ML20085D412
| ML20085D412 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 10/07/1991 |
| From: | BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML20085D410 | List: |
| References | |
| NUDOCS 9110160169 | |
| Download: ML20085D412 (45) | |
Text
{{#Wiki_filter:_ _ _ . _ . . . _ . . _ _ . - . - . . _ . _ - . - _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ -- ATTACHMENT B e FIRE PROTECTION REVISED TECHNICAL SPECIFICATION PAGES: 11 (License) 206
?O6A (Table 3.12) 206B 209 212 l
l-l l l 7110160169 v1100/ PDR f4 DOCK 05000293 P POR
SurveillaBLe Eagcj h 3.7 CONTAINHENT SYSTEMS 4.7 152 A. Primary Containment A 152 D. Standby Gas Treatment System and B 158 Control Room High Efficiency Air filtration System C. Secondary Containment C 159 3.8 RADI0 ACTIVE EFFLUENTS 4.8 177 A. Liquid Effluents Concentration A 177 B. Radioactive Liquid Effluent B 177 Instrumentation C. Liquid Radwaste Treatri,ent C 178
- 0. Gaseous Effluents Dose Rate D 179 E. Radioactive Gaseous Effluent E 180 Instrumentation F. Gaseous Effluent Treatment F 181 G. Main Condenser G 182 H. Mechanical Vacuum Pump H 183 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 194 A. Auxiliary Electrical Equipment A 194 B. Operation with Inoperable Equipment 196 3.10 CORE ALTERATIONS 4.10 202 A. Refueling Interlocks A 202 B. Core Monitoring B 202 C. Spent fuel Pool Hater Level C 203 0, Multiple Control Rod Removal D 203 3.11 REACTOR FUEL ASSEMBLY 4.11 205a A. Average Planar Linear Heat A 205a Geneiation Rate (APLHGR)
R. Linear Heat Generation Rate (LHGR) B 205b C. Hinimum Critical Power Ratio (MCPR) C 205c D. Power / Flow Relationship D 205d 3.12 FIRE PROTECTION - ALTERNATE SHUTDOWN 4.12 206 l PANELS I I I I I I I Amendment No. 15, 27, 45, 8A. 89, 113, 114, 133 11 1
l B. Jachnical Scecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. , are htn by incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. C. Records Boston Edison shali keep facility operating records in accordance with the requirements of the Technical Specifications. D. [qu1} iter Valve Restriction - DELETED E. Recirculation Loon Inocerable The reactor shall not be operated with one recirculation loop out of service for more than 24 hours. With the reactor operating, if one recirculation loop is out of service, the plant shall be placed in a hot shutdown condition within 24 hours unless the loop is sooner returned to service. F. Fire ProtectioJ1 l 1 Boston Edison shall implement and maintain in effect all provisions of the I approved fire protection program as described in the Final Safety Analysis l Repcrt for the facility and as approved in the SER dated December 21, 1978 i as supplemented subject to the following provision: I i Boston Edison may make changes to the approved fire protection I prcgram without prior approval of the Commission only if those l changes would not adversely affect the ability to achieve and l maintain safe shutdown in the event of a fire, i G. Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Iniscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR ?.7817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards information protected under 10 CFR 73.21, are entitled: Amendment No.
LLBillM.f0HDfTION FOR OPERATION _ SURVEILLAutE REOUIREMENTS 3.12 Eire Protection 4.12 Fire Protect 10D l Alternate Shutdown Panels Alternate Shutdown Panell .
- 1. Alternate shutdown panels for the The alternate shutdown panels l following systems shall be shall be demonstrated to be l OPERABLE: OPERABLE according to the I following:
- 1. Core Spray l
- 2. RHR 1. The motor operated valves
- 3. RBCCH of the core spray system
- 4. Salt Service Hater shall be operated from the
- 5. HPCI alternate shutdown panels
- 6. RCIC once each cycle.
- 7. Automatic Depressurization '
- 8. Diesel Generators 2. The motor operated valves of the RHR system shall be ADPLICABILITY: operated once each cycle utilizing the MCC B-17 At all times that the system is alternate power source.
required to be OPERABLE.
- 3. The pumps of the SSH
, ACTION: system shall be operated from the alternate Hith any of the alternate shutdown shutdown panels once each ! panels inoperable, cycle. a) Immediately verify that fire 4. The pumps and motor detection with automatic fire operated valves of the suppression for the Cable Spreading RBCCH system shall be Room is Operable. If fire operated from the detection with automatic fire alternate shutdown panels suppression cannot be determined once each cycle, operable, within one (1) hour from i the time the system is determined l S. Alternate shutdown panel to be inoperable, establish a 1 capability for the RCIC continuous Fire Hatch with backup i and HPCI systems shall be fire suppression. I verified to be OPERABLE once each c,etle. b) Immediately verify that the fire i detector zones listed on Table 3.12 1 6. After each refueling are operable for the respective 1 outage and prior to system fire zone (s) for which the i startup, perform a test panel (s) provided alternate i from the alternate shutdown capability, shutdown panel to verify that the relief valve If a fire detection zone cannot be I solenoids of the Automatic determined operable, establish an Depressurization System hourly fire watch patrol to inspect (ADS) actuate. the affected zone (s).
- 7. Once each refueling outage, the diesel generator control circuits shall be isolated from the Cable Spreading Room and the diesel generator started.
206
- ~ _ _ _
I Table 3.12 fire Detector i Zones Associated with i Alternate Shutdown Panels 1 I I , 1 Alternate Shutdown Sysigm Fire Zg.ne DetE11pn Panel /Det,_lgnn l I I Core Spray 1.1 L.2 C-224/4A I I RHR 1.1 &.2 C223/3C i i RBCCH 1.21 &.22 C-222/2A & 20 I l SSW 5.1 & .2 & .3 N/A l l HPCI 1.3 & .4 C-223/3D & 3E l , RCIC 1.5 C-223/3A & 3B l t ADS 1.1 & .2 C-224/4A l I DGS 4.1 & .3 C-93/1 & 2 I i 1 L 5 l l l i i Amendment No. 206A 1 i I' l-l
MSES: 3/4.12 fi.e Protection l l The alternate shutdown system, independent of cabling and equipment in the Cable Spreading Room, is provided to effect safe shutdown of Pilgrim in the event of a fire in the Cable Spreading Room. This is accomplished by installing isolation switches for safety-related equipment that will provide the capability for the plant operators to reach a safe shutdown condition. These switches will isolate their associated equipment from the CSR cables, thus transfer control from the Control Room to the local emergency shutdown stations outside the CSR. These isolation switches are located in alternate shutdown panels and are located as close as practical to the equipment or switchgear they serve. l An emergency shutdown procedure, which is compatible with the design modifications and plant operator availability, provides step-by-step actions to initiate safe shutdown operation. Operator actions to isolate safety-related cables passing through the CSR is initiated as soon as a fire which is not immediately extinguishable is detected and confirmed in-the CSR. Alternate shutdown panels are provided for the following systems:
- a. Core Spray
- b. RHR
- c. RBCCH
- d. Salt Service Water
- e. HPCI
- f. RCIC
- g. Automatic Depressurization System i
- h. Olesel Generators Inoperability of the above listed systems does r.ot require entry into LCO l action statements for the alternate shutdown panels.
A surveillance frequency of once per cycle is considered prudent and more frequent testing not warranted. The frequency of once per refueling outage for testing the diesei generators prevents unnecessarily rendering them ) j inoperable during normal power operation. The frequency of once per refueling outage for the Automatic Depressurization System is consistent with the existing surveillance frequency for this system. Requiring this surveillance to be performed during a refueling outage will also assure that plant conditions will allow for safe access to the ADS solenoids. l (The next page is 206K) l Amendment No. 114 2068 l
- .m .- _ ._ _ _ _ . _ .._ _.__ ___ ._
6.0 AQWJ115TRATIVE CMIRQL5
- 2. When the unit is in an operational mode other than cold shutdown or refueling, a person holding a Senior Reactor Operator License shall be present in the control room at all times. In addition to this Senior Operator, a Licensed Operator or Senior Operator shall be present at the controls when fuel is in the vessel.
- 3. At least two Licensed Operators shall be present in the control room during reactor startup, scheduled reactor shutdown and during recovery from reactor trips.
- 4. An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.
- 5. ALL CORE ALTERATIONS performed while fuel is in the reactor vessel af ter the initial fuel loading shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to fuel Handling who has no other concurrent responsibilities during this operation.
6 Deleted l
- 7. The Chief Operating Engineer, Nuclear Hatch Engineers, and Nuclear Operations Supervisors shall hold a Senior Reactor Operator License. The Nuclear Plant Operators shall hold a Reactor Operator License.
