ML20148N020
ML20148N020 | |
Person / Time | |
---|---|
Site: | LaSalle |
Issue date: | 06/19/1997 |
From: | COMMONWEALTH EDISON CO. |
To: | |
Shared Package | |
ML20148N019 | List: |
References | |
NUDOCS 9706250417 | |
Download: ML20148N020 (14) | |
Text
3
. ~ - . . . ~
ATTACHMENT A Marked Up UFSAR' Changes ~ ;
1 l
1 1
l i
9706250417 970619 PDR ADOCK 05000373 P PDR ,
. . . _ _ - _ _ _ _ . _ . . _ _ _ _ _ _ _ _ _ ~ -- _ _ _ - - _ _ _ _
- . 309036
- D kN h Ths control room cnd cocociated effica crcss cro con::tructed of noncombuntible
' materials, including those having a flame spread rating of 25 or less. There
.-,e is no provision for automatic fire suppression-in<these areas.
,M ,
- 'M- Ample protected exits are provided in the stairwells as well as protection provided by the fire rated walls and doors. No travel-distance greater than
- . 100 feet is needed to get into a fire-safe area. Walls in the reactor ,
J
! building, auxiliary building, and radwaste building are of reinforced concrete which exceed the 3-hour fire ratings.
As required by_the NFPA, loss of power to the fire protection system is prevented by using the unit's 125-Vdc power supply for a power source. l The fire protection system, including external storage, is not. designed to I Seismic category I. The fire protection system is designed so that failure of l ,
the system or parts of the system does not result in failure of Seismic category I syntems.
A single failure in the fire protection system does not prevent the nyntem I from performing its design function. Two fire pumps are provided with one being sufficient for any plausible demand. If one pump fails to start, the other pump starts and provides water to the fire protection system. The plant is encircled by a 14 inch ring header which feeds the fire protection system inside the station. If pipe rupture occurs, the affected portion of piping can be isolated and water can still be supplied. The fire protection system forms several loops in the plant, permitting portions of the system to be valved-out, thereby assuring continued water supply for the balance of the ste lon.
Automatic fire protection systems are electrically supervised, thereby
- producing system failure annunciation both in the AEER and in the control l room. If a system fails to automatically actuate, it may be engaged manually !
or adjacent equipment (e.g., fire hoses, CO2 hose reels, or hand held 9 extinguishers) may be utilized. , j l'
9.5.1.4 Inspection and Testino Recuirements Initial construction and preoperational testing of the fire protection nyntem were conducted in accordance with the preoperational test program defined in chapter 14 of the ImAR.
Periodic inspections and operational checks to demonstrate integrity are routinely performed on all fire pro tion syst===- These tests and inspections are identified in the echnical specification .
- A:. A A /,4..u/ 8,p.
~
9.5-18 REV. 3 - APRII. 198~1
~.
uf kts LSCS-UTSAR i . 9.5.1.5.2 Construction Phase: Renconsibilities for Fire Protection l The CECO supervisor of safety has a fire protection coordinator assigned to him with responsibilities for:
- a. Adequacy of fire fighting equipment including its operation.
- b. Conduct of fire inspections as required by CECO standards, underwriting bureau policies, and insurance company requirements.
c.
Conduct of tests on new fire protection and fire fighting equipment; conducting and witnessing acceptance tests on fire equipment after the initial preoperational test is completed.
- d. Maintainf.ng CECO contacts with local fire departments and fire prevention organizations.
- e. Issuing company policy and procedures for fire prevention and protection supervising and coordinating the internal fire reporting forms and reports; advising departments on fire prevention rules and standards.
- f. Supervising and assisting in the training of personnel in fire protection, including the use of fire-fighting equipment.
During construction, a fire inspection was perf rmed at LSCS once per month by the CECO fire protection coordinator. Independently, the site was inspected I bimonthly by the Nuclear Mutual Limited Consultants. On-call fire inspections were conducted at the request of the station project superintendent or the q LSCS station operations superintendent.
