ML20205T391

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Proposed Tech Specs Removing Fire Protection Elements
ML20205T391
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 03/31/1987
From:
SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML20205T379 List:
References
GL-86-10, NUDOCS 8704070281
Download: ML20205T391 (41)
v • d • e


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l INDEX (

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREME PAGE SECTION 3/4.2 POWER DISTRIBUTION LIMITS 3/4 2-1 3/4.2.1 AXIAL FLUX DIFFERENCE....................................

3/4 2-4 3/4.2.2 HEAT FLUX HOT CHANNEL FACT 0R.............................

3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTNALPY RISE HOT 3/4 2-8 CHANNEL F ACT0 R. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3/4 2-12 3/4.2.4 QUADRANT POWER TILT RATI0. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3/4 2-15 3/4.2.5 DNB PARAMETERS...........................................

3/4.3 INSTRUMENTATION '

3/4 3-1 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION. . . . . . . . . . . . . . . . . . . . . . '

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3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM 3/4 3-15 INSTRUMENTATION........................................

3/4.3.3 MONITORING INSTRUMENTATION 3/4 3-41 Radiation Monitoring.....................................

3/4 3-46 Movable Incore Detectors.................................

3/4 3-47 Seismic Instrumentation..................................

3/4 3-50 Meteorological Instrumentation...........................

3/4 3-53 Remote Shutdown Instrumentation.......................... 3/4 3-56 Accident Monitoring Instrumentation...................... -

3/4 3 , "i r e - 0steet4en-Imtr u= n i.a i. i v n . . . . . . . . . . . . . . . . . . . . . . . . . . .

Radioactive Liquid Effluent Monitoring 3/4 3-67 Instrumentation........................................

Radioactive Gaseous Effluent Monitoring 3/4 3-73.

Instrumentation........................................ 3/4 3-80 Loose-Part Detection Instrumentation.....................

8704070281 970331 ADOCKOSOOg5 PDR

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IV SUMMER-UNIT 1

INDEX TING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE ION 7 PLANT SYSTEMS

.7.1 TURBINE CYCLE Safety Valves............................................ 3/4 7-1 Emergency Feedwater System............................... 3/4 7-4 Condensate Storage Tank.................................. 3/4 7-6 Activity................................................. 3/4 7-7 Main Steam Li ne Isolation Valves. . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-9 Feedwater Isolation Valves............................... 3/47-9al 4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.......... 3/4 7-10 ,

'4. 7. 3 COMPONENT COOLING WATER SYSTEM...........................

3/4 7-11 9

/4.7.4 SERVICEWATEitSYSTEM..................................... 3/4 7-12

/4.7.5 ULTIMATE HEAT SINK ...................................... 3/4 7-13 , (

./4.7.6 CONTROL ROOM NORMAL AND EMERGENCY AIR HANDLING SYSTEM.... 3/4 7-14

,/4.7.7 SNUBBERS................................................. 3/4 7-16 3/4.7.8 SEALED SOURCE CONTAMINATION.............................. 3/4 7-23 3/4 7.9 r4RE Snoparssieu (vth e Suppression Water System............................ 3 Spray an r S rinkler Systems.................... .... 3/4 7-28 i CO System............ . . ......... ................. 3/4 7-30 2

Fire Hose Stations... . . . ....... ................... 3/4 7-31 Yard Fir ants and Hydrant Hose Houses.......... . 3/4 7-33 i

3/4 ,

3B RE4 ANSSEMBM E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . t 9

3/4.7.g AREA TEMPERATURE MONITORING.............................. 3/4 7-37

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SUMMER-UNIT 1 VIII Amendment No. 23 l 1

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INDEX BASES (

t SECTION P. AGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE............................................. B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...........8 3/4 7-3 3/4.7.3 COMPONENT COOLING WATER SYSTEM............................. B 3/4 7-3 3/4.7.4 SERVICE WATER SYSTEM...................................... 8 3/4 7-3 3/4.7.5 ULTIMATE HEAT SINK........................................ B 3/4 7-3 3/4.7.6 CONTROL ROOM NORMAL AND EMERGENCY AIR HANDLING SYSTEM............................ B 3/4 7-4 3/4.7.7 SNUBBERS.................................................. B 3/4 7-4 3/4.7.8 SEALED SOURCE CONTAMINATION................................ B 3/4 7-6 3/4.7." TI"E 00"."RESSION SYSTC43......................... ....... " 3/4-7-6 3/4.7.10 FIRE RATED A55EnullE5...................... .............. 9 3/4 '-'

3/4.7. AREA TEMPERATURE MONITORING............................... 8 3/4 7-7 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8.2 and 3/4.8.3 A.C. SOURCES, D.C SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS....................... B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTION DEVICES................. . B 3/4 8-3 ,,

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I SumER-UNIT 1 XIV

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IN UMENTATION-FIR'E TECTION INSTRUMENTATION N

LIMITINGChNOITIONFOROPERATION s -

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3.3.3.7 As a m oimum, the fire detection instrumentation for a ch fire detection zone shown in Ta& e 3.3-11 shall be OPERA 8LE.

APPLICABILITY: Who ver equipment protected by the fire d action instrument is required to be OP BLE.

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ACTION: .

! With'the number of OPERA 8L fire detection instrume (s) less than the minimum

. number OPERABLE requirement Table 3.3-11 or wi two adjacent fire detection instruments inoperable in tho areas identified n Table 3.3-11 by a # symbol:

a. Within I hour establis a fire wate patrol to inspect the zone (s) with the inoperable inst ument(s) t least once per hour, unless the 4 instrument (s) is located side e containment, then inspect the containment at least once p r hours or monitor the containment 4

air temperature at least onc er hour at the locations listed in Specification 4.6.1.5 -

! b. Restore the inoperable i trument s) to OPERABLE status within 14 i days, or in lieu of any other repo t required by Specification 6.9.1, prepare and su it a Special eport to the Commissign pursuant to Specification 6.9 within the nex 30 days outlining the action 2

taken, tne cause of the inoperability d the plans and scnedule for restoring tne ins rument(s) to OPERABLE tatus.

c. The provisions of Specifications 3.0.3 and . 0.4 are not applicable.

SURVEILLANCE REQUIR ENTS

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4.3.3.7.1 Ea of the above required fire detection instrumen which are accessible d ing plant operation shall be demonstrated OPERABL at least once

! per 6 mont by performance of a TRIP ACTUATING DEVICE OPERATIONA TEST. Fire

detectors hich are not accessible during plant operation shall be amonstrated .,

OPERABL by the performance of a TRIP ACTUATING DEVICE OPERATIONAL T T during each C D SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 months.

l '4. 3 . 7. 2 The NFPA Standard 720 supervised circuits supervision associa d w h the detector alarus of each of the above required fire detection inst -

ents shall be demonstrated OPERABLE at least once per 6 months.

