ML18106B024

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Proposed Tech Specs Re Deferral of Surveillance Requirements for Salem Generating Station,Unit 1
ML18106B024
Person / Time
Site: Salem PSEG icon.png
Issue date: 01/15/1999
From:
Public Service Enterprise Group
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ML18106B023 List:
References
NUDOCS 9901250170
Download: ML18106B024 (20)
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Document Control Desk LR-N990005 LCR S98-04 SALEM GENERATING STATION UNIT N0.1 CHANGE TO TECHNICAL SPECIFICATIONS DEFERRAL OF SURVEILLANCE REQUIREMENTS TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES Technical Specification 4.1.2.2.c

  • 3/4 1-9 Table 4.3-1 item 11 3/4 3-11 Table 4.3-1 Note (4) 3/4 3-13 4.3.2.1.3 3/4 3-14 Table 4.3-2 item 1a 3/4 3-31a Table 4.3-6 item 2 3/4 3-48 Table 4.3-11 item 4 3/4 3-57 Table 4.3-11 item 17 3/4 3-57a 4.5.1.d 3/4 5-2 4.5.2.e.1 3/4 5-5 4.7.6.1.d.2 3/4 7-20 4.7.10.b 3/4.7-34 4.8.1.1.2.d.7 3/4 8-5 4.8.1.1.2.d.7 (footnote) 3/4 8-5a 4.8.2.3.2.f 3/4 8-9a 4.8.2.5.2.c.2 3/4 8-12 4.8.2.5.2.d 3/4 8-12 4.8.3.1.a.1 3/4 8-14

81 'C7TITI CWTllQL SX'iT"'

StJRWiloLMIC'I IWQUIPPf!EMS - (Coatinued)

-=

c:.* Al: l-C oac:e per 18 mcmtlw during ahutdown by verifying that autc:matic valve in th* now path actuat** to it* correct po*itioa on a **f*tY injection t**t *ignal.

d. At lea*t once per 18 month* by verifying that th* now path required by epecific:ation 3.1.2.2.a deliver* at lea*t 33 gpn to the Reactor Coolant Sy*tem.
  • SAi.BM - ONIT l 3/4 1-9 Amendment No. 145

TABLE t.3-1 REACTOR TRIP SYSTEM IHSTRCMEHTATIOH SURVEILLANCE REQUIREMENTS CBAHHEL MODES IN WHICH CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIIUU>

1. M&nual Reactor Tri~.~-~ H.A. H.A. a 1, 2,"and *
2. Power Range, Heutroa nux s 0121, Mill and Q111 Q 1, 2, and 3* I
3. Power Range, Reutron rlux, H.A. R'~' 1, 2 High Poaitive Rate Riii

'* Power Range, Neutron Flux, High H99ative Rate N.A. Q 1, 2

5. Intermediate Range, Reutron Flux s R"' S/U111 1, 2 and *
6. Source Range, Neutron Flux sm R"' Q and S/Uc11 2, 3, 4, 5 and *
7. OVertemperature AT s R Q 1, 2
8. OVerpower AT s a Q 1, 2 9 .. Preaaurizer Preaaure--Low s R Q 1, 2
10. Preaaurizer Preaaure--Bigh s R Q 1, 2
11. Preaaurizer Water Level--Bigh s R @ Q 1, 2
12. Loaa of Flow - Single Loop s a Q 1 UNIT 1 3/4 3-11 Amendment No. 205

TABLI 4.l-1 (Continued)

NOTATION

(1) - If not performed in pr*vioua 31 day*.

(2) - H*at balance only, &Dove 1st of RATBD '1'HBRIGl. POWD.

( 3) - Compar* incor* to *xcor* axial off 1*t &Dov* 15t of RATBD THBRMAL POWER. Recalibrat* if ab*olut* diff*r*nc* a 3 percent.

(4) - Manual SSPS functional input check ev*ry 18 montha. -:¥ -#

(5) - Each train or logic channel *hall be t**t*d at l*a*t every 62 day1 on a STAGGBJlBI) TBST BASIS.

(6) - Neutron det*ctor* may be excluded from ~ CALIBRATION.

(7) - Below P-6 (Block of Sourc* Range R*actor Trip) **tpoint.