6.3 WIL11Aff 00AllflCATIONS The qualifications with regard to educational and experience backgrounds of the unit staff at the time of appointment to the active position j shall meet the requirements as described in the American National Standards Institute N18.1-1971, " Selection and Training of Personnel for l Nuclear Power Plants." In addition, the individual performing the l function of Radiation Protection Manager shall meet or exceed the qualifications of Regulatory Guide 1.8, September,1975.
- 6.4 TRAINING A retraining and replacement training program for the Unit staff shall be maintained under the direction of the Nuclear Training Department Manager. The training programs for the licensed personnel shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10CFR Part 55. l l
Amendment No. 41, 46, 69, E8, 122, 125, 122 209
6.5.A.6 RESPONSIBILIUES (CQatinndl
- e. Review of facility operations to detect potential safety hazards.
- f. Review of the Station Security Plan and implementing procedures and changes to the plan and procedures.
- g. Review of the Emergency Plan and implementing procedures and changes to the plan and procedures.
- h. Performance of special reviews and investigations and reports thereon as requested by '.he Nuclear Safety Review and Audit Committee (NSRAC) Chairman.
- i. Investigation of all violations of the Technical Specifications and shall prepare and forward a report covering evaluation and recommendations to prevent recurrence to the Station Director, the NSRAC Chairman, and the Senior Vice President - Nuclear.
- j. Review of the Station fire Protection Program and I implementing procedures and changes to the Program and I implementing procedures. !
The ORC Chairman may appoint subcommittees composed of personnel who are not members of ORC to perform staff work necessary to the efficient functioning of ORC.
- 7. AUTHORITY
- a. Recommend in writing to the Station Director the approval or disapproval of items considered under 6.5.A.6(a) through (d) above.
- b. Render determinations is writing with regard to whether or not each item considered under 6.5.A.6(a) through (d) above constitutes an unreviewed afety question.
- t. Provide written notification n 24 hours to the Station Director, the Nuclear S fety Review and Audit Committee, and the Senior Vice President - Nuclear of disagreement between the ORC Members and the ORC Chairman. The Station Director shall have responsibility for resolution of such disagreements.
- 8. RECORDS The ORC shall maintain written minutes of each meeting and copies shali be forwarded to the Station Director and the NSRAC Chairman.
Amendment No. 29, 46, 69, 28, 122, 125, J32 212
ATTACHMENT C FIRE PROTECH ON MARKED-UP TECHNICAL SPECIFICATI@ - EAGES 9 l k 6-
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Surleil.lMCf PM1tJL 3.7 CONTAINHEf41 SYSTEM 5 4.7 152 A. Primary Containment A 152 ~
- b. Stanaty Gas Treatment Systtm and B 158 Control Room High Efficiency Air Filtration System C. Secondary Containrrent C 159 3.8 RAD 10ACilVE EFFLUENTS 4.B 177 A. Liquid Effluents Concentration A 177 B. Radioactive liquid Ef fluent B 177 Instrumentation C. Liquid Radwaste Treatment C 178 D. Gaseous Effluents Dose Rate I) 179 E. Radioactive Gaseous Effluent E 160 InstruNntation F. Gaseous Efflutnt 1reatment f 181 G. Main Condenser G 182 H. Mechanical Vacuum Pump H 183 3.9 AUXILLARY ELECTRICAL SYSTEM 4.9 194 A. Auxiliary Electrical Equipment A 194 B. Operation with Inoperable Equipment 196 l 3.10 CORE ALTERATIONS 4.10 202 A. Refueling Interloc6.s A 202 B. Core Monitoring B 202 C. Spent fuel Pool Water Level C 203 D. Multiple Control Rod Removal 0 203 3.11 REAC10R FUEL ASSEMBLY 4.11 205a A. Average Planar Linear Heat A 205a Generation Rate (APLHGR) j B. Linear Heat Generation Rate (LHGR) B 205b C. Minimum Critical Power Ratio (MCPR) C 20Sb d t D. Power / flow Relationship D 205d 3.12 FIRE PROTECT 10N -ALTfgAW7E Mum ' 3 61Ako 4.12 206
~ ~-- y <-- s 206 y
A. Fire Detection Instrumentation h A B. Fire Water Supply Syster B
; 206a 3{
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C. Spray and/or Sprintler Systems C 206c s D. Halon System 0 f' 206d ) , E. Fire Hose Stations E 206e 4 . F. Fire Barrier System F 206e-1 ' C. f.ltctnste Shut'd;vn Panelt G A
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e : A s. Techiga.LSpeci f i c a tiond yd Technical Specifications contained in Appendix A, ar revised - throu;h Amendment No. @t 6re hereby incorporated in the license. ] F TN licensee shali operate the facility in accordance with the je '# 3 cinical Specifications. 63 Pfmrds zu a . D.~~ #.
. Bo, n' , sh;11 keep faci'ity operating records ici accordance ith ti , requirements of the Technical Specifications.
Idi . -
,,e
( [.qualizer Valve Rp triction - DELETED -
. RecirculatlQ n Loot IngMnblf N .
The reactor sh111 not be operated with one recirculation loop out of service for more than 24 hours. Hith the reactor operating, if one -- recirculation loop is out of sertice; the plant shall be M aced in a hot shutdown condition within 24 hours unless the loop is soonet
'4 nturned to service. 4{:
V
, SEE /N.SEM J Fire Protection g F.
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m The li see may preteed with and is required to complete the [ sodifications identified in Paragraphs 3.1.1 through 3.1.19 of the y (i NRC's Fire Protection Safety Evaluation (SE), dated December 21, 1978 m for the facility. The Safety Evalustion is supplemented ':y Amendment f ratings. These modifications No. 123 dated October 13, 1988, as it relates to fire barrier p (' will be ccepleted in acc?rdante witn the schedule in Table 3.1. - In addition, the licensee shall submit the additioi.a1 information identif9d in Tatla 3.2 of this SE in accordance with tne schedule _ m_ contained therein. In the event these dates for subniittal cannot be H
) met, the licerste shall submit a report, explaining the nr
/ circumstances, together with i revised schedule. --
The licensee is required to implement the administrative controls identiflad in Section 6 o' the SF. Th? sdministrative controls shall be in effect by December 31, 1978. ~ y" m - w _ _ _ . . . . - . -
- ^-
G. Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard , training and qualificdon, and safeguards contingency plans including amendments .e pursuant to provisions of the Miscellaneous Amen Nc ts and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 ano 27822) and to the authority of 10 CFR 50.90 and 10 CFR
- 50. 5.,( p ) . The p'ans, vnicn contain Sateguaros Information protectac under 10 CFR 73.2i, are entitlea: _
~~3 evision 151 Jp '
AmenTm'e'nWo. n fi 36 s
I
' LIB 111ECONDI.U ONJ!LOCER&U0tL_ __ SUREI LLMCE REQUIREMENIS
. A12 LIRE _EBOIECIION 4h flRLE80lICIl0N A. [ ire _Dettt110fLlDitLumcatalL00 A. f_ _QelfL110fLluttlum0Einth0 l The minimum # ire detection '
, As minimum, the number or instrumentation for n re fire Atectors noted in Table etection zone shown in Table 3.12-1 TNthe column entitled 12-1 shall be OPERABLE, ' Minimum IMtruments Operable in Zone " shliy be AF. LLC 6BILIlY: demonstrated 0fRABt.: ". n accordance with thN At 'll times when equipment in applicat'le NFPA 72A b 7?D that fire dctection 7one is Codes by a funrtional(t t at requi ed to be OPERABLE. least once per 6 months, aCIION Hith th number of n...iimum
\
l GPERABLE fire detection instrumen s less than required by Table 3.1 1;
- a. Wit \inIhour,establisha fire watch patrol to insp ct the zone with the inope able instrement(s) at 'ia't onc? per hour; and
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- f.
- b. Restore the inoperable so n e nu6Nd [J/9d instrume t(s) to OPERA"'E status w thin 14 days to
-assure th minimum operable d tectors for
.56zna a3.4/(& 4 7
each detet ion zone, or A Cfcdt%c b/er>+d l prepare and submit a ' report to th Ccmmission [j.; / ._, [y/ g ,y,.y 5 , 1,.rw within the nt t 30 days u l outlining the action j t akei1, the cau e of the
- malfunction an the plans L for restoring t e l instrument (s) to OPERABLE status.
- c. For inoperable fir >
detectors controlli' g fire , suppression systems, see the respective fire l l suppression system ' ; E section, i .e. , Sectior( l 3.i2C for water \ suppression systems or 'g 3.12D for gaseous \ suppression systems.
}
Revision 117 Amendment No. 29, 25, 114 206 l _ .- . - -_ . . . - - - ~
M MITING' CONDITION FOR OPERATION SU3y1 B LANCE REQUIRLHENTS b Fire _ Hate.r_Eupply System \.FireHaterSupolySvitem The Fire Water Supply System 1. The Fire Hater Supply System shall be c)erable with: shall-be tested and verified to be OPERABLE:
. Two (2) 2000 gpm/125 psig fire pumps which are arranged a. by checking the volume of to start automatically. water in each fire water tank at least once every 7
- 2. o (2) ' iter supplies with a days.
m nimum storage quantity of 24 ,000 gallons of water in b. y automatically starting e a d) . e ch fire pump at least once ev ry month and running each
- 3. Two ) independent water pum for thirty minutes at i flow aths from Item Nos. 1 & that time.