During the construction phase, the station project superintendent had onsite responsibility for fire loss prevention.
9.5.1.5.3 Ooeratino Phaser Oroanization and Responsibilities g y e- v v The station superintendent has overall onsite responsibility for fire loss prevention. The station fire protection progran calls for the following LSCS fire loss prevention organization:
A 7L ., r.A mea:wa L & Shah, , ,,4 Ay 4 h L ip.f , h,e p beko, cef.f0 h(,,,;cd g [
"',~J 4-6 , ~ AL.4D ;, cu,,
kch~,,,:4. ka S ucLu .
9.5-20 REV. 9 - APRIL 1993
67006D LSCS-UFSAR
, a. The fire marshal is the staff assi's6dtI/"who has the following duties:
I 1. Insure fire brigade, general employee and contractor l fire / housekeeping training. i 4 {
- 2. Ascertt 2n proper installation and maintenance -of fire equipment.
- 3. Purchase fire equipment as suggested by fire inspectors and approved by station superintendent. /
4 Investigate each fire and make reconnendations when necessary. 5
, 5. Monitor surveillance and testing program for fire loss l prevention.
- 6. Submit inspection reports.
l 7. Submit fire reports.
i
- 8. Make arrangements with local fire departments for possible i future service requests.
- 9. Prepare routines for fire drills.
4 f
b.
Assistant Fire Marshal - Staff Assistant with the following duties:
- 1. Review Fire Protection surveillance from various departments and
, ( implement corrective action when necessary.
- 2. Attend and assist Fire Brigade Training. '
' 4 Conduct and critique Fire Drills.
- i.
Review and revise Fire Protection Procedures.
l
- 5. Su'bmit Fire Reports and records.
- 6. Participate and respond to QV, NHL, NRC and Cor:porata. l 4
- 7. Perform fire hazard inspections. l
- 8. Respond to fires and alarms to give technical advice.
I j
- 9. Review Fire Protection Out-of-service Log.
- 10. Assume the position of Fire Marshal in his absence.
d l
l l
I I
l 9.5-21 REV. 9 - APRIL 1993
o?stD h7W ,
i LSCS-UFSAR
- Y M -
' k, The shift engineer has the followiny"5dEfes: l t
l 1. Assist fire marshal in preparation of Report of Fire.
W
$ 2.
Make reports to fire marshal on fire protection outages, fires '
and inspections. '
d.
A shift foreman is the fire chief for the Brigade (all shifts), which include the following:
i 1. a shift foreman (fire chief),
l
- 2. at least four operators (Rad-Chem personnel respond with the l fire brigade for first aid and radiation protection purposes).
4 j
Composition of the fire brigade is addressed in station administrative procedure LAP-900-14.
r~
1 ~ . .
J a
i l
\l 9.5-21a REV. 9 - APRIL 1993
l I
l 2
s 1 1
l ATTACHMENT B I
1 1
Marked Up License and Technical Specification l
l l
l l
1 1
c:
l i
l l
l I
4
{
l . .
l . ,
04/17/82-Licer.co t:s. NFF-11 i . -+..
i I
~
(b) A prelube pop, powered from a reliable direct current j power supply, be installed in the system to operate in
- parallel with the engine-driven labe oil pump, or an j alternative acceptable to the NBC shall be installed to preclude dry-starting of the diesel-engine.
} (c) Controls and monitoring instrumentation be removed from
! the engine and engine skid, except instruments qualified
! for this location. The non-qualified. control and
- monitoring instr oents shall be installed on a free l
standing floor mounted panel and located on a vibration free floor area. If the floor is not vibration free, the l
panel shall be equipped with vibration mounts.
l (22) nirect current power Evat== (Emetlen R.1.1.2. Era) l Prior to startup after the first refuellag outage for the 125 and 250-volt direct current systems for Divisions 1 and 2 and the 125-volt Division 3 direct current system, the following additional instrumentation shall be provided in the control rooms (1) Battery current (someter-charge / discharge), (2)
Battery charger output voltage (voltmeter), (3) Battery charger output current (ssuneter), (4) Battery high discharge rate alarm, and (5) Battery charger trouble alare. In the interim, the licensee shall implement approved procedures to monitor f, -
battery current, battery charger output voltage, and batter charger output current at the local panels at least once per eight hour shift..