( B) - Delet*d

  • ( 9) - The c:HAHNKL F'UNCTIOHAL TBST ah.all independently verify th*

OPERABILITY of the tJndervoltage and Shunt Trip mt1chani*m for the Manual Reactor Trip Punction.

Th* T**t ah.all al*o verify OPIR.ABILITY of the Byp*** Br*ak*r Trip circuit*.

(10) - DELBTBD (11) - Th* CBANlGL POHCTIOHAL TUT *hall independently verify the OPSRAAILITY of the Reactor Trip Breaker 'Ondervoltage and Shunt Trip mechani11U.

(12) - DELSTm I

  • SALEM - UNIT 1 l/4 3-13 Amendment No. 176 I

INSTRUMENTM'ION 3/4.3.2 £NGINllREP SAFETY FEATURE AC'l'UATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION

                                                    • ~**n===*==========3=================================

3.3.2.1 The Bngineered Safety Feature Actuation System (ESFAS) instru-mentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.

APPLICA8ILIIY: As shown in Table 3.3-3.

AC'I'ION:

a. With an ESFAS instrumentation channel trip setpoint less conserva-tive than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE statue with the trip setpoint adjusted consistent with the Trip Setpoint value.
b. With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.

StJRVBILLANCB REQOIREMBNTS

                                                                                                                • =***************z=

4.3.2.1.1 Bach BSFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNELCHECK, CHANNE~ CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3-2.

4.3.2.1.2 The logic for the interlocks ahall be demonstrated OPERABLE during the autanatic actuation logic test. The total interlock function shall be demcnatrated OPERABLE at least once per 18 months during CHANNEL CALIBRATIOR te*ting of each channel affected by interlock operation.

'6.3.2.1.3 Th* iRGIRBKRKD SAPBTY FBATORBS RBSPONSB TIME of each ESFAS function ahall be dmncliD*trated to be within the limit at least once per 18 month*r Deb te*t mhall include at leaat one logic train such that both logict,._~ are te*ted at lea*t once per 36 months and one channel per functiali-~lluc:b that all channel* are teated- at least once per N times 18 mcnth9 wbe:re-B i* the total number of redundant channels in a specific BSFAS functian u shown in the "Total No. of Channels" Column of Table 3.3-3. The provi*ion* of Specification 4.0.4 are not applicable to MSIV closure time testing. The provision* of Specification 4.0.4 are not applicable to the turbine driven auxiliary feedwater pump provided the surveillance ia performed within 24 hour* after the secondary steam generator pressure is greater than 680 psig .

  • SALEM - UNIT 1 3/4 3-14 Amendment No. 188
  • TABLE .4. 3-2 ENGJNEERl::D SAFC:TY FEATURE ACTUATION SYSTEM INSTRUMENTATION CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED
1. SAFETY INJECTION, TURBINE TRIP AND FEEDWATER ISOLATION
a. Manual Initiation N.A. N.A. R* 1, 2, 3, 4
b. Auto~atic Actuation Logic N.A. N.A. M(2) 1,2,3,4
c. Containment Pressure-High s R Q (3) 1, 2, 3
d. Pressurizer Pressure--Low s R Q 1, 2, 3
e. Differential Pressure Between s R Q 1, 2, 3 Steam Lines--High
f. Steam Flow in Two Steam s R 1, 2, 3 Lines--High coincid~nt with Tavg--Low-Low or Steam Line Pressure-Low
2. CONTAINMENT SPRAY
a. Manual Initiation N.A. N.A. R 1,2,3,4
b. Automatic Actuation Logic N.A. N.A. M(2) 1,2,3,4
c. Containment Pressure--High-High s R Q(3) 1, 2, 3 SALEM - UNIT l 3/4 3-31a Amendment No. 142

TABLE 4.3-6 RElllTE SllJTOOWH ll>NITORING INSTRUHENTATIOH SURVEllLANCE REQUIREMENTS I

'. *\*.i*ij::'<<

. c: ...