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SUMMER - UNIT 1 3/4 3-61 J,

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O TABLE 3.3-11 FIRE DETECTION INSTRUMENTS MINIMUM INSTRU- TO AL NUMBER INSTR ENT LOCATION MENTS OPERABLE" INSTRUMENTS HEAT SMOKE HEAT SMOKE "-

1. REACT BUILDING Zone 1 ev 412' Room -01 NE 3 Room 12- 1 SE 2 3 Room 12-0 SW 2 3 i Room 12-01 2 3 Zone 2 Elev. 43 Room 12-03 l 1 2 Room 12-07 1 2 Room 12-08 1 2 Zone 3 Elev. 436' Room 36-01 NE 2 3 Room 36-01 SE 2 3 Room 36-01 NW 2 3 Room 36-01 SW 2 3

- Zone 4 Elev. 462' Room 12-03 1 2 Room 12-07 1 2 Room 12-08 1 2

ene ~CO Eles. 495' Room 12-08 1 2 Zone 000 Elev. 514' (

Room 63-01 SE 2 3 Room 63-01 5 1 2 Zone PPP Elev 495' .  ;

Room 12- 1 2 Room 1 07 2 Zone PP Elev. 514' Ro 63-01 NE 1 1 -

om 63-01 NW '3, 6,

2. NTROL BUILDING ,

Zone A Elev. 448' Room 48-02 (Cable Spreading

  • Room-Upper) 17** 18""

Zone A Elev. 436' Room 36-03 ._ 3** 4"*

Room 36-04 1* * . **

SUMMER - UNIT 1 3/4 3-62 Amendment No.15

.- -r, INSTR ENT LOCATION TABLE 3.3-11 (Cont. )

MINIMUM INSTRU-TOTALNUM8fR

[ f MENTS OPERABLE" 0F INSTRWENTS HEAT SMOKE HEAT SM0KE

2. CONT \lLBUILDING(Cont.)

Zone E, Elev. 425' Roon 5-02 (Cable Spreading Room-Lower) 10** 11**

Zone 8 Ele 412' Room 12-0 3** 4**

Room 12-04 1* 2**

Room 12-04A

  • 1**

' Zone B Elev. 400 Room 00-01 1**

Room 00-01A 1**

1** 1**

Zone F Elev. 463' Room 63-03 3** 4**

Room 63-04 1**

2**

Zone J Elev. 436' Room 36-01 2** 3**

Room 36-02 2"* 3"*

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I Zone J Elev. 448' Room 48-01 21** 22**

re < Elev. 412' Roc- 12-:2 C'- 3**

Zone K Elev. 425' Room 25-01 21 " 22*"

Room 25-03 1* 2*

Room 25-04 1"" 2*

Zone L Elev. 43 Room 36-11 # #

4 7 l Zone M Ele 436' Room 3 -10 1 2 l Zone lev. 448' '

R m 48-02 (Cable Spreading Area

/ For HVAC & MC8 Cabinets) 13, 25, , l Zone O Elev. 463' Room 63-02 1** 2*

l Zone P Elev. 463' Room 63-05 (main Control Board) 3, 6, Zone R Elev. 463' Room 63-05 (PVAC Control Board) 1 SUMMER - UN*T 1 3/4 2-63 Amendment No. l3

TABLE 3.3-11 (Cont.) ,

I MINIMUM INSTRU- T AL NUMBER INS BUMENT LOCATION MENTS OPERABLE

  • F INSTRUMENTS HEAT SM0KE HEAT SM0KE
2. CONTROL BUILDING (Cont.) .~

Zone Elev. 448' '

Roo 48-02 (Cable Spreading Area for HVAC & MCB Cabinets) 2#

23# l Zone T Elev. 436' i Room 36-10 2*** 3***

Room 36-11 2** 23***

Zone U Elev. 436' Room 36-09 2*** 3***

Zone I Elev. 436' Room 36-11 5# 10#

Zone VV Elev. 436' Room 36-09 1 2.-

i Zone W Elev. 463' Room 63-05 4 8 Room 63-06 1 1 Room 63-07 1 2 Room 63-09 1 1 Roc- 62 .'~. 1 1 Room 63-11 1 1 Room 63-12 1 1 Room 63-13 1 1 Zone XX Elev. 63' Room 63-1 1 1 Room 63- 5 1 1 Room 6 16 1 Room 3-17 1 1 Roo 63 18 1 2

, Ropm 63-19 1 1

S6cm 63-20 1 1 oom 63-21 1 1
Room 63-22 1 2 Room 63-23 1 1 Zone NNN Elev. 482' Room 82-01 4,, 8, Room 82-02 4 7, Room 82-03 2 3 Room 82-04 1 Zone TTT Elev. 412'
  • Room 12-11 1 2 SUMMER - UNIT 1 _, 3/4 3-64 _ _ _

Amendment _No. 15 , _ . _

TABLE 3.3-11 (Cont.)

MINIMUM INSTRU- TOTAL NUMBER / .

INShRUMENTLOCATION MENTS OPERABLE

  • OF INSTRUMENTS / l
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HEAT LM0KE E HEAT SM0(E

6. AUXI ARY BUILDING (Cont.)

l Zone QQ 1ev. 452' Room -01 1 1 Room 5 02 1 1 Zone RR Elev. 463' Room 63-16 2** 3**

Room 63-19 1** 1**

Zone ZZ Elev. 374 Room 74-12 -

1 Room 74-16 2 3 1

i Room 74-17 -

2 3 Zone AAA Elev. 388' Room 88-23 1 1 Room 88-24 1 1 Room 88-25 1 l' Zone AAA Elev. 397' Room 97-02 # #

3 6 Room 97-02 N 1 1 Room 97-02 5 1 2 2:..e EEE Erev. 388' Rec.; S3-05 1 2 Room 88-13 N 2 3 Room 88-13 NE 1 1 Room 88-13 5 1 1 Zone BBB Elev. 397' Room 97-01 1 2 Zone BBB Elev. 400'

Room 00-01 W 1 1 Room 00-02 E 3 Zone CCC E1*ev!. 63' Room 63-0p 2 3 Room 63- 4 1 2 Zone EE lev. 374' Roo 74-01 1 . 2 R m 74-07 1 2 oom 74-08 2, Room 74-09 3, 3 5 Room 74-18 1 1 Zone GGG Elev. 400' Room 00-01 # * #

3 SUMMER - UNIT 1 3/4 3.-66a Amendment No.li

I TABLE 3. 3-11 (Cont. )

MINIMUM INSTRU- TOTAJ, NUMBER INSTRUMEN LOCATION MENTS OPERABLE" 0F , INSTRUMENTS HEAT SMOKE dAT SM0KE

6. AUXILIARY UILDING (Cont.) ' '

Zone HHH Ele . 412' '

Room 293-0 W 1 Room 12-06 1 Zone HHH Elev. 42 '

Room 26-01 5, 10, Room 26-02 W 1 1 Room 26-02 S 1 1 Zone III Elev. 412' Room 12-02 1 1 Room 12-03 A 1 1 Room 12-09 1 1 Room 12-11 N 1 1 Room 12-15 1 1 Room 12-18 1 1-Room 12-28 1 1 -

Room 12-31 1 1 Zone JJJ Eiev. 4'2 .

Roc '.2-02 1, 1, R:: "2-1".

. 7 R c e ". 2 ~.". *, '

. 1 Z:ne . . Elev. 436 Roc- 36-33 N 2 3 Roc- 35-18 3 Zone RRR Elev. 388' Room 88- 1 1 Room 8 13 1 2 Room -13 5 1 1 Roo 88-16 1 1 Zon WW Elev. 448' -

oom 48-01 3, 5, one WW Elev. 446' '

Room 46-01 1 1

. s SUMMER - UNIT 1 3/4 .3-fic Amenoment No,15

TABLE 3.3-11 (Cont. )

MINIMUM INSTRU- TOTAL MBER INST MENT LOCATION MENTS OPERABLE

  • OF IN. RUMENTS HEAT SMOKE. HEA[ SMOKE INTERMED ATE BUILDING (Cont.)
3. EASTMENETRATIONACCESSAREA Zone J Elev. 412' l Room -02 5 10 Zone LL El v. 436' Room 36-D #

5 10

4. WEST PENETRATION AREA l

! Zone Y Elev. 412 Room 12-01 4, 8, Zone 00 Elev. 436' Room 36-01 # #

4 8 Zone II Elev. 463' '

Room 63-01 2 . 3 Room 63-03 # #

3 6

5. INTERMEDIATE BUILDING ,

l Zone AA Elev. 412' Room 12-02 15** 16"*

Room 12-02 W 4"* 5""

Room 12-02 5 1"* 1*"

Roo.- 12-09 1-" 1*"

Room 12-13 A 1" 1""

Room 12-13 8 1"* 1**

Room 12-13 C 1"* 1**

Zone BB Elev. 412' Room 12-02 10** 11**

Room 12-02 E -

6** 7"*

Room 12-10 1** 1**

Zone CC Elev. 436' Room 36-02 SW 3** 4** I Zone FF Elev. 42 -6" Room 236-01 #

3 5 .