(23) Remeter coneml - nt Elmetrieml:Penetratlana f Beetlen R .4.1. tra)
Prior to startup after the first refueling outage, a redundant fault current device (circuit breakers or fuses) shall be provided on each penetrating circuit that would limit a fault current surge to be less than the surge for which the penetration is qualified except for low energy (millisaps) instrument systems.
==A (24) Eenarmelon of cimes ir Mon cinas 1E cable Temwn (Emetion n.4. a . i. men, mere si, amen a2 )
Prior to startup after the first refueling outage, the licensee
. shall provide adequate separation or barriers between Class 1E and adjacent non-Class 1E cable trays.
Ren, mare 52, atra 31)
(25) Fire Protectlen Procram (Emetion 9.E.
n - -
(a) The licensee shall maintain in effect and fully implement all provisions of the approved fire protection plan. In addition, the licensee shall maintain the fire protection program set forth in Appendia R to 10 CFR Part 50, except )
for the following deviationst
_f v 0011k 1
- . - - - . . - - - . - . - - - - . _ . - ~ . . - . - . - _ . - ~ - . - _ . ~ . _ . - . ~
t 9- 04/10/89 i , License No. NPF-11
. . - .s.
l t j (1) Bydrostatic hose tests in accordanoe with NEPA 1962-1979, and l
- j (ii) No automatic fire detection systems in areas 2K/3K and 584.
1 j f> (b) Prior to initial criticality, the licensee shall install a I
) 1-hour rated barrier on all four sides of a partially f
2 protected power cable pan and a general sprinkler system, both located'in the diesel- generator corridor.
(c) Prior to startup af ter the first refuellag outage, the licensee shall provide fire protection systems in fire areas 2C/3C, 4C3 and 6E. {
l i
! (d) Prior to startup af ter the first refueling outage, the i licensee with respect to fire doors shall implement one of the followings
) ,(1) Perform an engineering review of the manufac-turer's certified doors and door frames by a J
nationally recognised laboratory to certify that f i
i the door and door frames provide the required j fire resistance rating, or 5
(ii) Test a replicate "as installed" door assembly by a nationally recognised laboratory to determine the door rating, or .
(iii) Replace manuf acturer's labeled doors and door frames with UL rated items.
(e) Prior to startup after the first refueling outage, the licensee shall demonstrate the adequacy of its fire protection for record storage.
-_ ____-/- __
Am. 14 (26) DELETED 5/05/83 (27) f=dustrial security (section 13.s, men, amen as)
Am. 65 CECO shall fully implement and maintain in effect all 4/10/89 provisions of the Commission approved physical security, guard training and qualification, and safeguards contingency plans including smendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to-10 CFR 73.55 (51 FR 27817 and 27822) and to the_ authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain 0011k
\-
E Y INSERT A The licensee shallimplement an maintain in effect all provisions of the approvers R<,
Protection Program as describe in the Updated Final Safety Analysis Report for Lx3alle County Nuclear Station, and as in the SERs for NUREG4519, NUREG4519 Supplement 2, NUREG4519 Supplement 3, NUREG4519 Supplement 5, NUREG4519 Supplement 7, and NUREG4519 Supplement 8, subject to the following provision:
The licensee may make changes to the approved Fire Protection Program without prior Commission approval only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
( i 4
l i
i l
1 l
l i
( ;
i 1
l .
l .
i ADMINISTRATIVE CONTROLS f
i i 1. At least one licensed Reactor Operator shall be in the control room l when fuel is in the reactor. In addition, while the reactor is in !