z ~

CllAHNEL CHANNEL

..... INSTRUMENT CHECK CAL 1BRATI ON

1. Pressurlier Pressure H R
2. Pre~surlzer level H R*~
3. Ste111 Generator Pressure H R
4. Stea. Generator level H R w

w ~ I I

t I

I

  • TAB SURVEILLANCE CHANNEL

-11 UIREMENTS FOR ACCIDENT MONITORING INSTRUMENTATION CHANNEL CHANNEL FUNCTIONAL INSTRUMENT CHECKS CALIBRATION TEST

1. Reactor Coolant Outlet Temperature - M R ...HA- tJ.~ (

TeoT (Wide Range)

2. Reactor Coolant I~ T.-aperature - M R ,,)IX" f'L A.

TcoLD (Wide Range)

3. Reactor Coolant Pressure (Wide Range) M R J1K N* A.
4. Pressurizer Water Level M R**'- JIK f'J.A.
5. Steam Line Pressure M R
6. Steam Generator Water Level M R ft N* A*

(Narrow Range)

1. Steam Generator Water Level M R yx f\LA I (Wide Range)
8. Refueling Water Sto~age Tank Water Level M R _yK' rJ.A*
9. deleted R )U<f\J,A.

I

10. Auxiliary Feedwater Flow Rate
11. Reactor Coolant System Subcooling M JUr" N, I\.

Margin Monitor

  1. Auxiliary Feedwater System is used on each startup and flow rate indication is verified at that time.
  • The instruments used to develop RCS subcooling margin are calibrated on an 18 month cycle; the monitor will be compared quarterly with calculated subcooling margin for known input values.

3/4 3-51 Amendment No. 147 SALEM - UNIT 1

  • TABLE 4.3-11 (Continued)

SURYBILI.ANCE REQUIREMENTS FOR ACCIDENT MQNITORING INSTRYMENTA]'ION CHANNEL' CHANNEL CHANNEL FUNCTIONAL INSTRUMENT CHECKS CALIBRATION TEST

12. PORV Position Indicator M -im- f\l,,A1 R
13. PORV Block Valvo ~1tf~on Indicator M )iK N)AI Q*
14. Pressurizer Safo~y:v.A+ve Position M .* N* AI ~-

Indicator * *

15. Containment Pro**ure - ~arrow Range M _.}Ve" tJ 11 A*
16. Containment Pre**ure - Wide Range M .)B( tJ *A.
17. Containment Water Level - Wide Range M JB('N,A 1
18. Core Bxit Thermocouples M R >H( N* A~
19. Reactor Vessel Level Instrumentation M R yxN.A*

System (RVLIS)

  • Unless the block valve is closed in order to meet the requirements of Action b, or c in specification 3.4.3.

3/4 3-57a Amendment No. 155 SALEM - UNIT l

EMJ:RSjENCX COBE CQOL!NG SXSTEMS

  • SURVSILI.Allc:& J\ZQUIJU:MJ:NTS (Continued)
b. *At l***t once per 31 d&y* and within 6 hour* &!ter each *olution volume incr*&** of ~ l\ of t&nk volume by verifying th* boron I

concentration of the accumulator *elution.

c. At l*&*t one* per 31 day* when th* RCS pre**ure i* greater than 1000 p*iq by verifying that the power lockout *witch i* in lockout.

d.* At le&*t once per 18 month* by verifyinq that each accumulator iaolation valve open* automatically upon receipt ot & *&fety injection teat aiqnal

  • SALEM - UNIT l J/4 s-2 Amendment 10. *--

'~

iMQGQC:X cog COOLING SXSDjMS SURVEILLANCE RBQUlRDUCNTS (Conci.nued) c.. By a vi*ual* inspeccion which verifies Chae no loose del:lri* (raga, t:.ra*1'i:'* cloching, *Cc. l i* pre*enc in Ch* concainmenc which could be t:.r&n91M'~C*d to che containm*nt swnp and caus* re*triction of the pump succion. during LOCA condition*. Thi* vi.su.l insp*cti.on *hall be performed:

l. For all acce**ibl* areas of th* containment prior to establishing CONTAINMENT INTEGRITY, and I
2. At lea*c once daily (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> con*ecutive p*riod) the area*

affected within containment by containment entry and during the final entry when CONTAINMENT INTEGRITY 1.9 ~*Ca.blished.

d. At lea*t once per lB month* by:
l. A visual inapeccion of th* concainm*nt sump and verifying that the subay*t*m suction inlets are not re*tricted by debri* and that the sump component* (tra*h rack*, screen*, etc.) show no evidence of structural di*tre** or corro*ion.
e. At leaac once per 18 month8, during *hucdown, by:

l~ V*rifying th.at each automatic valve in the flow path actuate* to it* correct po*ition on a safecy injection te*t *i~l.