2 abov to each fire water suppres ion system. (3.12.C c. by vis ally checking every and 3.1 .E) shutof valve on the fire water su ply system at least
&EPLICABILIlY once eve month for proper position.
At all times when ny safety related equipment is requi ed to be OPERABLE. d. by cycling e ch fire water supply syste shutoff valvc ACILQN1 through its f I operation at least once r cycle,
- a. Hith less than th' above required equipment restore the e. by verifying at ast once inoperable equipmen to OPERABLE per "ycle that ea pump status within 7 days or prepare starts and deliver at least and submit a report the 2000 gpm Mile main ining a Commission within the next 30 system pre,,sure of a least days outlining the pia s and 125 psig.
procedures to be used t provide for the lo:s of redunda y in f. by performing a water \ flow __ this system. telt on the fire water y rd loop at least nnte every
- b. With no FIRE SUPPRESSION TER year.
SYSTEN OPERABLE:
- g. by verifying at least once
- 1. Establish the backup Fire every mcnth that the diesel Hater Supply System within 24 fire pornp fuel storace tank hrs. contains a minimum of 175 gallons of fuel oil.
- 2. If the requirement of b.1 above cannut be met, an h. at least once per operating orderly shutdown of 'e cycle by subjecting the reactor shall be initiated diesel to an inspection in and the reactor shall be in accordance with procedurer the cold shutdown condition prepared in conjunction with within 24 hrs. the manufacturer's recommendations for the class of service.
Revision 117 Amendment No. 29, 25, 114 206a
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- SURVEILLNi;LRCOUMEMENIL i
LIHLI1NG_CONDll10N10LONM110N d\ firLNatcLS9pp]LSntes (cont'd) i, by verifying at least once per 3 months that a sample of diesel fuel from the fuel storage tank, obtained in accordance with ASTM 04057-81 r 04177-82, is within the
/7M1 d, gue,udh [SVhC ceptable limits specified in T le 1 of ASTM 0975-81 with S(('M /O. 9. M 2. ('f('[y'/3 cn , nd se en .
Au[00le./Gr/./wwev j. by de, nstrating that the diesel etarting 24-volt battery () bank an charger are OPERABLE d'c 7wwe e'dr <fe <gw .<&rvw as go}to :
- 1. at lea t once per week by veri fyi that the electrol.te level of each battery i above the plates and batter voltage is at least 24 vo ts.
- 2. at least once 3er 3 months by verifying t at the specific gravit is appropriate for onlinued service of the ha tery.
- 3. at least once per c erating cycle by verifying t at the batteries, all plates and battery racks show no .
visual indication of physical damage or abnor al deterioration and the battery-to-battery and terminal connections are cican, tight, free of corrosion, and coated with anti-corrosion material.
-- Revision 117 '
Amendment No. 29, 96, 114 206b
= .- __.
UMU1NG CON.DHIDLf0R OPERAT1ON SURVLIMMCLEQUIR[HJJilS
. Satay_and/or Sgttohlet Sy11em Spr_ayY_Andlor_Sprinkl er Sittm3 The spray and/or sprinkler \The spray and/or ink'er systems located in the following ystems shall be uomon trated to areas shall be OPERABLE except as b OPERABLE according to the noted below: fo lowing:
. Diesel Generator Room 1. ach sprinkler system and Preaction sprinkler systems w ter spray system alarm (including detectors), sh 11 be tested at least once eve year by opening the
- 2. 1 Diesel Fire Pump fuel Oil alar bypass or inspector torage Room wet pipe test alve. Alarms in high s rinkler system. rao ar are to be tested once pe cycle.
- 3. Au iliary Boiler Room wet pip sprinkler system. 2. Each wet pe sprinkler system sha be proven to be
- 4. Reci culation Pump HG Set unobstrutte by opening the Room et pipe sprinkler inspector te connection at syste least once pe cycle.
- 5. Hydroge Seal Oil Supply Unit 3. Each preaction s rinkler preactio sprinkler system. system shall be t ip tested (includi detectors) at least once per cle.
- 6. Turbine Ba ement Addition wet 4. Each water spray :;ys em shai, pipe sprinsler system. be trip tested automa ically by simulated actuation f the
- 7. Reactc,r. Buil ing Elev. heat detectors at least nce 23'-0", North Side wet pipe per cycle, sprinkler sys m.
- 5. At least once per 3 years,
- 8. Reactor Buildin Elev. flow test through each open 51'-0", North a South Side head spray / sprinkler header wet pipe sprinkl r systems. shall be performed and each.
open head spray / sprinkler
- 9. Reactor Auxiliary uilding, nozzle-shall be verified to Water Treatment Ar 1, wet be unobstructed, pipe sprinkler syst m.
- 10. Health Physics Access Area wet pipe sprinkler sy tem. ']g g h M/M APILl_CABILITY:
At all times when equipment kt%< ) m . 8. 4 3 (' & / / 3 /h the spray / sprinkler protecte area is required to be OPERABL . W 6[c2C'N o 5tt'W
- m ) Spt -r a < ><,a
- s. Revision 117 Amendment No. 29, 25, 114 206c
l.IMLUEG_ CON 0ll30RSl0!LOELRAUON . SURVIILt#KLBIOVIMERIL. _
~
Spray _.andLor_SpthhhtSystem (cnnt'd) ACHONI t . from and after the date that a spray and/or sprinkler. syst0.; is made or found to be
- INOPERABl.E. within one hour e.tablish a continuous fire w tch with backup-su pression, except as e spe i fied . in 3.12.C.b. aM t.Ji b te , m om u d e [e 3.1 C.c.
- b. If th suppression system of M/7d M c d / O 'd #/
3.12.C.1, or 3.12.C.4 is INOPERA LE, establish an hourly f re watch patrol with [g43) ., g(2 g6, &M c[ backup su pression provided ' ,f 9)w <[r '1"**1 [';g j g g .g , that the d tection system in that fire a ea and the detection'an suppression sys'em for tt i redundant fire area is OPERA E.
- c. If two or more etectors of 3.12.C,1 are fou d or made to be INOPERABLE, wi hin one
- hour charge that s rinkler system piping with ater.
I- d. Restore-the system to uPERABLE status within 14 days or prepate and su it a rsvn ; to the Commissio i j- / t;iin '5e next 30 days ! outlining the action take , the cause of inoper3Dility and the plans for restoring the system to OPERABd statu . l L Revision 117 Amendment No. 29, 25, 114 206c-1
UB111EG10NQU10NS FOR OK88TUAN $1JRVEILLANCEEQQlRBMIS C. Sany_an_dlor_Sorinkler syitets (cont'd) EQ1LQh When the entire fire a ea protected by a spray and/or s rinkler system is designated, '
"H GH RADIATION AREA / AIRBORNE RA '0 ACTIVITY AREA", an hourly fire wat patrol may be established g/ W W * " # [' d , F 5 / D L.--
(e.g , for ALARA considerations in lieu f a contis.uous fire watch). [ M'o.g *7 g'3,g,3 (gg@3) If a znne of the fire area is so f design ted, one of the following shall a ply: (1) If the zone is ( ggfj,[ w c L I w .,[; adequat 'iy inspectable from a C - Zy,_ >, non-High Radiation Area, the Yg'[ continuou fire watch shall be located i the non-High Radiation Area, or ( ) If (1) cannot be accomplishe , a fire watch patrol shall enter the High Radiation Area once every e ght (8) hours. j D. Halon Syltem D.' Halon Syltes l The Halon Syste for the Cable he Halun System shall be Spreading Room all be OPERABLE monstrated OPERABLE: with each of the five (5) storage tanks charged to t least 95% of 1. t least once per month by the minimum quant y of Halon (217 rifying the Halon storage Ibs. per tank) nec ssary to ta k pressure and that the extinguish a fire nd-minus or con rol panel is in the plus 10% of the pres urt stamped on auto atic mode. the Data Plate on th tank corresponding to an a bient 2. At lea . Once per 6 months temperature of 70*F. etectors by veri ing the quantity associated with the au matic of Halon n the storage initiation of the Halon System tank (s).
- shall be operable, excep that an individual detector may 3. a. At least nce per inoperable if the other d.tector in refueling utage L the same bay is operable a d both verifying i at the detectors in ALL adjacent ys are system and a sociated operable. devices actua upon receipt of a s ulated l APfLLCABILIIY1 actuation signa and l 'At all times when the safety r. . Performance of an l related equipment in the Cable inspection to assur Spreading Room is required to beg the nozzles are operable. unobstructed.