Zone GG Elev. 12' l Room 12-0 1 1 l Room 12- 4 1 . 1 Room 12f 05 1 2 Room 2-06 1 2 Room 2-07 1 1 Roo 12-08 1 1 Rgdm 12-12 1 1 36cm12-14 1 1

/Hoem 12-15 1 1 l SUMMER - UNIT 1 3/4 3-65 Amendment No.15

i TABLE 3.3-11 (Cont.) j/

/ l MINIMUM INSTRU- TOTAL fNUMBER INS UMENT LOCATION MENTS OPERABLE

  • OF INSTRUMENTS HEAT SMOKE HE[T SM0KE
5. INTE EDIATE BUILDING (Cont.) f '"'

Zone KK lev. 412' Room -09 1 1 Zone KK Ele 423' Room 23-01 2,, 4, g Room 23-02 2 4, Zone KK Elev. 436 Room 36-01 2 3 Zone MM Elev. 463' Room 63-01 4 ,, 8,,

Room 63-02 3 . 6 Room 63-03 1 2 Zone PP Elev. 436' Room 36-02 8, 16, Room 36-03 (CREP) 1 2 -

Room 36-03 A (CREP) 1 2 Room 36-03 8 1 2 Room 36-04 1 1 I: e W. Elev. 451' ,

Room 51-01 2, 6,f Room 51-02 3 6 Room 51-03 1 2 Room 51-04 1 2 i

Zone FFF Elev. 436' Room 36-0 8, 16, 1 Room 36- 2 E 1 1 .

1 1

Zone UU Elev. 426' l Roo 26'01 2, 4 ,,

R m 26-02 2 4 y .

! 6. ALJ ILIARY BUIOLING l Zone Q Elev. 436' Room 36-18 2, 4, Zone HH Elev. 463' Room 63-01 1 2 Room 63-04 1 1 Room 63-06 1 J

Room 63-17 1

  • 1 SUMMER - UNIT 1 3/4 3-66 Amendment' No.15\

TABLE 3.3-11 (Cont. )

g MINIMUM INSTRU- TOTAL NUMBp INSTRUMENT LOCATION MENTS OPERABLE

  • OF INSTRUMNTS HEAT SMOKE HEAT SMOKE
6. AU LIARY BUILDING (Cont.) [

i Zone YY Elev. 412' Ro 12-05 1 1 Room 2-27 1 1 Room -30 ,1 ,

1 Zone ZZZ E1 . 445' Room 45-01 1 1 Zone ZZZ Elev. 4 6' Room 36-01 1 1 Room 36-03 1 2 Room 36-31 1 1 -

Room 36-33 S 1 2

7. FUEL HANDLING BUILDING l

Zone EE Elev. 436' Room 36-01 W 2 3

. Room 36-01 E 1 1 l Zone EE Elev. 443'-6" .

Room 436-01 1 1

..e TT E'.e. 463' Room 63-01 5 10 Room 63-01 N ,

5 10 Zone UU Elev. 463' Room 63-01 -

7" 13 Room 63-01 S 5 9 Zone YY Elev. 412' Room 12-01 4

8. SERVICE WATER P PHOUSE Zone NN Elev. 425'

, Room 25- 1, 2, Room 25 5 3 6 Zone 00 lev. 441' Roo 41-02 1** 1**

Zon 00 Elev. 436' Room 36-01 8"" 9""

SUMMER - UNIT 1 3/4 3-66c Amendment No.15'

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1 TABLE 3.3-11 (Cont.)

. MINIMUM INSTRU- TOTAL BER INSTRUMENT OCATION MENTS OPERABLE

  • OF I. TRUMENTS HEAT SM0KE Held SM0KE L

Zone D00 E v. 441' Room 41- 3, 5, l Room 41-01 1 1 Zone VW Elev. 5' ,

Room 25-03 1 1

9. DIESEL GENERATOR BUI ING ,

g Zone DG Elev. 436' Room 36-01 2**

Room 36-02 1** 2**

Room 36-03 7"* 8**

Room 36-04 7"* 3**

Zone DG Elev. 427' Room 27-03 1"* 1**

Room 27-04 1** 1** -

Zone KKK Elev. 400' Room 00-01 1 1 Room 00-02 1 1

,e .e,; Eis. 427 R:.cm 27-7. I 1 Re m 27-02 1 1 Rece 27-03 2 3 Roc- 27-0 2 3 "Tne fire c .ec* ion instruments located witnin tne Reac or Building are not required o be operable curing performance of Type A Co tainment Leakage Rate T ts.

""Aut atically Actuates Preaction Sprinkler System.

""" utomatically Actuates Low D. essure CO System.

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PhiSYSTEMS 3/4\.9 FIRE SUPPRESSION SYSTEMS FIRE S PRESSION WATER SYSTEM LIMITING C ITION FOR OPERATION 3.7.9.1 The f a suppression water system shall be OPERA 8LE with:

a. Two fi suppression pumps, each with a capacity of 2 0 gpe, with their di charge aligned to the fire suppression hea r, and
b. An OPERA 8L flow path capable of taking suction on the circulating water intak structure and transferring the wat through distri-bution pipin with OPERA 8LE sectionalizing co rol or isolation valves to the ard hydrant curb valve, the I t valve ahead of the water flow ala device on each sprinkler hose standpipe, and the last valve ahdad f the deluge valve on e h deluge or spray system required to be OP 8LE per Specificati s 3.7.9.2, 3.7.9.4, and 3.7.9.5.

APPLICA8ILITY: At all times. .

ACTION:

a. With one pump inoperable, es re the inoperable pump to OPERA 8LE status within 7 days or, in feu of any other report required by Specification 6.9.1, prepar nd submit a Special Report to the

~ Commission pursuant to Sp ifi ation 6.9.2 within the next 30 days outlining the plans and rocedu es to be used to restore the inoper-able equipment to OPE LE statu or to provide an alternate backup pump or supply. The rovisions o Specifications 3.0.3 and 3.0.4 l are not applicable.

b. With the fire s ression water syst otherwise inoperable:
1. Establis a backup fire suppressio water system within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> , and
2. In 1 ou of any other report required b Specification 6.9.1, su it a Special Report in accordance w h Specification 6.9.2:

) By telephone within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b) Confirmed by telegraph, mailgram, or fa imile trans-mission no later than the first working y following the

{ event, and c) In writing within 14. days following the evenk outlining I the action taken, the cause of the inoperabili y and the plans and schedule for restoring the system to PERA8LE status.

St#WER - UNIT 1 3/4 7-25

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P T SYSTEMS SURVE\LANCEREQUIREMENTS 4.7.9.1.1 fire suppression water system shall be demonstrated OPE

a. At le t once per 31 days by starting the electric motor iven pump and ope ting it for at least 15 minutes. ,. ,
b. At least o e per 31 days by verifying that each va e (manual, power operat or automatic) in the flow path is its correct position.
c. At least once per months by cycling eac estable valve in the flow path through at least one complete cle of full travel,
d. At least once per 18 no hs by perfo ng a system functional test which includes simulated tomatic ctuation of the system throughout its operating sequence, an
1. Verifying that each p velops at least 2500 gpa at a system head of 125 psig
2. Cycling each valv in the flow th that is not testable during plant operatio hrough at least ne complete cycle of full travel, and -
3. Verifyin that each fire suppression p starts (sequentially) to mai ain'the fire suppression water s tem pressure greater than r equal to 85 psig.

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e. At le t once per 3 years by performing a flow tes of the system in acc dance with Section 11, Chapter 5 of the Fire Pr action Handbook, I h Edition, published by the National Fire Protectio Association.