2. verifying that each of the following pump* *tart automatically upon receipt of a *afecy injection te*t *i~l:

al centrifugal ~barging pump bl Safety injection pump c) R**idual heat removal pump

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

~-- ..

  • SALEM - UNIT l 3/4 s-s Amendment No. l~~

PLANT SYSTEMS

.URVEILLANCE REQUIREMENTS

                                                                  • =z********c***************a**********

4.7.6.l Each control room emergency air conditioning system filtration train shall be demonstrated OPERABLE:

a. At least once per 31 days by initiating flow through the HEPA filter and charcoal adsorber train(s) and verifying that the train(s) operates with each fan operating for at least 15 minutes.
b. At least once per 18 months or prior to return to service (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system, by:
l. Verifying that the charcoal adsorbers remove 299t of a halogenated hydrocarbon refrigerant test gas when they are tested in-place while operating the ventilation system at a flow rate of 8000 cfm

+/- lOt.

2. Verifying that the HEPA filter banks remove 299' of the DOP when they are tested in-place while operating.the ventilation system at a flow rate of 8000 cfm +/- lOt.
3. Verifying within 31 day* after removal that a laboratory analysis

.of a carbon sample from one of the charcoal adsorbers demonstrates a removal efficiency of a99t for radioactive methyl iodide when the sample is tested at J0°C, 9St relative humidity.

c. After every 720 hour* of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a carbon sample obtained from a test canister demonstrates a removal efficiency of a 99t for radioactive methyl iodide when the sample is tested at 30°C, 9St relative humidity.
d. At lea11t once per 18 months by:
l. Verifying that the preaaure drop across the combined HEPA filter and charcoal adaorber bank is s 3.5 inches water gauge while oper~*th* ventilation system at a flow rate of 8000 cfm +/- 10\.

~

~YT'f.-*;

2. Veri~ that on a *afety injection test signal or control room intakifchigh radiation te*t signal, the system automatically actuat. . in the preaaurization mode by opening the outside air supply.and diverting air flow through the HEPA filter and charcoal adaorber bank.
3. Verifying that the system can maint.ain the control room at a positive pressure 2 1/8" water gauge relative to the adjacent areas during system operation with makeup air being supplied through the HEPA filters and charcoal adsorbers at the design makeup flow rate of s 2200 cfm.

SALEM - UN~ .it{~ 3/4 7-20 Amendment No .190

  • PLANT SYSTEMS LIMITING COllDlTION FOR OPERATION ACTION: MODES 5 and 6*0r during movement of irradiated fuel assemblies. *
a. With one chiller inoperable:
1. Remove the appropriate non-essential heat loads from the chilled water system within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and; OPEi£A-8L
2. Restore the chiller to *epera~l~ status within 14 days or;
3. Suspend CORE ALTERATIONS and movement of irradiated fuel assemblies.
b. With two chillers inoperable:
1. Remove the appropriate non-essential heat loads from the chilled water system within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and;
2. Align the control room emergency air conditioning system (CREACs) for single filtration operation using the Salem Unit 2 train within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and; oPf2ABLG
3. Restore at least one chill&r to epe5agle status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or;
4. Suspend CORE ALTERATIONS and movement of irradiated fuel assemblies. Df'tf°'2-A6LE"
c. With one chille~er pump inoperable, restore the chilled water pump to operable status within 7 days or suspend CORE ALTERATIONS and movement of irradiated fuel assemblies.
a. At leaat once per 31 days by verifying that each manual valve in the c~lled water system flow path servicing safety related components t~is not locked, sealed, or otherwise secured in position, is in ita: correct position.

b.