3l4. rz D "Undw 2L ! " ~~'E N f# ""^- Revision 117 M. 0 . 4. (d^l//S) O v d$At5 Y A W "Ucd Amendment No. 29, 35, 84, 114 e +-
~
206d 4pr e wLuc wa
LIElllM_COE01110N_ LOR.APlRG0F SURVIILL#!CLRE.0VIPlMLNJS 4
. ACI M : -
ithin one (1) hour from and after e time that the system is found to e
U'" "([~,[5/4/1L Mwq be inoperable, establish a continuous g,g,y,g(j:'gg/j3 p c(cG,6 &c[
fit watch with backbp fire .
-suppr sion equipment. M kcnc$cA- .Npvi'* I m.d E. Lire _Em Stathm . Elt t.H u t itAtio n The interio fire hose stations shown Each interior fire hose station -
in Table 3.1 2 > hall be OPERABLE. hall be verified to be OPERABLE: APPLLCARLLLIX: 1. At least once per month by visual inspection of the station At all times when i e equipment in to assure that the hose and the area protected b the fire hose ozzle are properly installed. station is required to be operable.
- 2. At least once per cycle by 6LIL0ti: re ving the hose for ins ction, replacing any Hith a hose station inoperab , degr ded coupling gaskets, and provide'an additional equival t rerac ing.
capacity hose for the unprotect area at/from an OPERABLE hose sta ion 3. at leas once per three.(3) within I hour, years b
- a. parti ly opening each hose h 4,12 E fdt j[,.g g
- statio valve erify valve o erabilit and no obstruct on.
th nmmu"c( ta nd2 Sectic
- 4. by annually to ducting a
/#<$ Y. 6((f t//J) h/ hydrostatic tes of each hose
- a. at a pressur. 50 psig
. (dAC c[ <mo #cd e d/ greater than e ;naximum available pres ure at that hose station. o SAcug<iA<o
- 0. at the applicable service test pressure as sted in Table 8-3 of the " andard for Care, Maintenan of Fire Hose Including Connection and Nozzle ."
NFPA No. 1962-1979, or
- c. by replacing each nontes ed hose with a new or used se l which has been hydrostatically tested in accordance with the pressures specified in l 4.12.E.4.a or 4.12.E.4.b.
Amendment No. 29, 25, 76, 114 206e 1 .
l l e L1tiLURLC0HD1 HOR _f_0R_0EER& HOR SMEILLANCE_REQUIREMENIS ~ _ _ l$
. ~. ULLBArdfr_Syst.em Y firstB3rrietPSDrintlana l u
q All fire barrier systems providing Surveillance requirements for 1 cparation of redundant safe shutdown enetrations in tire barriers l 5 stems shall be functional. escribed in specification ! 3.i2.f are as follows: AEP . CABlulYl ,
- 1. Tite _DArrier PfDrirclion )
At all times when the safe shutdown S Ali i systems re required to be operable. ' Ea fire barrier ACJ10M pene ratio 7 seal shall be veri ed to be functional With one or te of the required fire by a y sual inspection at [ barrier syste nonfunctional, within least o ce per operating l one hour either establish a continuous cycle an subsequent to i fire watch on on s$de of the affected any insta lation, ! barrier or verify. he OPERABILITY of modification or an automatic fire tection or maintenance frecting the suppression system o at least one seal. , . side of the nonfuncti al fire barrier and establish an houri fire watch 2. Ure_Doori patrol. Each fire door sh 11 be EXCIEll0M When the Fire. eas on tested once per c le for
- D02 sides of the affected re operability of clos re and barrier are designated "HIGH 'ADIATION latching mechanisms nd AREAS / AIRBORNE RADI0 ACTIVITY A EA", an for integrity. ,
hcurly fire watch patrol may be i established (e.g. for ALARA 3. Eire Dameers i considerations) in lieu of a N l continuous fire watch. - Eechfiredampershallbe\ 3h #2. F "Fvk t3< a v Sph A wcf tested once per cycle for
% u 7~5, perability and integrity. yg S. '3G,. t[,AlleInale ps 44LciG /0 5. //.46 he/c0la [4. n3 i-
- l. '
Shutdown _P3nels -) 'A1 ternate Shu1AoED Pane 1s/,\( \ t 2 PdL
/
- l. Alternate shutdown panels for the Q .
Thc alternato shutdown panels i y( following systems shall be shall be demonstrated to be /\ OPERABLE: { OPERABLE according to the / following:
- 1. Core Spray b) i .. 2. RHR 1. The motor operated valves p/
V 3. RBCCH of the core spray system ,
- 4. Salt Service Water shall be operated from the n L
-{7 '
- 5. HN.I alternate shutdown panels j
)
j ..
-l 6. RCIC once each cycle. L
~/ 7. Automatic Depressurization i S
- 8. Diesel Generators / 2. The motor operated valves I L ,
of the RilR system shall be 3.11 F#ilt TMdigrich yNg"tN NC B-
< wm_.,
alternate power source. ((/ 7 Rev)[ ion 17 , 7m ,m i Amptdment No. 25, 66 76 114 - l 2&lo l
' ',? UlM OSM UO11C D E CL __ _ S FlEILLOC.i lECU 3EMEFi. . _ _ _
, . u .. ._ . . .wj.,
, - _ _ . - . . . . y-~..-- %-. , , . 3 y r.t. 2., e. .~ .-; ? - --. 5 M Mrt' %'7;Q*'^ Z,-:1.'.C ~ i~s
- . m.3 2
'..__ J J C C C _.2 : c. C. : v ; i Q _ , i F I'
';)
i Aff_LM M ILill; 3. The pumps of the SSH systtr. Shall be operated from the , At all times that the system is alternate shutdown panels once i required to be OPERABLE. each cycle. / KlK@l 4. The pumps and motor operated valves of the RBCCH system With any of the alternate shutdown ihcIl be operated from the panels inoperable, alterr. ate shutdown panels once each cycle. )
< e) Immediately verify that fire q detection with automatic fire 5. Alternate shutdown panel ;
suppression for the Cable :apability for the RCIC and Spreading Room is Operatie. HPCI systems shall be verified i If fire detection with to be OPERABLE once each cycle, automatic fire suppression cannot be determined operable. 6. After each refueling outage i
~ take'approprlate~actFon as' and prior to startup, perform described in Section 3.12.0 of a test from the alternate (
the Tech. Spec. shutdown panel to verify that .
" the relief valv6 sole oids of b) Immediatgly_ verify that fire the Automatic Depressu,ization tectortf are operatie, per System (Ans) actuate.
Tfch. Spec'. Section 3.12.A for th'e respective system ire 7. Once each refueling outa ',
) zone (s) for which the panel (s) the diesel generator control
,/ provided alternate shutdown circuits shall be isolated i capability. from the Cable _ Spreading Room
\ l a, and the diesel generator l
l Ifkire detection /c$ e started. l determined operable, establish-( an houriyLfire watch patrol to inspect the affected zone (s).
~
y % .< ) A s G e k w T M $ . I ? a s R . o f Tf'E 7ZX 7~ Oi= 77DS RWE A)ou) APPEARS OA) A%tJ PAGE.-
!O(o.
w% o,a 6) Gw y cLe & ik & k W k ck G k. Q A ,. a M M L <~ 4 - l 1 - %
-kkwani a 2 4 p ,.
Revision 117 l Amendment No. 76, 114 k 206e-2
, _ ~ -
l. L ~ __ _ _
3 E L. E T E. D f 2 0 pi i 3 ', MO VEb TO FSAL 7?fk2 /0 8-/ TABLE 3.12-1
,/
ELRE_DEJEXTICH INSTRWE.NTS
. / "
\ Total No. 'Minimu?
\ Local Panel No./ Detectors ,- Instruments Bui7 ding / Operabje_In Jene E!en11pn Z.on e_No. In Zon_e_
Fire Area 1 t' actor Building 01'3" C225/5 C-2 2. ilothes Change Area i C222/2A 1 6 i Reacter 3nilding "0" ' RBCCW "A" / 5'0" C222/8 / 13 7 Reactor Building RECCW "B" ,[ Reactor Building 51'0" C96/A/B ,/ 8 4 Recirc. Pump
/
M.G. Set Poon 11 6 Turbine Building 37' ,C9I/3 Switchgear Room "A"
/
/,e 7 4 Turbine Bailding 23' ,/ C221/1B 13 7 Switchgear Room "B" j C94/2 2
Turbine Building 37',/ C94/7 3 { Battery RNm "A" s 1 3 2 t 23' C94/8 Turbine Briiding Battery Rcem "B"
'/
p 6 3 Off Gas Retention / 23' C113/1 l dailding /
- No non than' two (2) adjacent detectors shall be cut of service.
/
./
Revis ,n 117 i 206f Ao . rent No. 2!, 25, 114 l _.