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SUPMER - UNIT 1 3/4 7-26

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PLANTSYSTEMS SURVEILLANCEREhUIREMENTS(Continued) /

1 4.7.9.1.2 The fire pump diesel engine shall be demonstrated OPERA E:

a. At least once per 31 days by verifying:
1. he fuel storage tank contains at least 150 g lons of fuel, ad
2. The diesel starts from ambient condition and operates for at leas 30 minutes on recirculation flow.
b. At least on per 92 days by verifying th a sample of diesel fuel from the fuel storage tank, obtained in ccordance with ASTM-0270-1975, is within the captable limits specif'ed in Table 1 of ASTM 0975-1977 when checked fo viscosity, water an sediment.

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c. At least once per 8 months, duri shutdown, by subjecting the diesel to an inspec ion in accor ance with procedures prepared in conjunction with its anufactu er's recommendations for the class of service.

4.7.9.1.$ The fire pump diesel st ,ing 24 volt battery bank and charger shall be demonstrated OPERABLE: .

a. At least once per 7 ys by erifying that:
1. The electrol e level of ch battery is above the plates, and
2. The overa battery vcitage 's greater tha. or eoual to 24 volt .
b. At least ce per 92 days by verifyi that the specific gravity is appropr te for continued service of t a battery.
c. 'At 1 st once per 18 months by verifying that:

1 The batteries, cell plates and batte racks show no visual indication of physical damage or abnorm 1 deterioration, and

2. T'he battery-to-battery and terminal conne(tions are clean, tight, free of corrosion and coated with an i-corrosion material.

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PLANT SYSTEMS -

5 SAY AND/OR SPRINKLER SYSTEMS '

! LIMITJNG CONDITION FOR OPERATION 2

s 3.7.9.2 The following spray and/or sprinkler systems shall be OPE LE: ,, ,

a. el Handling Building Charcoal Filter Plenums
b. Co rol Room Emergency Charcoal Filter Plenums
c. Diese Fire Pump Room Wet Pipe Sprinkler System
d. Diesel nerator Building Preaction Sprinkler stem
e. Control 8 'lding Preaction Sprinkler System
f. Service Wate Pump House Preaction Sprink r System
g. Intermediate B *1 ding Preaction Sprink r System
h. Auxiliary Buildin Preaction Sprinki r System APPLICABILITY: Whenever equip nt protect by the spray / sprinkler system is required te be OPERABLE.

ACTION:

a. With one or more of the o required spray and/or sprinkler systems inoperable, within one our e tablish a continuous fire watch with' ,.

backup fire suppress' n ecuipm t for these areas in whien redundant systeies or compone s coulc be c aged; for other areas establish an heerly fire watch atrol. Restere One system te GFERABLE status withir. 14 days , in lieu of a y owner report eouired by Soecifica-

'en E.9.1. p . pare an: se::i: a Soe:'=1 Reso ; tc the Ccer'ssion
.rsuar.: te .:e;ificatien E.E.: i-h'r ne nee: 30 ca;.s cutiining

- e actier taken, tne cause of ne inope bility ano ne plans and senecule for restoring the system to OPERA LE status.

t. Tne : cvisions of Specification 3.0.3 and 3. 4 are no a: licable.

SJRVEILLANC~ REQUIREMEN'TS l /

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' N 4.7.9.~ Each of the above required spray and/or sprinkler syl ems shall be demon rated OPERABLE:

j a. At least once per 31 days by verifying that each valve anual, power operated or automatic) in the flow path.is in its e rect

position. ,

D. At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel.

l SUMMER - UN'T 1 3/4 7-28 Amenament Nc. 15

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< . PLANT SYSTEMS ,

! 56RVEILLANCE REQUIREMENTS (Continued)

c. least once per 18 months:
1. performing a system functional test which ludes simulated aut tic actuation of the preaction sprin r system, and:

I a) Ver ying that the automatic valv in the flow path actua to their correct positi s on a preaction system test si 1, and b) Cycling each lve in t flow path that is not testable during plant op tio through at least one complete cycle of full travel.

2. By a visual inspe ion of the pipe, spray and sprinkler headers to ver their integrity, and
3. By a visu inspection of each nozzle' spray area to verify the spr pattern is not obstructed. -
d. At leas nce per 3 years by performing an air flow st through each en head spray / sprinkler header and verifying e open head spr / sprinkler nozzle is unobstructed. ,

l 6

SUMMER - UNIT 1 3/4 7-29 9

,- - . _ _ , , - - _-.-7 . , , _ . . . , , _ ,- _ _ ,

_.9 +

,m .. ,

l l

PLANT SYSTEMS CO SYSTEM

' 2

\

LIMITING CONDITION FOR OPERATION

\ f l

3.7.9.3 The Re ey Room - Control Building Elevation - 436' low pres re CO l system shall be OPERA 8LE. 2 "'

1 APPLICA8ILITY: When ver equipment protected by the CO system i required to 2

be OPERABLE.

ACTION:

3. With the above re ired C0 system inoperable, ithin one hour establish a contin usfir$watchwithbackupfiresuppression equipment. RestorelhesystemtoOPERABLE atus within 14 days or, in lieu of any other report required by S cification 6.9.1, prepare andsubmitaSpecialRe@rttotheCommi ion pursuant to Speci-fication 6.9.2 within t next 30 days utlining the action taken, the cause of the inoperabi ity and th plans and schedule for restoring the system to OPE LE st us. .
b. The provisions of Specificatio .0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS

/ \ "

4.7.9.3.1 The above required C0 stem shall be demonstrated OPERABLE at least once per 31 days by verify g that each valv (manual, power operated or automatic) in the flow path is 'n its correct posit n.

4.7.9.3.2 The above requir low pressure CO system s all be demonstrated 4 2 OPERABLE:

a. At least once er 7 days by verifying the C0 7 sto ge tank level to be greater an 85% and pressure to be greater tha 275 psig, and
b. At least nce per 18 months by verifying:
1. e system valves and associated ventilation damper and fire door release mechanisms actuate manually and automati 11y, upon receipt of a simulated actuation signal, and
2. Flow from each nozzle during a " Puff Test."

I l

l SUMMER - UNIT 1 3/4 7-30

~

. PLMTSYSTEMS j FIRE SE STATIONS LIMITING ONDITION FOR OPERATION

/

3.7.9.4 Th fire hose stations shown in Table 3.7-5 shall be OPERABLE ,

1 APPLICABILITY: Whenever equipment in the areas protected by the fi hose I stations is reg ' red to be OPERABLE.

ACTION:

a. With one o more of the fire hose stations shown i Table 3.7-5 inoperable, rovide gated wye (s) on the nearest 0 RABtE hose station (s). ne outlet of the wye connected to he length of hose at the station the other outlet of the wye co nected to a hose of sufficient leng to provide coverage for th area unprotected by the inoperable h a station. This shall b accomplished within I hour if the inop rable fire hose is the rimary means of fire suppression; otherw e, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Restore the fire hose station to OPERABLE atus within 14 d s or, in lieu of any other report required by Spe ification 6.9. , prepare and submit a Special Report to the Commissio pursuant t Specification 6.9.2 within the next 30 days outlining t action /aken,thecauseoftheinoper-ability, and plans and sc dule for restoring the station to OPERABLE status. /
b. The provisions of Specificat' ns 3.0.3 and 3.0.4 are not applicabie. '

SURVEILLANCE REOUIREMENTS

/ \

a.7.9.4 Eacn of the fire nose .ations snowr. in Tacle L 7-5 sha be i.-- : .ra ed CPER*BLE:

a. At least once per i days by a visual 'nspection of tne fire hose stations accessi le during plant operat. n, to assure all required equipment is at the station.
b. Atleastonc[per18monthsby:
1. Remo ng the hose for inspection and re- acking, and
2. In ecting all gaskets and replacing any graded gaskets in e couplings.
3. Visual inspection of the fire hose stations n t accessible during plant operation to assure all required uipment is at the station. '-
c. At least once per 3 years by:
1. Partially opening each hose station valve to verify alve OPERABILITY and no flow blockage.
2. Conducting a hose hydrostatic test at a pressure of 15 sig or at least 50 psig above maximum fire main operating press re, whichever is greater.