~**- -

At lea.1t orice per - re months, by- verifying- that each automatic -val v.e actuates to its correct position on a Safeguards Initiation signal.

c. At least once per 92 days by verifying that each chiller starts and runs.
  • During Modes 5 and 6 and during movement of irradiated fuel
  • !.EM assemblies, chilled water components are not considered to be inoperable solely on the basis that the backup emergency power source, diesel generator, is inoperable.

~-UN~ 1t:. I") 3/4 7-34 Amendment No. 199

I ELICTRICAI, PQ!ll SYSTIMS SURWI~ a.QOIJlDmll'l'S (Continued) cl Verifying that all non***ential automatic di***l generator trip* (i.e., other than engin* over91>9ed, lube oil pre**ure low, 4 "J:V bU9 differential and generator differential), ar~

aut-omatically bypa**ed upon lo** of voltage on the vital bu*

concurrent with a *afety injection actuation *ignal.

.#:.14~
7. Verifying the di***l generator operate* for at l*a*t 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s*.

During the fir*t 2 hour* of thi* te*t, the die**l generator *h..all be loaded to 2760-2860 kw.** During the remaining 22 hour* of this te*t, the die*el generator *ball be loaded to 2500-2600 kw**. The

  • t*ady *tate voltage and frequency *ball be maintained at a 3950 and s 4580 volts and 60 t l.2 Hz during thi* teat.
8. Verifying th.at the auto-connected loads to each diesel generator do not exceed the two hour rating of 2860 kw.
9. Verifying th.at with the die*el generator operating in a test mode (connected to it* bu*), a *imulated *afety injection signal override* the te*t mode by (l) returning the die*el generator to standby operation and (2) automatically energizing the emergency loads with offsite power.
e. At least once per ten years or after any modification* which could affect diesel generator interdependence by starting all diesel generators simultaneou*ly*, during *hutdown, and verifying that all diesel generators accelerate to at lea*t 900 rpm in less than or equ&l to 10 secon~.
f. At leaat once per 18 month9, the following te*t sh.all be performed within 5 minutes of dieael *hutdown after the diesel has operated for at least two hours at 2500-2600 kw.. :

Verifying the die*el *tart* and accelerates to 900 rpm in leas than or equal to 10 *econd**. The generator voltage and frequency shall be

~ 3950 volt* ands 4510 volts ~d 60 i 1.2 Hz within 13 seconds after the start signal.

4.8.l.l.3 The dieael fuel oil storage and transfer system *hall be demonstrated OPERABLE:

a. At lea*t once per 31 rtays by:
l. Verifying the level in each of the above required fuel storage tanks.
2. Verifying th.at both fuel transfer pumps can be started and transfer fuel from the fuel storage tanks to the day tanks.

SALEM - UNIT l 3/4 8-5 Amendment No. 17C

I

  • ELECTRICAL POWER SYSTEMS SURVEILLANCE ~OIREMENTS (Continued)
s:mam:*w1S>..:&

b.

_ _ _ _ __,,._. .._....,ss_-.,

.,. . ..,.,_aa***wr*ww----**:sz::S2a~=---s~==

At leaat once per 92 daya by verifying that a aample of dieael fuel from each of the above required fuel atorage tank* is within the accept.tile limit* apecified in Table 1 of AS'lM 0975-77 when checlced for viacoaity, water and aediment.

4.8.1.1.4 Reporta - NO'l' OSED

  • Surveillance teatinq ahall be conducted in accordance with the manufacturer'* recomnendationa reqardinq enqine prelube, warm-up and loadinq (unleaa loadinq time* are apecified in the individual Surveillance Requirement*).
    • Thia band ia meant as quidance to preclude routine exceedances of the diesel qenerator manufacturer's desiqn ratings. Loads in excess of this band for apecial teatinq or momentary variations due to chanqinq bus loads ahall not invalidate the teat .
  • SALEM - ONIT l 3/4 8-Sa Amendment No. 203

IContl.nued)

Th* connection resistance is:

s 150 m1cro ohms for inter-cell connections.

s 350 ml.ere ohms for inter-rack connections.

s 350 ml.cro ohms for l.nter-tl.er connectl.ons.

s 70 micro ohms for field cable terminal connectl.ons. "~j s 2500 ml.cro ohms for the total battery connectl.on resl.stance which l.ncludes all l.nter-cell connections (l.ncludl.ng bus barsl. all inter-rack connectl.ons ll.ncluding cable resistance). all inter-tl.er connections (including cable res1stancel, and all field terminal connections at the battery.

e. At least once per lB months by verifying that the battery charger will supply at least 170 ampere* at llS volts for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

f.