D ?k()}Q [ /L{Ql/$ / 0 fbb - TABLE 3.12-1 /
\
LIllE_DETEC_ TION INSTRUMENTS (Cont'd) Total No. Minican' Bull .g Local Panel N9./ Detectors Instruments Fire _frq_ Elgy311on Z.qnf_Nq. _Ic Zone _ Op_erable_In_Zo_ne Control Poom Cabi.e.ts 37' C 94/6 1 1
\ N C221/3 C221/4 3/ '
2 2 ' i C221/5 3 2 C221/6 3 2 C221/7 3 2 C221/8 3 2 C221/2 [ 5 3 Vital M.G Set Room 23' C221/1A 5 3 Reactor Euilding (-)17'6" C22 *A 3 2 RHR - Core Spray "A" Reactor Building (-)17'6" C22.14C 3 2 RHR - Core Spray "B" \ Reactor Building (-)17'6" C223/30 2 1 C223/3E HPCI 2 1 Reactor Building . -)17'6" C223/3A 2 1 RCIC C223/3B 2 1 Reactor Eailding C224/4E 6 CR0 - East C224/4F 7 4 7 C224/4C 9 5 [ C224/40 C224/4G C224/4H 5 2 9 5 3 i No ..o/r? than two (2) adjacent detectors shall be cut of service. Rev'> ion 117
/ endeer.t No. 114 2cr-1
I Y Y$l 0 b lO* , Of TABLE 3.12-1 FIRE. DETELLION INSTRlLMENTS (Cont'd) Total No. nimum' Local Panel No./ Detectors nstruments Build q L1.fyAtJpn Zone No. In ZonL Optrable_Ig_ Zone Fire _Arfa C223/3F 9 5 Reactor Building 23' C223/3] 10 5 CR0 - Hest 10 5 C223/3G C223/3H 1 6 2 1 C223/3I 18 g Reactor Building C225/5A1 C225/5A2 6 3 2 1 C225/5A3 C225/5A4 4 2 N 8 4 Reactor Building 74'3" C225/5-Fuel Pool Heat Exchanger Area 18 g l Reactor Building 74'3" C225/5% C225/583 2 1 , North Side l C225/5C3 6 3 Reactor Building 91'3" l Standby Liquid Control System ' Tank. Area C225/5C1 c 13 Reactor Building 91'3"
- No more than two f adjacent detectors shall be out of service.
Rev' ;or. 117 2t f-2 A nduent 10. 114 t
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vC 4 4 D rurasreert ssecrsaseac0eR ooot yourouenl eoet el eoRl Hl C e I(v 1 1 G NSNSSNFANOHIEDNWSHERLCERER ! N ? I D . L 7 o I 1 N U 1 B 77 t 1 1 1 1 44 1 1 1 3 3 3 3 3 3 3 n R 1 1 99 77 55 5 2 2 2 2 0 0 0 e O id p - - - - - - - - - - - - - - - - T C A a u1 3525 1 4 1 0 93 00 0 1 1 4 7 0 2 0 5 1 5 1 1 7 1 0 i s v e/ E i cBB BP BB 2 B S S B C S S er R S B R "C RR RR RR R R R R R R R R RA - /
' ~ JDELETEb FRop j3 r, p f a y?s h / c p s p? Q 7y s a io.s - 2. , TABLE 3.12-2 1 ' ELRE HOSE STATIjh5 (Cont d) I TURBINE BUILDING RADRASTE &_CCHTROL AREA .([prttinu- d St3m! RC-59-37 Stairway Outs)<fe Control Room Elev. 37' / TB-35-06 Hect End Ele A 6' RC-66-37 Radiatic/ChemicalLab l TB-29-06 E3st Hall Elev.X Elev. ' TB-31-51 South Hall Elev. 51' TB-34-51 Hest Hall Elev.51' TURBINE AUX. BAY TA-86-51 Outside Standby Gas Room / QFF-GAS RrTENTION BUI_LDULG OR-91-23 Retention Buildin9, Elev. 23' GR-93-05 Retention Building Elev. 5' [ DIESEL GENERATQR$ [ DG 46-23 Diesel Generator Room A DG.47-23 Diesel Generator Room INTAKE STRgCTURE 15-95-23 Near Fire P" .s Revisi 117 i Amen' ..-ent io. 2 9, 25, 1 :4 206,
MSLS:
' 314J2A_flRLDEJEQ1Q!LJhSIRUMMIMlON . PERABILITY of the fire detection instrumentation ensures that adequate rning capability is available for the prompt detection of ' ires. This ca .bility is required in order to detect and locate fires ir, the'r early sta, s. Prompt detection of the fires will reduce the potential for damage to safet related equipment and is an integral element in the overall facility fire p tection program.
In the ev t that a portion of the fire detection instrumentation is inoperable, ir. reasing the frequency of fire watch patrols in th? affect d areas is req red to provide detection capability until the inoperable instrumentatio is returned to operability. 31&d2fk L _0. E ELSMPl[S.SION SYSTQiS The OPERABILITY of t e fire suppression systems ensures that ad uate fire suppression capabilit is available to confine and extinguish res occurring in any portion of the cility where safety related equipmen is located. The fire suppression system nsists of the water system, spray nd/or sprinklers, the Halon System and fire ose stations. The collective pability of the fire suppression system is , equate to minimize potentia damage to safety related equipment and is a ma or element in the facilit fire protection program. The surveillance requirements pro de assurances tF t the minimum OPERABILITY requirements of the fire suppressio systems are et. The allowance is based on the minimum quantity of Halon nec sary to ex inguish a fire. The minimum quantity is 217 lbs. per tank, and the system quires a minimum of 5 tanks at all times. This is in accordance with - e Na ional Fire Codes. Operability is assured by verifying the quantity of I and pressure in the tank (s). The backup Fire Water Supply System is e ab ished by connecting the Pilgrim water distributica system to the city s stem rough a booster pump truck (stationed onsite). The truck connec to the lymouth city water system at a predesignated location in close prox (nity to the lant; dedicated hoses and auxiliary equipment for this purpos are staged on ite. The backup Fire Water Supply Sys em does not provide M07. backup to the entire primary fire water system but r ther provides a tempora - means of supplying water until at least one trai of the fire suppression v ter system is declared operable. In the event that portion of the fire suppression system are inoperable, l alternate backup fire f hting equipment is required to be mad available in the affected areas unt the atfected equipment can be restored o service. l l 1)ELESYD FSDM TS [ Revisi 117 Amendgent No. 29, H , 114 206i
7.;_.-_-__-_________.
, BASES:
314 J 20..L. D._ Ell RL SUPfR ESS10N_ SYSIDiS . _Cor t inu ed I
- bntheeventthatportionsofthefiresuppressionwate*systembecome i i perable, alternate backup fire fighting equipment is required to be made ava lable in the af fected areas until the affected equipment can be restorea to s cc.
In the event that the fire suppression water system b( .mes inoperable, immediate orrective measures must be taken since this cstem provides th. major fire uppression capability of the plaat.
/
D E. LETED Ff2omt T3 P.ev ., ion 117 Am/ndment No. 114 2061-.1
BASES ... ]
-94.12r FIRE BABRIER SY37EM The functional ~ integrity of the fire barrier system ensures-that fires J ill be confined or adequately retarded-from spreading to adjacent Mrtions oigthe facility. A functional fire barrier system, is considered to be the-4 bar'xter itself with all penetration seals, doors and dampers intact or oper}}le. This design feature minimizes the possibility of a single fire rapidl involving several areas of the facility prior to detection and extingu beent. . The fire barrier systems are a passive element in the facility ire protection program and are subj?ct to_ periodic inspections Safe s tdown systems are those systems which must operste af ter/a loss of offsi e power and are required to achieve and maintain safe 4hutdo-n
-(hot and cold -butdown) conditions.
During perio of__ time when the barriers are not function , either.
- 1) a continuous fir watch is required to be maintained in th.
vicinity of the affe ed barrier, or 2) the automatic fire tection or supp'ession system on t least one side of the affected ba rier rnust be
-verified CPCEABLE and a hourly fire watch patrol-establ hed until the barrier is restoreo to f ctional status. A fire watch strol is a concesa;ory meesure to survey area (s) n whiCh the active and/or ssive fire dete:ti n,
?v;Dression or barrier syst (s) are in a-degraded m de and is utilized for cetection and reporting of fi es. .
Tne surveillance reQuiremengt are consider to'be ade sate since they ere deter-ined using accer'td- industry r ference mattrial as a basis a;; lying good engineering judgeme and stit n operating considerations. I 4
\
DE LE.7ED Fl20 M TS
/
AmedmentNo.[, 3 206j
3' MSIS: 3L42 W S $ t $ Petel D
- VI G N W D The alternate shutdown system. independent of cabling and equipment in the i Cable Spreading Room is provid3d to effect safe shutdown of Pilgrim in the I event of a fire in the Cable Spreading Room. This is accomplished by installing isolation switches fo." safety-related equipment that will provide the capability for the plant operators to reach a safe shutdown condition.