- \

SUMMER - UNIT 1 3/4 7-31

PLA\N SYSTEMS .

TA'LE 8 3.7-5

\

FIRE HOSE STATIONS LOCATIO * -

ELEVATION HOSE REEL / RACK ENTIFICATION** l Auxiliary Buil 'ng 374 4138, 4140 I42 388 4144, 6764, 4145 I 412 6766, 676 , 6763 436 6783, 67 S, 4148, 4147 463 6784, 55, 4149 397 4143 Reactor Building '

412 67 8, 6780, 6776 a

436 77, 6782 463 6781, 6779 Fuel Handling Building 36 6802 3 6804, 6807 .

Control Building 412 6812, 6813 425 4067, 4069 436 6808, 6814 -

448 4068, 4070 463 6809, 6933 '~

_ 482 - 6815, 6810 Inter eciate Building 2 4128, 4121, a122 436 4129, 4124. 4123 463 413:

I

" List all Fire Hose Stations required to ensure the OPERABILITY of fety related equipment.

"" Identified by isolation valve number l

l l SUM *4ER - UNIT 1 3/4 7-32 Amendment Nc.15

. PLANT SYSTEMS YARD RIRE HYDRANTS AND HYORANT HOSE HOUSES j/

LIMITINbCONDITIONFOROPERATION 3.7.9.5 Th yard fire hydrants and associated hydrant hose houses shown in Table 3.7-6 all be OPERABLE.

APPLICABILITY: hen'ever equipment in the areas protected by the ya fire nycrants is requi ed to be OPERABLE.

ACTION:

a. With one or ore of the yard fire hydrants or asso ated hydrant i hose houses s own in Table 3.7-6 inoperable, wit n 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> have sufficient add ional lengths of 2 1/2 inch dia eter hose located in an adjacent OPE BLE hydrant hose house to pr ide service to the unprotected area ( if the inoperable fire drant or associated hydrant hose house 's the primary means of ire suppression; otherwise, provide t e additional hose w' hin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Restore the hydrant or hose house o OPERABLE statu within 14 days or, in lieu of any other report req ired by Speci cation 6.9.1, prepare and submit a Special Report the Commi sion pursuant to Specifica-i tion 6.9.2 within the nex 30 days utlining the action taken, the cause of tne inoperacility, and e plans and schedule for restoring the hydrant or hose house to P- BLE status,
b. The provisions of Specificati 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS

/ \

, 1.7.9.5 Each of the yard fir nycrants and ass: iate: My: ant 5cse houses shown in Table 3.7-6 snail b demonstratec OPERA 5L':

a. At least once p 31 days by visual inspec ion of the hydrant hose house to assur all required equipment is a the hose house.
b. At least on per 6 months (once during March, April or May and once during Sep ember, October or November) by visua ly inspecting each yard fir hydrant and verifying that the hydrant arrel is dry and that t hydrant is not damaged.
c. At 1 ,st once per 12 months by
1. Conducting a hose hydrostatic test at a pressure f 150 psig or at least 50 psig above maximum fire main operat g pressure, .

whichever is greater.

~

2. Inspecting all the gaskets and replacing any degraded askets i in the couplings. ,
3. Performing a flow check of each hydrant to verify its  ;

OPERABILITY. l SUMMER - UNIT 1 3/4 7-33

3 PLANT SYSTEMS TABLE 3.7-6 I

YARD FIRE HYDRANTS AND ASSOCIATED HYDRANT HOSE HOUSES LOCATION HYDRANT NUMBER

  • EQUIPMENT I.D. ,[

West o Service Water Pumchouse 3 XFX-1N-FS North o Diesel Generator Building 2 XFX-1M-FS I

I I

Tnese nycrant numbers are the numbers physically indicated on the hy ant houses

)

N

\,

' PLA SYNEMS 3/4.7 FIRE RATED ASSEMBLIES LIMITING NOITION FOR OPERATION -

. ,- _. - . s _.m . _ _ _ -

3.7.10 All fi barrier assemblies (walls, floor / ceilings, cable tray closures and other fire b rriers) separating safety-related fire areas or separfting portions of redun nt systems important to safe shutdown within a ftpd area and all sealing dev ces in fire-rated assembly penetrations (fire 46crs, fire windows, fire damper cabig and piping penetration seals an'd ven ilation seals),

shall be OPERABLE.

AFPLICABILITY: At all t es.

ACTION:

a. With one or more f the above required fiye rated assemblies and/or sealing dev es inoperable, with 6 one hour either, establish a continuo s fire watch on least one side. of the affected assemoly, or verify the PERABILITY of the fire detectors on at least e side of e inoperable assembly and establish an hourly fre wate patrol .* Restore the -

inoperable fire rated ass ..bly d' sealing device to OPERABLE m status within 7 days or, i 11 u of any other report required by Specification 6.9.1, prep e and submit a Special Report to the Commission pursuant pecification 6.9.2 within the -

l next 30 days outlining th acti n taked, the cause of the 1 inoperable fire rated a embly a /or sealing device and the plans ant. schedul for restori g the fire rated assembly and sealing device t(' OPERABLE stat .

b. The provisions of ecifications 3.0.3 and 3.0.4 are not applicable.

{

(

I

  • For at period, of plant operation prior to initially achieving critica ity th requirement to verify the OPERABILITY of the fire detectors on at lea t

( o e side of the inoperable assembly is waived..

SUMMER - UNIT 1 3/4 7-35 Amendment No. 1

, p(AMT SYSTEMS' RVEILLAMCE REQUIREMEHTS 4.7.10. At least once per 18 months the above required fire ra'ted ass lies' and penet tion sealing devices shal1~be verified 0PERABLE by:

~

a. Per ing. a' visual inspection of'the expose-d'an'fav =
  • _ rated- ,sembly. = ~
  • ' " ~

r

==- rtra

b. Performing visual inspection of each fire windo fire damper /and associated ha are. ~

i ,

. c. Performing a visu irispection of at least J percent of each type of sealed penetrati . If apparent chan et in appearance or abnormal degradations are foun a visual inspec on of an additional 10 per-cent of each type of se ed penetrati n shall be made. This inspection process shall tinue il a 10 percent sample with no apparent'. changes in appear.an or abnormal degradation is found.

4.7.10.2 Each of the above required f' e ors shall be verified OPERABLE by inspecting the automatic hold-open, lease a closing mechanism and latches

at 1 cast once per 6 months, and by erifying
a. The position of eac closed fire door at ast once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. .
b. That doors with utomatic hold-open and releas mechanisms are free of obstructio at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c. The positt n of each locked closed fire door at leas once per 7 days.
d. Th PERASILITY of the fire door supervision system by per qming a IP ACTUATING DEVICE OPERATIONAL TEST at least once per 31 da 's.

i D

., g  ;*

G l '.

SUPRER - UNIT 1- -

3/4 7-36

. - - - --- -----l

. INSTRUMENTATION u

g J BASES 3/4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety. This capability is required to permit comparison of the measured response to that used in the design basis for the facility to determine if plant shutdown is required pursuant to Appendix "A" of 10 CFR Part 100. The instrumentation is consistent with the recommendations of Regulatory Guide 1.12, " Instrumentation for Earth-quakes," April 1974.

3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION
The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs," February 1972.

