-2 REACTOR COOLANT SYSTE~

CHEMISTRY LIMl??'

TRANSIENT PARAMETER LIMIT

)It DISSOLVED OXYGEN ~ 1. 00 ppm CHLORIDE ~ 0. 15 pp '\ ~ 1. 50 ppm FLUORIDE /'/ ~ 0. 15 ppm ~ 1. 50 ppm

/

~\

TABLE 4.4-3 CHEMISTRY LIMITS PARAMETER DISSOLVED OXYGEN

• CHLORIDE FLUORIDE per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> with Tavg ~ 250°F.

SA~2

REACTOR COOLANT SYSTEM BASES 3/4.4.7.2 OPERATIONAL LEAKAGE (Continued)

The total steam generator tube leakage limit of 1 GPM for all steam generators (but not more than 500 gpd for any steam generator) ensures that the dosage contribution from the tube leakage will be limited to a small fraction of Part 100 limits in the event of either a steam generator tube rupture or steam line break. The l GPM limit is consistent with the assumptions used in the analysis of these accidents. The 500 gpd leakage limit per steam generator ensures that steam generator tube integrity is maintained in the event of a main steam line rupture or under LOCA conditions.

PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary. Therefore, the presencg of any PRESSURE BOUNDARY LEAKAGE requires the unit to be promptly placed in COLD SHUTDOWN.

(3'Li; 4.8 CHEMISTRY> - IN sE12-T ~

of th sf The limitations on Reactor Coolant stem chemistry ensure that corrosio actor Coolant System is minimize and reduces the potential for Reactor Co nt System Leakage or failure due to stress corrosion. M

• aining

. the chemistry "thin the Steady State LimJts provides adequate co* sion

• protection to ens the structural integtity of the Reactor,.C ant System over the life of the p . The associattd effects of ~e'aing the oxygen, chloride and fluoride limit: re time andl temperatur, pendent. Corrosion studies show that operation may contin~ed wit ntaminant concentration levels in excess of the Steady State

• i~s. to the Transient Limits, for the specified limited time illt~L_Vals w'_ , mg----a=sign+ficant-*!!ffec-e-on the structural-;11Ugr1}"o- the Rea~ oolan ~stem. The time interval 11 permitting continued operation w.i-tffin th restrict10 qf the Transient Limits provides time for taking cOJ"l'eetive acti ns to restore t -- - .ntaminant concentrations to~~he Steady Sta e Limits. - _

The surv

• ance requirements provide adequate assurance that concent ations the limits will be detecte in sufficient time to take corrective SALEM - UNIT 2 B 3/4 4-5