i 0PERATIONAL CONDITION 1, 2 or 3, at least one licensed Senior I
! Reactor Operator who has been designated by the Shift Superviser to ;
! assimo the control room t;1rection responsibility. s. hall .be in the j Control Room.
l 2. A radiation protection technician s shall be on site when fuel is in l the reactor.
l i 3. All CORE ALTERATIONS shall be observed and directly supervised by i either a licensed Senior Reactor Operstar er Senior Reactor Operator l Limited to Fuel Handling who has no other concurrent responsibilities 1
! durirg this operation.
- 4. hte Fire Brigade of at least'5 members sha1T be maintained onsita (be,httd at ell times *. The Fire Brigade shall not include the Shift Supervisor,
- the Gtation Control Roon Engineer and the 2 other members of the mini- l
- mus shift crew necassary for safe shutdown of-the unit and any personjne i
cuired for__other assential functions during a f% -- gra
- 5. The Onsite Nuclear Safety Group (0NSG) shall fMion to examine unit operating characteristics..NRC issuances, in&!stry advisories, Licensee Event Reports and other sources of plant design and operst-
! ing experience information, including plants of.similar design, j which may . indicate areas for improving unit safety. The ONSG shall i . be cosposed of at least three, dedicated, full-time engineers of
! - multi-disciplines located on site and shall be augmented on a part-l ( time basis by personnel free other parts of the Commonwealth Edison i Company organization to provide expertise not represented in the j group. The 0NSG shall be responsible for maintaining gurveillance of unit activities to provide independent verification that these a
! activities are performed correctly and that htman errors are reduced
- as such as practical. The 0NSG shall sake detailed recommendations
! for revised procedures, equipment modifications, maintenance activi-1 ties, operations activities or other means of improving unit safety
! to the Safety Assessment' Manager and the Station Manager.
l 6. The Station Contrtil Roan Engineer (SCRE) may serve as the Shift l Technical Advisor (STA) during abnomal operating and accident con-i ditions. During these conditions, the SCRE or other on duty STA shall i provide technical support to the Shift Supervisor in the areas of i thermal hydraulics, reactor engineering and plant analysis with regard j to the safe operation of the unit.
~
l fThe radiation protection technician and Fire Brigade composition may be less than the minisus requirements for a period of time not to exceed two hours in
! order to accommodate unexpected absence provided inmediate action is taken to *
) fill the required positions.
- Not responsible for sign-off feature.
U
! LA SALLE - UNIT 1 6-2 Amendment No. 78 c
j ,
i
1
! . \
. ,' . 03/24/04 '
{
Lisease Be. NFF-18
,- e l
i
- p. (34) e -e,s er a.- , u.a- taneet-- e.i. ;--- si. m** ant t
j Prior to startup after the first refeellag, the 11eessee shall j
have made emanitments aeseytable to the NaC regarding the guideliase of Seetles 5.1.2 through 5.1.8 of NUREG-o611.
4 i
(15) Fire ee.+= +<a= ora- terrea- e s, m.m. ;; - an ;--- as._
i
=2-- an. ;--- av. --- an.
i 1
' (a) The liseneee shall meistain la effect all previsions of.
I the approved fire protection program.
i (b) Prior to initial criticality, the licensee shall replace
{ the B diesel fire pump engine and perform a test la j
a ee mrcanoe with Sectione 11-1.3,11-1.3 and 11-1.5 of i ursh lo/iss2. .
... . .. . . .l Tab Priar ta laatist eritionney,. the liseneee shall revise 4
I J
.T .
.f f the ure protection leep fler test la asserdamos .
%
- Y>Jwith
- 18 emmath section inteavals.