3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that i @A4 sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room. This capability is required in the event control room habitability is lost and is i

consistent with General Design Criteria 19 of 10 CFR 50. i 3/4.3.3.6 ACCIDENT MONITORING INSTRUMENTATION I The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG 0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."

4/4. 3. 3. 7 FIRE DETECTION INSTRUMENTATION MEILABILITY of the fire detection instrumentation ensures,thatkate j warning ca Mp is available for the prompt detectiorLof' fires. This capability is re 1

' ed in order to detect and locatenres in their early stages. Prompt det(ectisyf fires will reduce'tTie potential for damage to safety related equipment antb' an integra'T element in the overall facility j fire protection program.

I In the event that ayortion of the fir detection instrumentation is  ;

inoperable, the estabTishment of frequent f(ire' patrols in the affected areas is required is restorea ,t.01irovide to OPERABILITY. detection capat.ility until thes noperable instrumentation  !

7 SUMMER - UNIT 1 B 3/4 3-3 J

____._._._._.m _ . _

f l PLANT SYSTEMS ,

l BASES 3/4.7.8 SEALED SOURCE CONTAMINATION

-~-

The limitations on removable contamination for sources requiring leak i testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.

i Sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a source in that group. Those sources which are frequently handled are required to be tested more often than those which are not. Sealed sources which are continuously enclosed within a shielded mechanism (i.e. sealed sources within I

radiation monitoring or baron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

i

/4. 7. 9 FIRE SUPPRESSION SYSTEMS N

OPERA 8ILITY of the fire suppression systems ensures that ade ate fire supp ssion capability is available to confine and extinguish res occurring in ny portion of the facility where safety-related paent is located. The e suppression system consists of the water s es, spray and/or sprinklers, 0 , fire hose stations, and yard fire h rants. The collective capabilit 2 f the fire suppression systems is dequate to minimize potential damage to saf -related equipment and is a jor element in the facility fire protection p}e ram.

l l In the event that portions the fire su ression systems are inoperable, alternate backup fire fighting equ nt is equired to be made available in i

the affected areas until the inoperab e ipment is restored to service.

When the inoperable fire fighting equi is intended for use as a backup l means of fire suppression, a longer riod o time is allowed to provide an s erable i

alternate means of fire fighting an if the in equipment is the f primary means of fire suppress .

f The surveillance re i'rements provide assurance th the minimum OPERA 8ILITY l requirements of the fir suppression systems are met.

In the event e fire suppression water system becomes inop able, immediate i corrective meas es must be taken since this system provides the ma r fire

} suppression pability of the plant. Therequirementforatwenty-fohuhour

report to e Commission provides for prompt evaluation of the acceptabi Nty

) of the rrective measures to provide adequate fire suppression capability fo(

l

the tinued protection of the nuclear plant. N 1

SumER - UNIT 1 B 3/4 7-6

k . .g PLANT SYSTEMS ,

8ASES 4M0 FIRE RATED ASSEMBLIES I

i The OPERA 8IL the fire barriers and barrier penetratio e that fire damage will be limite . ese design features nietz the possibility of a single fire involving more t rea prior to detection and extinguishment. The firepi , tre enetrations for conduits, i

cable trays a iping, fire windows, fire dampers, fire doors are inspected to verify their OPERA 8ILITY. )

3/4.7. AREA TEMPERATURE MONITORING The area temperature limitations ensure that safety-related equipment will not be subjected to temperatures in excess of their environmental quali-fication temperatures. Exposure to excessive temperatures may degrade equipment and can cause a loss of its OPERA 8ILITY. The temperature limits include an allowance for instrument error of 2*F.

I l

l SUMER - UNIT 1 8 3/4 7-7

.. . . I l

l

. i 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY ,

6.1.1 The Director, Nuclear Plant Operations shall be responsible for overall unit operation and shall delegate in writing the succession to this responsi-bility during his ab'sence. The title Director, Nuclear Plant Operations, is O synonymous to the titles Manager, Virgil C. Summer Nuclear Station, Station Manager or Plant Manager.

6.1. 2 The Shift Supervisor shall be responsible for unit operations. A management directive to this effect, signed by the Vice President, Nuclear Operations, shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for unit management and technical support shall be as shown on Figure 6.2,-1.

UNIT STAFF -

6.2.2 The unit organization shall be as shown on Figure 6.2-2 and: '

c. Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

4

b. At least one licensed Reactor Operator shall be in the control room .

when fuel is in the reactor. In addition, while the unit.is in MODE 1, 2, 3 or 4, at least one Lic'ensed Senior Reactor Operator j shall be in the Control Room,

c. A health physics technician # shall be on site when fuel is in the reactor.

l d. All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator i/

Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

/

b te Fire Spigade of at least 5 members shall ained onsite at all 1 . he Fire Brigade sh nc ude the Shift Supervisor and the other 2 mem e s

shutdown of and any persinimum shift crew necessary for safe /

uired for other essential .

ns during a fire emergency.

The health physics technician M c8 reBrig.d.compositionmaybelessthan'[

the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order " i to accommodate unexoected absence provided immediate action is taken to fill the required positions.

SUMMER - UNIT 1 6-1 Amendment No.18 l

~ .

/ t.P'11NISTRATIVE CONTROLS e f Administrative procedures shall be developed and implemented to limit the

} E working hours of unit staff whc perfore safety-related functions; e.g.,

senior reactor operators, reac 3r operators, health physicists, auxiliary -

operators, and key maintenance norsonnel. -

Adequate shift coverage shall be maintained without routine heavy use of T

overtime. However, in the event that unforeseen problems require

/ substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance or major plant modifications, on a temporary basis, the following guidelines shall be followed:

a. fn individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />

) itraight, excluding shift turnover time.

b. An in'aividual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any seven day period, all excluding shift turnover time.
c. A break of at least eight hours should be allowed between work periods, including shift turnover time.
d. Except during extended sh'utdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

) Any deviation from the above guidelines shall be authorized by the Director, Nuclear Plant Operations or his deputy, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation. Except during extended shutdown periods, con-trols shall be included in the procedures such that individual overtime shall be reviewed monthly by the Director, Nuclear Plant Operations or his designee to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.

b

)

6-la Amendment No. AA, 51 SIM4ER - UNIT 1

a f .

Q .

PRE 5M NT h

H AND CHIEF OM RAf 8NG Of f KE R

>4 sa E NECUTivE VKE PRESIDENT OPE RATeON5 5ENIOR VICE PRESIDENT NUCLE AR POWE R.

CONSTRUCieON AND PRODUCTION ENGINEE RING f VKE PRE 5MNT N NUCLE AR OPERATIONS QUALITY AND NUCLE AR NUCLEAR PROCUREMENf 5ERVsCE5 SERVICES PLANT OPE RATM)NS I

I I NUCLE AR REGULATORY AND TECHNIC %

5E P ,sCE 5

o FIGURE 6 2-1 '

z SOUTH CAROLINA EL[CTRIC AND GAS COMPANY

? VIRGIL C SUMMER NUCLEAR STATION g OFF SITL ORGANIZATION o

^*, V - - U

.n

l . .

~

ADMINISTRATIVE CONTROLS

f. Reports of violations of codes, regulations, orders, Technical Specifications, or Operating License requirements having nuclear safety significance or reports of abnormal degradation of systems designed to'contain radioactive material,
g. Reports of significant operating abnormalities or deviations from

- normal and expected performance of plant equipment that affect nuclear safety.-

h. Review of all REPORTABLE EVENTS.
i. All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or components.
j. The plant Security Plan and changes thereto.

. k.

The Emergency Plan and changes thereto. -

1. Itus which may constitute a potential nuclear safety hazard as identified during review of facility operations.
m. Investigations or analyses of special subjects as requested by the Chairman of the Nuclear Safety Review Committee.
n. The unexpected offsite release of radioactive material and the report as described in 10 CFR 50.73.
o. Changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL.

P.

