ML18101B024
| ML18101B024 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/28/1995 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML18101B023 | List: |
| References | |
| NUDOCS 9510050021 | |
| Download: ML18101B024 (12) | |
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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 Hot Standby Hoc Shutdown Cold Shutdown 3/4.4.2.l SAFETY VALVES
- SHUTDOWN 3/4.4.2.2 SAFETY VALVES
- OPERATING 3/4.4.3 RELIEF VALVES 3/4.4.4 PR!SSlJlUZEll 3/4.4.5 STEAK GENERATORS 3/4.4.6 REACTOR COOLANT SYSTEM LF.AKAGE Leakage Detection System Operational Leakage Pressure Isolation Valves f
CHEMISTR.Y SPECIFIC ACTIVITY 3/4.4. 9 PR!SstlR!/TEMPERATtlll! LIMITS Reactor Coolant System Pressurizer
<;>v*rpressur* Protection Syste...
3/4.4.10 STR.UC'IURAL INT!Gl.ITY ASMI Coda Clas* l, 2, and 3 Components 3/4.4.ll IHT!liTIONALLY BIANK 3/4.4.12 HEAD VENTS SALEK
- UNIT l r--*~-~----- -- --- ----- ----
v 3/4 4-l 3/4 4-2 3/4 4.3 3/4 4-3b 3/4 4-4 3/4 4-4&
3/4 4-5 3/4 4-6 3/4 4.7 3/4 4-14 3/4 4-15 3/4 4-16&
3/4 4-24 3/4 4-29 3/4 4-30 3/4 4-32 3/4 4.34 3/4 4-35
..\\menclllenc No. 101 9510050021 950928 PDR ADOCK 05000272 I
P PDR I :
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e INDEX*
BASES S,ECTION 3/4. 3 INSTRtJHgNIATION 3/4.3.l PROTECTlvE INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURES (ESF)
INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.4 TUR!INE OVERSPEED PROTECTION 3/4.4 REACTOR COOJ.ANT SYSTEM 3/4.4.1 REACTOR COOIANT ioc>PS AND COOIANT CIRCUlATION 3/4.4.2 SAFETY VALVES 3/4.4.3 RELIEF VALVES 3/4.4.4 PRESSURIZER..
3/4.4.5 STEAM GENERATORS
/JJ5£tlT 3/4. 4. 6 REACTOR COOIANT SYSTEM LEAICAGE B
. ~3/4.4.7 CHEMISTRY 3/4.4.8 SPECIFIC ACTIVITY 3/4.4.9 PRESSURE/TEMPERATURE LIMITS 3/4.4.10 STRUCTURAL INTEGRITY 3/4.4.11 BIANK 3/4.4.12 REACTOR VESSEL HEAD VENTS SALEM
- UNIT 1 XII B 3/4 3-l B 3/4 3-l B 3/4 3-l B 3/4 3-4 B 3/4 4-1 B 3/4 4-la B 3/4 4-la B 3/4 4-2 B 3/4 4-2
.I B 3/4 4-3 B 3/4 4;:>
B 3/4 4*5 B 3/4 4*6 B 3/4 4-17 B 3/4 4-17 B 3/4 4*17 Allenmaent No.ll~
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9
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
- b.
At all 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.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and 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
~
INSEfi.I D
PARAMETER DISSOLVED OXYGEN CHLORIDE FLUORIDE t applicable with Tavg/!. 250°F.
I SALEM~ 1 TRANSIENT LIMIT
~ 1.00 ppm
{1.so ppm
~ 1.50 ppm
e*
T BLE 4.4-3 REACTOR COOLANT SYSTEM.
PARAMETER DISSOLVED OXYGEN ~~-
_.-CHl:0R"I1)~--
FLUORIDE
~-
- 7Not r uirecl with T
< 250 F avg -
SALE~ 1
.. SAMPLE AND ALYSIS FRE UENCY
_J
'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 1 eakage 1_ iini*t* ;p~r. s.te&r11 9ene1 a tor."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
)
~\\
PARAMETER
)It DISSOLVED OXYGEN CHLORIDE FLUORIDE
/'/
/
TABLE 3.4-2 REACTOR COOLANT SYSTE~
CHEMISTRY LIMl??'
~ 0. 15 pp '\\
~ 0. 15 ppm TRANSIENT LIMIT
~ 1. 00 ppm
~ 1. 50 ppm
~ 1. 50 ppm
PARAMETER DISSOLVED OXYGEN CHLORIDE FLUORIDE CHEMISTRY LIMITS with Tavg ~ 250°F.
SA~2 TABLE 4.4-3 per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
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 s E 12-T ~
The limitations on Reactor Coolant sf stem chemistry ensure that corrosio of th 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~ 11 oolan
~stem. The time interval 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