- 11.3 of SFP&-39/1353 and be esadseted en
'f l
" ' 44f'Pu er to laitial criticality, the 11oessee shall revise r the fire protesties leep flee test la esserdamse with
.g, Cheyter 5 Secties il ef. the Fire Ptseetles Easdbook, leth
'.. Fire Protecties
- ,; i g.,N' Asessiatles -g, . saition
.' yehuaham by the ==*a-1
? .:.. . ;t Q;.' M ; ..s.: ..
i (
j n' - ' S' :. , . .w ,
j
. ' {" -.%F.lPriertaetastayafter/the
- ) first reisen as estage, the f' nesseee shan replacer eyyresametely 110 feet of fear-iaek i
yiye feeding the: sprinkler system is the cable spreedlag k ,.
s 'sees le . with ala-lack-pipe to effectively reduce the.fristles
! (EP, Prior to esseeding five peroomt power, the 11eemsee shan provide a history of the deviations eheerwd la operaties
" , '
- of the diesel 21Jre tempo.
. th prior to esseediay five persest poser, the usenese chan
~
. ,;,., C's.;4
- ;t
de the resales er as smalreis of the servie water
( -1y
, .s eretem'ar sayability to perfers as a keskup water supply i - (. y[.
' .fier'the fire protecties. Thie assaysis will laslade a '
r.eeeeriytles of the surveinasse procedures for the service
{
i 4].g#gh,
.- v.* .. aster yemy eyeten whom amed as a fire protecties water i
". supply, and as evalsaties of limitatione on the service ,.
{ water eyetas due to the mee.of these pumpe as a fire water
- eupply.
t 0011k ,
i
~: -
, 1
- j. '
INSERT W t _ _
i I 1 t' .
I a
4 4
-m . . y . :
c o. n
. --.o
~. ~, - m. p >* e, ; -- s e. ~ > . vcw w-
. . . * + - .
- 1
{ , , -
04/10/89 j
Llosase No. EFF-18
,, , . .. m.; : -
I
( .-
4 (h) Prior to escoedlag five percent power, the licensee shall i provide a surveillance program for NEC staff approval to i l ensure operability,of the fire dampers. This programm will j
imelude a perledic operability test of a sample populaties j of accessihas dampers.
i
' (1) Prior to escoeding five pereest power, the licensee shall ;
assure, is a mammer. acceptable to the ERC staff, that a !
fire la a single fire some will not result la the inadvertest spealag of all three high/ low pressure latertace valves between the remeter eere Aseleties
- 3. cooling and residual heat removal systems.
I l (j) Prior to startup after the first refuellay estate, the
- ; ~
11eemsee shall provide the suppression pool level and
'4 temperature mesitorias lastrimiestaties at the remote .
l .
"'.ahutdows pomel ukisk are electrically isolated ires the j *c-7 l# ~E i. a sentrol team, med assere the imetruseastataan are operable
- with the accessary surveillanee procedures-is place.
t...
' (k)- Prior te startup after the first refueling estage, the 11eemose shall assure, is a mammer aseeptable to the ESC
. ' ' ., staff, that a fire is any single sees will met affest
.a austrei of the fuel oil transfer pumpe for diesel -
! .( ,- i- Aeres"D" and "1&". -
- ( -
. . ..:
- c , . _
l . .
(16)i t.nematrini seenrity fsaeelas 1.1.s. swe. **** sf. en*e as) .
i Am. 44 .
. . 9 l 4/10/89 CECe shall fully Amylement and malatala la effect all i
provisieme of the Commissies approved physical seemrity, guard l troisisy and qualifiestica, and safeguards oor.tiagemey plans I
, assauding amemaments made yarsuant te provimiens of the Mises11 assess Amenenesta and Search Requirements revisions to le CFR 73.55 (51 FR 27817 and 17833) and to the aetherity of 10 l .CFB S0.90 and 18 CFR 50.54(p). The plans, which contais ,
i Safeguards Informaties protected under le CFR 73.21, are I -
, , antitleg =rma=11= Coasty Nuclear Statiest Security Plan," with
! . s. serialens submitted through Jime 1,1984; "LaSalle Ceesty
! - ?~b f l ^Q, y .sosseem. power .Plaa," Station Seentty Persommel with revisieme submitted through Training Juneandp 13, sa m mes ,
! c :. 32909r sude"f-man 11* County suelear Power Staties SafeTuards l '*' , ,,, -
'7,J."' '" . ~ , Flas," with- revisions sahaitted thrM February 15, i %. . M ./, Change made is accordance with 10 CFR 73.55 shall he
.- implemented is escordance with the schedule set forth therois.