These switches will isolate their associated equipment from the CSR cables, thus transfer control from the Control Room to the local emergency shutdown stations outside the CSR. lhese isolation switches tre located in alternate Outdown panels and ate located as close as practical to the equipment or switchgear they serve. The operability of the fire suppression and detection system in the Cable Spreading Room in conjunction with the passive element of cable coating ensures that adequate fire protection / detection / suppression capability is {
/
available to quickly detect, confine and extinguish fires occurring in any I portion of the room where safety-related equipment is located. The fire detection / suppression system consists of an independent smoke detection system, an automatic Halon 1301 Fire Suppression system and fire hose stations available outside.the doorways to the Cable Spreading Room. The collective capability of passive protection and detection with either manual or automatic suppression is adequate tc, minimize potential damage to safety-related equipment and is a major element in the facility fire protection program. An erargency shutdown procedure, which is compatible with the design modifications and plant operator availability, provides step-by-step actions to initiate safe shutdown opeiation. Operator actions to isolate safety-related cables passing through the CSR is initiated as soon as a fire which is not immediately extinguishable is detected and confirmed in the CSR. l Alternate shutdowr. panels are provided for the following systeas:
- a. Core Spray
- b. RHR
! c. RBCCH
- d. Salt Service Water
- e. HPCI
- f. RCIC 4 i g. Automatic Depressurization System J
- h. Olesel Generators l
Inoperability of the above listed systems does not require entry into LCO action statements for the alternate shutdown panels. A surveillance frequency of once per cycle is considered prudent and more [ frequent testing not warranted. The f.equency of once per refueling outage for testing the diesel generators prevents unnecessarily rendering them < inoperable during normal power operation. The frequency of once per refueling l outage for the Automatic Depressurization System is consistent with the ( existing surveillance frequency for this system. Requiring this surveillance to be performed during a refueling outage will also assure that plant conditions will allow for safe access to the ADS solenoids. ( 7NL AL)<7^~ P/4 G-[_. 15 Z. 0(o l< Revision 117 Amendment No. 114 20f;j -1
/
# f a cc;B
.-. .~. . - - - .- , .-
6.0 MMfil5TPATlyL101TEQLS
. 2. When the unit is in an operational mode other than cold shutdown or refueling, a person holding a Senior Reactor Operator License shall be present in the control room at all times. In addition to this Senior Operator, a Licensed Operator or Senior Operator shall be present at the controls when fuel is in the vessel.
- 3. At leist two Licensed Operators shall be present in the control room during reactor startup, scheduled reactor shutdown and during recovery from reictor trips.
- 4. An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.
- 5. ALL CORE ALTERAll0NS performed while fuel is in the reactor vessel af ter the initial fuel loading shall be directly s supervised by either a licei..ad Senior Reactor Operator or Senior Reactor Operato'. Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
NNC/> TO Pv1A ,-,~-m- ~w 5EcTeod /O tr v. 7 6. A fire Brigade of 5 members including a Fire Brigade Leader (Rg g,g 4 NWD shall be maintained o') site at all times. This excludes 3 members of the minimum shift crew necessary for safe shutdown and any personnel required f0r other essential functions during U ee~'
- 7. The Chief Operating Engineer, Nuclear Hatch Engineers, and huclear Operations Supervisors shall hold a Senior Peactor (g Operator License. The Nuclear Plant Operators shall hold a Reactor Operator License. n 6.3 UNIT STAFF QUALIFICATIQN3 The qualifications with regard to educational and experience backgrounds of the unit staff at the time of appointment to the active position shal'. l meet t 'uirements as described in the American National Standards Institucs 3.1-1971, " Selection and Training of Personnel for Nuclear
-Power Plan. .
" In addition, the individual performing the function of Radiation Protection Manager shall meet cr exceed the qualifications of Regulatory Guide 1.8, September,1975.
6.4 TRAINING A retiaining and replacement training program for the unit staf f shall be maintained under the direction of the Nuclear Training Department Manager. The training programs for the licensed personnel shall meet or exceed the req 1ments_ and recommendations of Section 5.5 of ANSI N18.1-1971 and peridix A 10CFR Part 55. The training programs for the Fire Brigade l meet exceed the requirements of NFPA Standaro No. 27-1975 " Private Fire Brigade" Fire Protection Training sessions will be held quarterly. Ann u m c,. n.n.an.m.m@
6.5.A.6 RESPONSIBILITIES (Continued)
._~
- e. Review of facility operatic.ns to cetect potential safety hazards.
- f. Review of the Station Security Plan and implementing procedures and changes to the plan and procedures.
- g. Review of the Emergency Plan and i *1ementing procedures and changes to the plan and procedures,
- h. Performance of special reviews and investigations and reports thereon as requested 5/ the Nuclear Safety Review and Audit Committee (NSRAC) Ct. airman.
- 1. Investigation of all violations of the Technical Sper.lfications and shall prepare and forward a report
(.overing evaluation and recommendations to prevent recurrence to the Station Director, the NSRAC Chairman, and the Senior Vice President - Nuclear.
, EugrnM
- j. Review the Station Fire Protec ic hF ft and implementing procedures and changes to the _
ndt procedures, g 7n9rre The ORC Chairman may appoint subcommittees composed of personnel who are not members of ORC to perform staff work necessary to the efficient functioning of ORC. __ 7. AUTHORITY
- a. Recommend in writing to the Station Director the approval or disapproval of items considered under 6.5.A 6(a) through (d) above.
- b. Render determinations in writing with regard to whether or not each item considered under 6.5.A.6(a) through ('d) above constitutes an unreviewed safety question.
- c. Provide written notification within 24 hours to the Station l Oirector, the Nuclear Safety Review and Audit Committee, and the Senior Vice President - Nuclear of disagreemeat between the ORC Members and the ORC Chairman. The Station Director shall have responsibility for resolution of such disagreements.
- 8. RECORQS
~
The ORC shall maintain written minutes of each meeting aad copies shall be forwarded to the Station Director and the NSRAC Chairman. Amendme6t16! 29, 46, 69, 88,122 h'f)/ 212 xo k
ATTACHMENT D List of Affected Paggi Dalghlxi s tina Revised Rt9httment 11 11. License License 206 206 206 a 206 A 206 b 206 B 206 c --- 206 c-1 --- 206 d- --- 206 e --- 206 e-1 Text moved 206 e-2 to page 206 206 f --- 206 f-l --- 206 f-2 --- 206 g --- 206 h --- 206 i --- 206 1-1 ---
-206 j --
206 j-1 Text moved to 2068 209 209 212 212 9
+- _
4 J La - 4J.m = . 4, ( .a__.ui 6 J .s 4o4. .a.- a. , , a: 4 -- 3 mw,.._ . I' l 1
~
ATTACHMENT E-.
.5 4
4
)
I r l l =~ e r l' . 3 l.. l'. I ' I f-l l
PNPS-FSAR Fire exits in the Turbine Auxiliary' Building (i.e., access area and time tunnel) are separated by smoke control doors. Noncombustible shields are installed between the feedwater pumps (i.e.,-Turbine 8uilding) to prevent oil from one pump from spraying on the other(s). The diesel generator day tank room (s) are designed to prevent diesel fuel oil from entering the diesel generator room (s). 10.8.4 Inspection, Testing and Limiting Conditions for Operation for Fire Protection Equipment Thelfollowing provides surveillance frequencies, acceptance criteria and Limiting Conditions for Operation for equipment associated with fire prevention. This section reflects the guidance provided in Generic Letters 86-10 and 88-12. 10.8.4.1 Fire Detection Instrumentation 10.8.4.1.1 Fire Detection Instrumentation Limiting Conditions for Operation The ' minimum fire detection instrumentation for each fire detection zone shown in- Table 10.8-1 shall be operable at all times when equipment in that fire detection zone is required to be operable. Action: With 'the number of minimum operable fire detection instruments less than required by Table 10.8-1:
- a. Within 1 hour, establish a fire watch patrol to i nspect the zone ,
with the inoperable instrument (s) at least once per Sour; and
- b. Restore the inoperable instrument (s) to operable status within 14 days to assure the minimum operable- detectors for each detection zone, or prepare and submit a report to the Commission within the next 30 days outlining the action taken, the~ cause of the malfunction and the plans for restoring the instrument (s) to operable status.
- c. For inope,able fire detectors controlling fire suppression systems, see the respective fire suppression system section, i.e.,
Section 10.8.4.3 for water suppression systems or 10.8.4.4 for gaseous suppression systems. 10.8.4.1.2 Fire-Detection Instrumentation Surveillance Requirements As a . minimum. the number of fire detectors noted in Table 10.8-1 in the column entitled " Minimum Instruments Operable in Zone " shall be demonstrated operable in accordance with the applicable NFPA 72A or 72D Codes by a functional test at least once per 6 months. 10.8-5 Revision 13 - June 1991
PNPS-FSAR 10.8.4 2 rire Water Supply System 10.8.4.2.1 Fire Hater Supply System Limiting Conditions for Operation
-At all times when any safety related equipment is required to be operable the Fire Water Supply System shall be operable with:
- 1. Two 2000 gpm / 125 psig fire pumps which are arranged to start automaticaily.