AUTHORITY 74, ph,, f- F&e LMG Lym in,J .duinen,s b lo .

6.5.1.7 The Plant 5arety Review Committee shall:

a. Recommend in writing to the Director, Nuclear Plant Operations approval or disapproval of items considered under 6.5.1.6a, c, d, e, j, and k above. I
b. Render determinations in writing to the Director, Nuclear Plant Operations with regard to whether or not each item considered under 6.5.1.6a, c, and d above constitutes an unreviewed safety question. .

I

c. Make recommendations in writing to the Director, Nuclear Plant 1 Operations that actions reviewed under 6.5.1.6(b) above did not constitute an unreviewed safety question.
d. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President, Nuclear Operations and the Nuclear Safety Review Committee of dis-agreement between the PSRC and the Director, Nuclear Plant Operations however, the Director, Nuclear Plant Operations shall have responsi-bility for resolution of such disagreements pursuant to 6.1.1 above.

RECORDS 6.5.1.8 The Plant Safety Review Committee shall maintain written minutes of each PSRC meeting that, at a minimum, document the results of all PSRC activ-ities performed under the responsibility and authority provisions of these technical specifications. Copies shall be provided to the Vice President Nuclear Operations and the Chairman of the Nuclear Safety Review Committee.

SUMER - UNIT 1 6-7 Amendment No. 35

e- o.

ADMINISTRATIVE CONTROLS 6.5.2 NUCLEAR SAFETY REVIEW COMMITTEE (NSRC) ,

l FUNCTION 6.5.2.1 The Nuclear Safety Review Committee shall function to provide independent review and audit of designated activities in the areas of:

a. nuclear power plant operations ,
b. nuclear engineering

...c. chemistry and radiochemistry ,

d. metallurgy i a. instrumantation and control
f. radiological safety l - .

! g. mechanical and electrical engineering

h. quality assurance practices .

I COMPOSITION 6.5.2.2 NSRC shall consist of a Chairman and four or more other members appointed by the Vice President, Nuclear Operations. No more than a 18 minority of the members of the NSRC shall have line responsibility for the

' operation of the unit.

The NSRC members shall hold a Bachelor's degree in an engineering or physical science field or equivalent experience and a minimum of five years of technical experience of which a minimum of three years shall be in one or more of the disciplines of 6.5.2.la through h. In the aggregate, the membership of the committee shall provide specific practical experience in the majority of the disciplines of 6.5.2.la through h.

ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the Vice Ig President, Nuclear Operations; however, no more than two alternates shall participate as voting members in NSRC activities at any one time.

~

CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NSRC Chairman to provide expert advice to the NSRC.

i j SUMMER , UNIT 1 6-8 Amendment No. 18

4

b. Prior to startup after the first refueling outage, SCE&G shall install and make oper-able a fire detection sytem in the areas listed in Table 9-1 of Supplement No. 4 to the Safety Evaluation Report. Pending installation of the fire detectors in these areas the following actions shall be taken:

(i) Prior to initially exceeding 5 per-cent of full power, SCE&G shall, in lieu of Section 3.3.3.7 of the Technical Specifications, establish a fire watch patrol to inspect each area every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in accordance with Section 9.5.1 of Supplement No.

4 to the Safety Evaluation Report.

(ii) For all operating conditions subse-quent to initially exceeding 5 jib 5#,

[ jj percent of full power, SCE&G shall comply with Section 3.3.3.7 of the Technical Specifications.

, _ f i NC

(~ (19) Instru'me'nt and Control Vibration Tests for Emergency Diesel Engine Auxiliary Support Systems (Section 9.5.4, SER)

Prior to startup after the first refueling outage, SCE&G shall either provide test results and results of analyses to the NRC staff for review and approval which validate that the skid-mounted control panels and mounted equip-ment have been developed, tested and qualified for operation under severe vibrational stresses encountered during diesel engine operation, or SCE&G shall floor mount the control panels presently furnished with the diesel generators separate from the skid on a vibration-free floor area.

(20) Solid Radioactive Waste Treatment System (Section 11.2.3, SSER 4)

SCE&G shall not ship " wet" solid wastes from the facility until the NRC staff has reviewed and approved the process control program for the cement solidification system.

(

. _ - . - .. _ . - - . . . - . . . = . _ - .

9 I

Insert A

c. The licensee may make changes to the approved fire protection program without prior approval of the Comission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

Attachment III

. Page 1 of 1 SAFETY EVALUATION This amendment request deletes Technical Specifications 3.3.3.7,3/4.7.9, 3/4.7.10, 6.2.2.e and the corresponding section 3/4 bases, and revises Technical Specification 6.5.1.6 and license condition 2.A.C(18) in accordance with the annotated pages provided in Attachment II. These changes and their respective safety evaluations are discussed hereinafter.

1. Technical Specification 3.3.3.7, Fire Detection Instrumentation, is deleted. The requirements of this specification have been moved in their entirety to plant operating procedures. This change is administrative in nature in that no requirements are being altered.

Provisions for review of future changes to the requirements are dictated by the change to Technical Specification 6.5.1.6.

2. Technical Specification 3/4.7.9, Fire Suppression Systems, is deleted.

All of the requirements of this specification have been moved to plant operating procedures. This change is purely administrative in nature, since no requirements are being altered. Provisions for review of future changes to the requirements are dictated by the change to Technical Specification 6.5.1.6.

3. Technical Specification 3/4.7.10, Fire Rated Assemblies, is deleted.

All of the requirements of this specification have been moved to plant operating procedures. This change is purely administrative in nature, since no requirements are being altered. Provisions for review of future changes to the requirements are dictated by the change to Technical Specification 6.5.1.6.

4. Technical Specification 6.2.2.e, Site Fire Brigade Requirements, is deleted. The requirement of this specification has been moved in its entirety to plant operating procedures. This change is administrative in nature in that no requirements are being altered. Provisions for review of future changes to the requirements are dictated by the changes to Technical Specification 6.5.1.6 as described below.
5. Technical Specification 6.5.1.6, Plant Safety Review Committee (PSRC)

Responsibilities, is being revised to provide specific reference to the requirement to review the plant Fire Protection Program and its revisions. This change reinforces the importance of the Fire Protection Program on plant safety and assures a multi-discipline review by the PSRC of proposed thanges to those requirements that are removed from the Technical Specifications.

6. License condition 2.A.C(18) is revised in accordance with the guidance provided in section F of Generic letter 86-10, Implementation of Fire Protection Requirements. The changes provided in Generic Letter 86-10 establish requirements for control of the Fire Protection Program.

Pursuant to the above information, this amendment request does not adversely affect or endanger the health or safety of the general public and does not involve an unreviewed safety question.

Attachment IV Page 1 of 5

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NO SIGHTTICANT HAZARD DETERMINATION This amendment request consists of deletions of Technical Specifications 3.3.3.7, 3/4.7.9, 3/4.7.10, and 6.2.2.e. and changes to Technical Specification 6.5.1.6 and license condition 2.A.C(18) as discussed in the Safety Evaluation. The following discussions address these changes and their corresponding significant hazard evaluations in the same order as discussed in the Safety Evaluation.

1. Technical Specification 3.3.3.7, Fire Detection Instrumentation, is deleted, and the requirements contained therein have been transferred to plant procedures.
a. This change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

No changes to the requirements have been made. This change simply removes the fire detection instrumentation requirements from the Technical Specifications and places them into plant procedures without altering them. Review of the plant Fire Protection Program and its revisions will be the responsibility of the Plant Safety Review Committee (PSRC), just as it has always been the responsibility of this group to review changes to fire protection requirements when they were part of the Technical Specifications.

b. This change does not create th3 possibility of a new or different kind of accident from any previously evaluated. The proposed change does not alter the requirements; it just moves them from the Technical Specifications into plant procedures. Plant procedures will continue to provide the specific instructions for implementing the LCO, action, and surveillance requirements. There has been no reduction in commitments and, as incorporated into the plant procedures, this change meets the requirements of the existing Technical Specifications.
c. This change does not involve a significant reduction in the margin of safety. No change is being proposed for the requirements themselves. Technical Specification 3/4.3.3.7 is being deleted, and tne requirements contained therein are being incorporated into plant procedures. Plant procedures will continue to provide the specific instructions necessary for the implementation of the requirements, just as they had when the requirements resided in the Technical Specifications. By this process Fire Protection Program commitments, reporting requirements, and amendments will be transferred from the jurisdiction of 10 CFR 50.73 and 10 CFR 50.90
to 10 CFR 50.59 and 10 CFR 50.71(e).