(17) v.a e.a .1 %., . _ 2 t==--1 14- ===. ;--- ett i
- The liesssee shall coadmet the ialtial.startup test program I (set forth la secties 14 et the licensee's Final Safety haalysis Report, as amended) withest maklag modifications of this program unless such endafications are la accordence with i ,
' previsions of 10 CFR Secties 50.59. In addities, the licensee i 00111 .
i 4
~
- A"% t % '
The licensee shall implement an maintain in effect all provisions of the approved Fire Protection Program as described in the Updated Final Safety Analysis Report for LaSalle County Nuclear Station, and as L....... 'n the SERs for NUREG4519, NUREG4519 Supplement 2, NUREG 0519 Supplement 3, NUREG-0519 Supplement 5, NUREG4519 Supplement 7, and j NUREG-0519 Supplement 8, subject to the following provision: -
3 The licensee may make changes to the approved Fire Protection Program without prior Commission approval only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire, i
J 4
a f
e 4
l '
~
l .~- ,
~
ADMINISTRATTON CONTROLS
- L At 1. east one licensed Reactor Operator"shall be in the control roca
- when fuel is in the reactor. In addition, while the reactor is in 4 OPERATIONAL CONDITION 1, 2 or 3, at least one licensed Senior
! Reactor Operator who has been designated by the Shift Supervisor to
, assume the control room direction responsibility shall be in the
- Control Room.
- 2. A radiation protection technician
- shall be on site een fuel is in the reactor.
l 3. All CORE ALTERATIONS shall be observed and di.ectly supervised by j either a licensed Senior Reactor Operator or Senior anactor Operator
! Limited to Fuel Handling who has no other concurrent responsibilities
, Delth during this operation.
- 4. f site Fire Brigade of at least 5 seabers shall be unintained onsita i at all times". The Fire Brigade shall not include tte Shift Supervisor pthe Station Control Room Engineer and the 2 other members of the mini-
. num shift crew necessary for safe shutdown of the unit and any person-l si reevired for other essential functions durina a fire mc;ra l 5. The Onsite Nuclear Safety Group (0NSG) shall function to examina j unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports and other sources of plant design and operat-
) ing experience information, including plants of similar design, i which may indicata areas for improving unit safety. The 0NSG shall i be composed of at least three, dedicated, full-time agineers of
( sulti-disciplines located on site and shall be auguested on a part-time basis by personnel from other parts of the Commewealth Edison Company organization to proyide expertise not represented in the s group. The 0NSG shall be responsible for maintaining gurveillance of unit. activities to provide independent verification that these activities are performed correctly and that tuman ersers are reduced as auch as practical. The DNSG shall make detailed secommendations for revised procedures, equipeent modifications, maistanance activi- j ties, operations activities or other means of improving unit safety to the Safety Assessment Manager and the Station Marager.
- 6. The Station Control Room Engineer (SCRE) may serve as the Shift Technical Advisor (STA) during abnormal operating asd accident condi-tions. During these conditions, the SCRE or other os duty STA shall provide technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering and plant snelysis with regard '
to the safe operation of the unit. .
The radiation protection technician and Fire Brigade composition usy be less than the minimum requirements for a psriod of time not to ammed two hours in order to accommodate unexpected absence provided immediata action is taken to t fill the required positions.
I #N ot responsible for sign-off feature.
^ .
a LA SALLE - UNIT 2 6-2 Amendment No. 62 L _ _ - -