- 2. .Two water supplies with a. minimum storage quantity of 240,000 gallons of water in each.
- 3. Two independent water' flow paths from 1 and 2 above to each fire water suppression system. (10.8.4.3 and 10.8.4.5)
Action: With less than the above required equipment, restore the inoperable equipment to operable status within 7 days or prepare and submit a report to the Commission within the next 30 days outlining the plans and procedures to be used to provide for the loss of redundancy in this system. With no Fire Suppression Hater System Operable:
- 1. Establish the backup Fire Water Supply System within 24 hours.
- 2. If the requirement of No. I above cannot be met, an orderly
-shutdown of the reactor shall be initiated and the reactor shall be in the cold shutdown condition within 24 hours.
10.8.4.2.2 Fire Water Supply System Surveillance Requirements
- 1. The Fire Hater Supply System shall be tested and verified to be operable:
- a. by checking the volume of water in- each fire water tank at least once every 7 days.
- b. by automati illy starting each fire pump at least once every month and running each pump for thirty minutes at that time.
- c. by visually checking every shutoff valve on the fire water supply system at least once every month for proper position.
- d. by cycling each fire water supply system shutoff valve
-through its full operation at least once per cyc_le.
- e. by verifying at least once per cycle that each pump starts and delivers at least 2000 gpm while maintaining a system pressure of at least 125 psig.
- f. by performing a water- flow test on the fira water yard . loop at least once every year.
10.8-6 Revision 13 - June 1991
PNPS-ISAR
- g. by verifying at least once every month that the diesel fire pump fuel storage tank contains a minimum of 175 gallons of fuel oil,
- h. at least once per operating cycle by subjecting the die >el to an inspection in accordance with procedures prepared in conjunction with the manufacturer's recommendations for the class of service.
- i. by veri fying at ieast once per 3 months that a sample of diesel fuel from the fuel storage tank, obtained in accordante with ASTH 04057-81 or D4177-82, is within the acceptable limits specified in Table 1 of ASTM 0975-81 with respect to viscosity, water content, and sediment.
- j. by demonstrating that the diesel starting 24-volt battery bank and charger are operable as follcws:
- 1. at least once per week by verifying that the electrolyte level ot each battery is above the plates and battery voltage is at least 24 volts.
- 2. at least once per 3 mont5s by verifying that the specific gravity is appropriate for continued service of the battery.
- 3. at least once per operating cycle by verifying that the bitteries, all plates, and battery racks show no visual indication of physical damage or abnormal deterioration and the battery-to-battery and t ermt r.al connections are clean, tight, free of corrosion, and coated with anti-corrosion material, i0.8.4.3 Spray and/or Sprin(ler Systems 10, B . 4. 3.1 Spray and/or Sprinkler Systems Limiting Conditions for Operation The spray and/or sprinkler systems located in the following areas shall be operable at all times when equipment in the spray / sprinkler ,
protected area is required to be operable:
- 1. Diesel Generator Room Preaction sprinkler systems (including detectors).
- 2. Diesel fire Pump Fuel Oil Storage Room wet pipe sprinkler system.
- 3. Auxiliary Coller Room wet pipe sprinkler system.
4 Recirculation Pump HG Set Room wet pipe sprir.kler system.
- 5. Hydrogen Seal Oil Supply Unit preaction sprintler system (including detectors).
10.8 7 Revision 13 - June 1991
i PNPS-fSAR fn Turbine Basement' Addition wet pipe sprinkler system.
- 7. Reactor Building Elevation 23'-0", Nor+h Side wet pipe sprinkler system.
- 8. Reactor Building Elevation 51'-0", North and South Side wet pipe sprinkler systems.
- 9. Reactor Auxiliary Building, Water Treatment Area, wet pipe sprinkler system.
- 10. Health Physics Access Area wet pipe sprinkler system.
EXCEPTION: When the entire fire area protected by a spray and/or sprinkler system is designated, "HIGH RADIATION AREA / AIRBORNE RADIOACTIVITY AREA", an - hourly fire watch patrol may be established (e.g., for ALARA con.ciderations in lieu of a continuous fire watch). If a zone of the fire area is so designated, one of the following shall apply: (i) If the zone is adequately inspectable from a non-High Radiation Area, the continuous fire watch shall be located in the non-High Radiation Area, or (2) If (1) cannot'be accomplished, a fire watch patrol shall enter the High Radiation Area once every eight hours. ACTION:
- a. from and af ter the date that a spray and/or sprinkler system is made or found to be inoperable, within one hour establish a continuous fire watch with backup suppression, except as specified in 10.8.4.3.1.b and 10.8.4.3.1.c.
- b. If the suppression system of Diesel Generator Room Preact: Jn sprinkler systems (including detectors), or Recirculation Pump HG Set Room wet pipe -sprinkler system is inoperable, establish an hourly fire watch patrol with backup suppression provided that the detection system in that fire area and the detection and suppression system for the redundant fire area is operable,
- c. If- two or more detectors of the Diesel Generator Room Preaction Sprinkler System are found -or made to be inoperable, within one hour charge that sprinkler system piping with water.
l
- d. Restore the system to operable status within 14 days or prepare and submit a report to the Commission within the next 30 days l outlining the action taken, the cause of inoperability and the plans for restoring the system to operable status.
. 10.8.4.3.2 Spray and/or Sprinkler Systems Surveillance Requirements The spray and/or sprinkler systems shall be demonstrated to be L operable according to the following:
- 1. Each sprinkler system and water spray system alarm shall be tested at least once every year by opening the alarm bypass or inspector 10.8-8 Revision 13 - June 1991 l -. __ _ _ , . _ _ . __ ,_ _ .-
PNPS-FSAR test valve. Alarms in high radiation areas are to be tested once per cycle.
- 2. Each wet pipe sprinkler system shall be proven to be enobstructed by opening the inspector test connection at least once per cycle.
- 3. Each preaction sprinkler system shall be trip tested at least once per cycle.
- 4. Each water spray system shall be trip tested automatically by simulated actuation of the heat detectors at least once per cycle.
- 5. At least once per 3 years, a flo' test through each open head spray / sprinkler header shall be performed and each open head spray / sprinkler nozzle shall be ',e';'ied to be unobstructed.
10.8.4.4 Halon System 10.8.4.4.1 Halon System Limiting Conditions for Operation The Halon System for the Cable Spreading Room shall be operable with each of the five storage tanks charged to at least 95% of the minitt'am quantity of Halon (217 lbs. per tank) necessary to extinguish a fire, and minus or plus 10% of the pressure stamped on the Data Plate on the tank corresponding to an ambient temperature of 70*F. Detectors associated with the automatic initiation of the Halon System shall be operable, except that an individual detector may be inoperable if the other detector in the same bay is operable and both detectors in all adjacent bays are operable. The Halon system shall be operable at all times when the safety related equipment in the Cable Spreading Room is required to be operable. ACTION: Hithin one hour from and af ter the time that the system is found to be inoperable, establish a continuous fire watch with backup suppression equipment. 10.8.4.4.2 Halon System Surveillance Requirements The Halon System shall be demonstrated operable:
- 1. At least once per month by verifying the Halon storage tank pressure and that the control panel is in the automatic mode.
- 2. At least once per 6 months by verifying the quantity of Halon in the storage tank (s).
- 3. a. At least once per refueling outage by verifying that the system and associated devices actuate upon receipt of a simulated actuition signal, and
- b. Performance of an inspection to assure the nozzles are unobstructed.
10.8-9 Revision 13 - June 1991
c^ PNPS-FSAR 10.8.4.5 Fire Hose Stations - 10.8.4.5,1 Fire Hose Stations Limiting Conditions for Operation The interior fire hose stationt shown in Table 10.8-2 shall be operable at all: times when the equipment in the area protected by the fire hose station is required to be operable. ACTION: _ Hith a hose station inoperable, provide an additional
-equivalent capacityf hose for the unprotected area at/from an operable hose statien within I hour.
10.8.4.5.2 Fire Hose Stations Surveillance Requirements Each interior fire hose station shall be verified to be operable
- l. At least once per month by visual- inspection of the station to assure that the hose and nozzle are properly installed. -i
- 2. At least once per cycle by removing the hose for inspection, replacing any degraded coupling gaskets, and reracking.
- 3. At least once per three years by partially opening each hose station valve to verify valve operability and no obstruction.