  • At least once per l8 months. during shutdown, by verifying that the battery capacity l.s adequate to supply and maintal.n in OPERABLE status all of the actual or simulated emergency loads for the design duty cycle when tbe battery is subjected to a battery service test.
g. At least once per 60 months. during shutdown, by verifying that the battery capacity is at least BOt of th*

manufacturer's rating when subjected to a performance discharge test. Satisfactory completioa of this performance discharge test shall also satisfy the requirements of Specification 4.8.l.3.2.f if the perfo~c* discharge test l.S con'~;.!Cted during a shutdown where that te*t and the battery service t**t would both be required.

h. At l*a*t once per*12 month*. during shutdown, if the battery show* *ign* of degradation Qlf ha* reacbmd &St of the serv1ce life with a capacity l*** tnan lOOt of ..nufactur*r* rating.

by vezifyincJ that the battery capacity i9 at l*a*t sot of the manufacturer'* rating when subjected to a performance di*cb.arge t**t. Cegradation is indicated when th* battery

~-l c;apac:ity drop* more than lOt of rated eapac:ity from its

~:' capacity on th* previou* performance tau, or i* below 90t of

-the manufacturer'* rating.

i. At l*a*t once per l4 month*, duriricj sliutdown; -H--thc- batte:c:y _

ha* reached BSt of the service life with capacity gre-ater than or equal to 1oot of manufacturer* rating; by verifying that th* batter/ capacity is at lea*t aot of th*

manufacturer's rating when subjected to a perform&nce

-*~Mrg* eese .

  • SALEM - 3 / 4 8 - 9& Amendment No . I ea

£IJ,CI1lICAL pgUJll SYSTEM$

SUllVEII.IANCI REQUIR!:KENTS (Continued)

2. Th* pilot call *p*cific gravity, corrected to 77*r, and full electrolyte level, 1* greater than or equal co l.200.

J. Th* pilot call voltage i* greater than or equal co 2.oa voles.

4. Th* ov*rall battery voltage i* greater than or equal co 27 volt*.
b. At lea*t once per 92 d.ay1 by verifying that:
l. The voltage of each connected call i* greater than or equal to 2.13 volt* wider float charge and ha* not decreased more than 0.27 volt* from th* value ob1erved durin1 th* original accaptanc* teu:.
2. Th* 1pecific gravity, correct*d to n*r *and full eleccrolyca level, of each connected cell i* greater than or equal to l.200 and ha* not decreased more than 0.02 from the value observed during the praviou. ceac.
3. Th* elactroly~* lev*l of each connected call 1* b*tv**n th*

minillWI and maximum level indication marka.

c. At l*a*t one* p*r lS month* by verifyin1 that:
l. Th* cell*, call plat** and battery racka *hov no vi*ual indication of phy1ical daa&&* or abnormal d*t*rioracion.

2.~ Th* call*to*c*ll and terminal connection. ar* clean, eight, and coated vith anti*corro1ion material.

3. Th* battery charger vill 1upply at l*a*t 150 ampere* ac 28 volt* for at le .. t 4 hour*.

d.~ At leaat once per 11 110nth*, during *hutdovn, by v*rifying that th* battery capacity 1* adequate to *upply and aaintain in OPERABLE atatua all of the actual or simulated e.. r1ency loada for th* design!

duty cycle when the battery i* *\abjected to a battery **rvic* ceat.

    • At leaac oace per 60 110ntha, duriftl 1hutdovn, by verifying that the battery capacity 1* at l*a*t iOt of eh* ii&iiufacturQr'= racing vbea aubjected to a performance di*chArg* test. Sati*factory cCM1pl*cion of chi* p*rformanca di*chAr1* t**t 1h&ll also 1ati1fy the requira..nta of Specification 4.1.2.5.2.d if th* performanc*

d1achar1* teac 1* conducted durin1 a shutdown vh*r* chat t**t and the battery 1ervic* t**t would both be r*quir*d

  • SALEK
  • UNIT l 3/4 1*12 Amendment No. 111

!Lls;tBICA,L powEB SYSTEMS l/f *a.J Ef.lc:tJtICAI, EOUIPMEHT PRQT~CIIVJ QEYICJS LIHITillG COllDITION roa OPERATION l.l.l.l All containment penetration conductor overc:urrent protective device*

required to provide thermal protection of penetration* *hall be OPZP.ABI.Z.