Attachment IV Page 2 of 5 9

2. Technical Specification 3/4.7.9 Fire Suppression Systems, is deleted.

All of the requirements contained therein have been transferred to plant operating procedures.

a. This change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

No changes to the requirements have been made. This change removes the fire suppression system requirements from the Technical Specifications and places them into the plant procedures. Review of the plant Fire Protection Program and its revisions will be the responsibility of the Plant Safety Review Committee (PSRC), just as it has always been the responsibility of this group to review changes to fire protection requirements when they were part of the Technical Specifications,

b. This change does not create the possibility of a new or different kind of accident from any previously evaluated. The proposed change does not alter the requirements; it just moves them from the Technical Specifications into plant procedures. Plant procedures will continue to provide the specific instructions for implementing the LCO, action, and surveillance requirements. There has been no reduction in commitments and, as incorporated into the plant procedures, this change meets the requirements of the existing Technical Specifications.
c. This change does not involve a significant reduction in the margin of safety. No change is being proposed for the requirements themselves. Technical Specification 3/4.3.3.9 is being deleted, and the requirements contained therein are being incorporated into plant procedures. Plant procedures will continue to provide the specific instructions necessary for the implementation of the requirements, just as they had when the requirements resided in the Technical Specifications. By this process Fire Protection Program commitments, reporting requirements, and amendments will be transferred from the jurisdiction of 10 CFR 50.73 and 10 CFR 50.90 to 10 CFR 50.59 and 10 CFR 50.71(e).
3. Technical Specification 3/4.7.10, Fire Rated Assemblies, is deleted, and

. the requirements contained therein have been transferred to the plant procedures,

a. This change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

No changes to the requirements have been made. This change simply removes the fire barrier rated assemblies requirements from the Technical Specifications and places them into plant procedures without altering them. Review of the plant Fire Protection Program and its revisions will be the responsibility of the Plant Safety Review Committee (PSRC), just as it has always been the

o Attachment IV Page 3 of 5 l responsibility of this group to review changes to fire protection requirements when they were part of the Technical Specifications.

b. This change does not create the possibility of a new or different kind of accident from any previously evaluated. The proposed change does not alter the requirements; it just moves them from the Technical Specifications to plant procedures. Plant procedures will continue to provide the specific instructions for implementing the LCO, action, and surveillance requirements. There has been no reduction in commitments which, as incorporated into the plant procedures, meet the requirements of the existing Technical Specifications.
c. This change.does not involve a significant reduction in the margin of safety. No change is being proposed for the requirements themselves. Technical Specification 3/4.7.10 is being deleted, and the requirements contained therein are being incorporated into plant procedures. Plant procedures will continue to provide the specific instructions necessary for the implementation of the requirements, just as they had when the requirements resided in the Technical Specifications. By this process Fire Protection Program commitments, reporting requirements, and amendments will be transferred from the jurisdiction of 10 CFR 50.73 and 10 CFR 50.90 to 10 CFR 50.59 and 10 CFR 50.71(e).
4. Technical Specification 6.2.2.e. Site Fire Brigade Requirements, is i deleted, and the requirements contained therein have been transferred to the plant operating procedures.
a. This change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

No changes to the requirements have been made. This change simply removes the site fire brigade requirements from the Technical Specifications and places them into plant procedures without altering them. Review of the plant Fire Protection Program and its revision will be the responsibility of the Plant Safety Review Committee (PSRC), just as it has always been the re:ponsibility of this group to review changes to fire protection requirements when they were part of the Technical Specifications.

b. This change does not create the possibility of a new or different kind of accident from any previously evaluated. The proposed change does not alter the requirements; it just moves them from the Technical Specifications to plant procedures. Plant procedures will continue to provide the specific instructions for implementing the LCO, action, and surveillance requirements. There has been no reduction in commitments and, as incorporated into the plant procedures, this change meets the requirements of the existing l Technical Specifications.

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Attachment IV l Page 4 of 5 4

c. This change does not involve a significant reduction in the margin of safety. No change is being proposed for the requirements themselves. Technical Specification 6.2.2.e is being deleted, and the requirements contained therein are being incorporated into plant procedures. Plant procedures will continue to provide the specific instructions necassary for the implementation of the requirements, just as they had when the requirements resided in the Technical Specifications. By this process Fire Protection Program commitments, reporting requirements, and amendments will be transferred from the jurisdiction of 10 CFR 50.73 and 10 CFR 50.90 to 10 CFR 50.59 and 10 CFR 50.71(e).
5. Technical Specification 6.5.1.6, Plant Safety Review Committee (PSRC)

Responsibilities, is being revised to provide specific reference to the PSRC's requirement to review the plant Fire Protection Program and its revisions.

a. This change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

The change does not involve a reduction in requirements. The PSRC has always been responsible for reviewing proposed changes to the Technical Specifications and is now responsible for reviewing changes to the plant Fire Protection Program, which has been created from the former Technical Specifications and other 4

requirements.

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b. This change does not create the possibility of a new or different l kind of accident from any previously evaluated. There has been no change in requirements as a result of this Technical Specification

. revision. In fact, the inclusion of specification 6.5.1.6.e is an l addition to the previously identified PSRC responsibilities in that previously the PSRC did not have a specific Technical Specification requirement to review the plant Fire Protection Program.

j c. This change does not involve a significant reduction in the margin

, of safety. The change to PSRC responsibilities as delineated in j section 6.5.1.6 involves an increase in requirements. The former Technical Specifications are a subset of the entire Fire Protection i Program, and the PSRC is now specifically responsible for reviewing the plant Fire Protection program, i

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6. License condition 2.A.C(18) is revised in accordance with the guidance I provided in section F of Generic Letter 86-10, Implementation of Fire '

j Protection Requirements.

) a. This change does not involve a significant increase in the i

probability or consequences of an accident previously evaluated. ,j

' The change in license conditions from those previously incorporated  !

into the license to the one presented in Generic Letter 86-10 does  !

not result in any loss of control of the change process.

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Attachment IV Page 5 of 5 Previously, changes to the Fire Protection Program that decreased the level of fire protection in the plant could only be made with prior Coluission approval utilizing the license amendment process (10 CFR 50.90). The new license condition also requires prior Commission approval but utilizes the 10 CFR 50.59 process.-

b. This change does not create the possibility of a new or different kind of accident from any previously evaluated. The proposed license conditions do not involve any significant change in requirements and are recommended by the NRC.in Generic Letter 86-10.
c. This change does not involve a significant reduction in the margin of safety. The proposed license condition does not involve any significant change in requirements and was recommended by the NRC in Generic Letter 86-10.

By this process Fire Protection Program commitments, reporting requirements, and amendments will be transferred from the.

jurisdiction of 10 CFR 50.73 and 10 CFR 50.90 to 10 CFR 50.59 and 10 CFR 50.71(e).

SUMMARY

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Based on the previous discussions, this amendment request does not involve a significant increase in the probability or consequences of an accident previously evaluated; nor creates the possibility of a new or different kind of accident from any accident previously evaluated; nor involves a reduction in the required margin of safety. Based on the foregoing, the requested amendment does not present a significant hazard. .

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