- 4. By annually conducting a hydrostatic test of each hose
- a. at a pressure 50 - psig greater than the maximum available pressure at that hose station, or
- b. at the applicable service test pressure as listed in Table 8-3 of the " Standard for Lara. tuintenance of Fire Hose Including Connection and Nozzles." NFPA No. 1962-1979, or
- c. by replacing each nontested hose with a new or used hose which has been hydrostatically tested in accordance with the .
pressures specified in a or b above. 10.8.4.6 Fire Barrier System 10.8.4.6.1 Fire Barrier System Limiting Conditions for Operation All fire _ barrier systems providing separation of redundant safe shutdown systems shall be functional at all times when the safe shutdown systems are required to be operable. ACTION: Hith one or more of the required fire barrier systems nonfunctional, within one hour either establish- a continuous fire watch on one side of the affected barrier or_ verify the OPERABILITY of an automatic fire detection or suppression system on at least one side of the nonfunctional fire barrier and establish an hourly fire watch - patrol. 10.8-10 Revision 13 - June 1991
PNPS-FSAR
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IXCEPTION: When the Fire Areas on both sides - of the af fected fire barrier are designated "HIGH RADIATION AREAS / AIRBORNE RADI0 ACTIVITY AREA", an hourly fire watch patrol may be established (e.g. for ALARA considerations) in lieu of a continuous fire watch. 10.8.4.6.2- Fire Barrier System Surveillance Requirements Surveillance requirements for penetrations in fire barriers are as follows:
- 1. Fire Barrier Penetration Seals: Each fire barrier penetration seal shall be verified to be functional by a visual inspection at least once per operating cycle and subsequent to any installation, modification or maintenance affecting the seal.
- 2. Fire Doors: Each fire door shall be tested once per cycle for operability of closure and latching mechanisms and for integrity.
- 3. Fire Dampers: Each fire damper shall be tested once per cycle for operability and integrity.
10.8.4.7 Fire Brigade A Fire Brigade of 5 members including a Fire Brigade Leader shall be maintained on site at all times. This minimum excludes 3 members of the minimum shif t. crew necessary for safe shutdown and any personnel required for other essential functions during a fire emergency. The Fire Brigade training shall be in accordance with Boston Edison's Fire Protection Training Program. The Fire Protection training of Fire Brigade members shall be held quarterly. 10.8.5 References
- 1. Pilgrim Station 600, Unit 1, Boston Edison Company, Fire Protection System Evaluation, March 1, 1977
- 2. Safety Evaluation Report by the Office of Nuclear Reactor Regulation (Amendment 35 to License No. OPR-35) for Pilgrim Nuclear Power Station-1, December 21, 1978
- 3. Safety Evaluation Report (additional fire Protection Information Review) for Pilgrim Nuclear Power Station-1, October 7,1980.
- 4. Safety Evaluation- Report by the Office of Nuclear Reactor Regulation Related to Amendment No. 123 to Facility Operating License No. DPR-35, dated October 13, 1988.
l l l 10.8-11 Revision 13 - June 1991 I
, PNPS-FSAR j- TABLE 10.8-1
[ FIRE DETECTION INSTRUMENTS Total No. Minimum' Building Local Panel No./ Detectors Instruments Fire Area Elevation Zone No. In Zone Operable In Zone Reactor Building 91'3" -C225/5 C-2 2 1 Clothes Change Area Reacter Building 3'0" C222/2A - 11 ~6-RBCCH "A" Reactor Building 3'0" C222/8 13 7-R8CCH "B" Reactor Building 51'0" C96/A/B 8 4 Recirc. Pump H.G. Set Room Turbine Building 37' C94/3 11 6 Switchgear Rocm "A" , Turbine Building 23' C221/iB 7 -4 Switchgear Room "B" C94/2 13 7 Turbine Building 37' C94/7 3 2 i Battery Room "A" Turbine Building 23' C94/8 3 2 j Battery Room "B" Off Gas Retention 23' C113/1 6 .3 Building No more than two (2) adjacent. detectors shall be out of service. i of 3 Revision 13 - June 1991
PNPS-FSAR I TABLE 10.8-1 (Cont) T FIRE DETECTION INSTRUMENTS Total No. Minimum'
'm as Ponel No./ Detectors Instruments Building Operable In Zone (1_gva t f or' Zone ti,. _I n_Jyn3_.
Fire Area 1 Control Room Cabinets 37' C 94/6 1 3 2 C221/3 3 2 C221/4 3 2 C221/5 3 2 C221/6 4 3 2 C221/7 3 2 C221/8 5 3 C221/2 5 3 Vital H.G. Set Room 23' C221/1A 3 2 Reactor Building (-)l7" C224/4A RHR - Core Spray "A" 3 2 Reactor Building (-)l7*6" C223/3C RHR - Core Spray "B" 2 1 Reactor Building (-)l7'6" C223/3D C223/3E 2 1 HPCI C223/3A 2 1 Reactor Building (-)17'5" 2 1 C223/3B RCIC C224/4E 12 6 Reactor Building 7 4 CRD - East C224/4F C224/4C 9 5 9 5 C224/4D C224/4G 5 3 C224/4H 2 i
' No more th3n two (2) adjacent detectors shall be out of service.
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PNPS-FSAR g TABLE 10.8-1 (Cont) FIRE DETECTION IN HRUMENTS Total No. Minimum' local Panel No./ Detectors Instruments Building ZAne No. I n . Zgrit Coerable_In Zone Fire Area El t vali_o_n 1 23' C223/3F 9 5-Reactor Building 5 C223/3J 10 CRD - West 10 5 C223/3G C223/3H 11 6 C223/3I 2 i C225/SA1 18 9 Reactor Building 51' 6 3 C225/5A2 2 1 C225/5A3 4 2 C225/5A4 8 4 Reactor Building 74'3" C225/SB2 Fuel Pool Heat Exchanger Area 18 9 Reactor Building 74'3" C225/581 2 1 North Side C225/583 C225/5C3 6 3 Reactor Building 91'3" Standby Liquid
'notrol System Tank Area 25 13 Reactor Building 91'3" C225/5C1
- No more than two (2) adjacent detectors shall be out of service.
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r PNPS-fSAR TABLE 10.8-2 FIRE HOSE STATIONS REACTOR BUILDING SECONDARY CQNTAINMENT ACC(SS LOCK Sta. # Sta..f SL-81-23 Reactor Bldg. Truck Lock RB-13-117 North Hall .Elev. 117' Elev. 23' RB-06-117 . South Hall, Elev. 117' RB-12-91 North Hall, Elev. 91' Standby Liquid Control, REACTOR AUX. BAY RB-05-91 System Area, Elev. 91' Auxiliary Plant Heating Boiler Roam North Hall, Elev. 74' RA-41-23 RB-11-74 Elev. 23' RB-04-74 . Fuel Pool Heat Exchanger RA 42-06 RBCCH Loop B Area Area, Elev. 74' North Hall, Elev. 51' Elev. 3' RB-09-51 Condensate Demin./ Resin Corridor Outside MG Set Room - RA-44-06 RB-03-51 Area Elev. 3' Hest Hall, Elev. 51' RB-10-51 Inside North MG Set Alriock RADHASTE & CONTROL AREA Elev. 51' l RB-14-23 Decontamination Room Radwaste Stairway to Turbine l North Hall, Elev. 23' RC-57-01 Hest Hall, RHR Loop B B1dg. Elev. -1' RB-07-23 Outside Radwaste Control Stairway, Elev. 23' RC-69-01 ;' Hest Hall, RCIC Stairway Room Elev. -1' RB-02-23 Hater Box Scavenging Pump Elev. 23' RC-56-23 l Area, Elev. 23' RB-16-23 Reactor Bldg. Access Stairway Outside Vital HG Set Lock Elev. 23' RC-58-23 Room Elev.'23' 1 RB-15-03 CR0 Quadrant Corridor Switchgear Room B Elev. 2'9" RC-12-23 RHR Quad Loop A Elev. 23' ; RB-17-03 East Hall Near B-8 Load Center Elev. 2'9" TB-39-51 Elev. 51' RB-01-03 'RCIC Quad Elev. 2'9" 1 of 2 Revision 13 - June 1991
, y
,g -,
PNPS-FSAR ,
.c ..-
TABLE 10.8-2-(Cont) ; .i l f1RE HOSLS16TIONS 1 f TURBINE BUILDING RADHASTE & CONTROL AREA (Continggdl. Sla. # RC-59-37 Stairway Outside Control Roor: . i Elev. 37' TB-35-06 West End Elev.-6' RC-66-37 Radiatto,1 Chemical Lab TB-29-06 East Hail Elev. 6' Elev. 37' TB-31-51 South Hall Elev. 51' . . TB-34-51 Hest Hall Elev 51' TURBINE AUX. BAY TA-86-51 Outside Standby Gas Room .! OFF-GAS RETENTION BUILDING OR-91-23 Retention Building, Elev. 23' OR .'3-05 Retention Building, Elev. 5' DIESEL GENERATORS DG-46-23 Diesel Generator Room A DG-47-23 Diesel Generator Room B INTAKE _SJTRUSTI)R[ , i
- 15-96-23 Near Fire Pumps ,
i Revision'13 - June 1991 2 of 2 i
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