APPLICAIILITX1 MODES 1, 2, J and 4.

ASTIQN1 With one or mere of th* required containment penetration conductor overcurrene protective device(*) inoperaole1

a. Re*tor* th* protective device(*) to OPSRA9LS *tatu* or d*-*nerqize th* circuit(*) by trippin9 either th* primary or bacJaap protective device, or rackin9 out or removin9 th* primary or bacJaap device within 72 hour*, declare the affected *y*t. . or component inoperable, and verify th* primary or bacJaap protective device to be tripped, or th* pri.m&ry or backup device racJcecl 01&t or removed at lea*t once per 7 day* thereatter1 or

. b. .. in at l*a*t H0'1' STAMl)IY within th* next: I hour* and in COLD SHDTDONW within th* followin9 JO hour* *

............................................................................ ~

4.1.3.1 All required containment penetration conductor overcurrent .

protective deTic** *hall be demon*tratecl OPSRAll.&1

a. At lea*t once per 11 month**
1. .

) ror at lea*t one 4.16 ltV reactor coolant pump circuit, *uch that all reactor coolant pump circuit* are d...:tn*trated OPSJtAat.a at l***t once per 72 month*, by performance of:

(*) A CllAllRSL CAI.IIRATIOlf of th* ae*ociated protective relay*, and (b) Aft int99rated *Y*t.. functional teat which include*

aianalated autoin&tic actuation of the *y*t. . and veri!yin~

that each relay and ***ociated circuit breaker* and control circuit* function ** de*i9fted *

  • SAL&M - UNIT l 3/4 8-14 Amendment No. 13 ~

Docurr1ent Control Desk LR-N990005 Attachment 3 LCR S98-04 INSERT 1 A one time extension to this surveillance requirement which is satisfied by performance of the Manual SI test is granted during fuel cycle thirteen allowing Unit 1 operations to continue to the thirteenth refueling outage (1R13). The surveillance testing is to be completed at the appropriate time during the 1R13 outage, prior to the unit returning to Mode 4 upon outage completion.

INSERT 2 A one time extension to this surveillance requirement for performance of relay time

  • response and sequence testing of the safeguard equipment control (SEC) system, which partially satisfies the surveillance requirement, is granted during fuel cycle thirteen allowing Unit 1 operations to continueto the thirteenth refueling outage (1R13).

The surveillance testing is to be completed at the appropriate time during the 1R13 outage, prior to the unit returning to Mode 4 upon outage completion.

INSERT 3 A one-time extension to this surveillance requirement is granted during fuel cycle thirteen allowing Unit 1 operations to continue to the thirteenth refueling outage (1R13).

The surveillance is to be completed at the appropriate time during the 1R13 outage,

  • prior to the unit returning to Mode 4 upon outage completion.

INSERT 4 A one time extension to this surveillance requirement for inspection calibration and meggaring of the 1F 4KV Bus overload relays, which partially satisfies this surveillance requirement, is granted during fuel cycle thirteen allowing Unit 1 operations to continue to the thirteenth refueling outage (1R13). The surveillance testing is to be completed at the appropriate time during the 1R13 outage, prior to the unit returning to Mode 4 upon outage completion.

INSERT 5 A one time extension to this surveillance requirement for inspection calibration and meggaring of the 1A, 1B, and 1C 460 transformer relays and CT's, which partially satisfy this surveillance requirement, is granted during fuel cycle thirteen allowing Unit 1 operations to continue to the thirteenth refueling outage (1R13). The surveillance Docurr1ent Control Desk LR-N990005 Attachment 3 LCR S98-04 testing is to be completed at the appropriate time during the 1R13 outage, prior to the unit returning to Mode 4 upon outage completion

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