ML20132B577

Proposed Tech Specs 3.13 Re Fire Protection Sys

ML20132B577
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	12/10/1996
From:	VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20132B575	List: BVY-96-155, Application for Amend to License DPR-28,requesting Rev to TS to Relocate Fire Protection Requirements ML20132B577
References
NUDOCS 9612170305
Download: ML20132B577 (44)

Text

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o United States Nuclear Regulatory Commission l

Enclosure A Marked-up Technical Specification Pages l

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9612170305 961210 PDR ADOCK 05000271 P

PDR I

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A verification or coding system for emergency messages between Vermont Yankee and the state police headquarters of the respective states and the Coannonweal th.

14.

Vermont Yankee shall furnish advance notification to MDPH, or to another Cocanonwealth agency designated by MDPH, of the time, method and proposed route through the Commonwealth of any shipments of nuclear fuel and wastes to and f rom the Vermont Yankee f acility which will utilize railways or roadways in the Commonwealth.

ed with d is e quired to emplete the I

F.

e censee pay pro mod ficatio e ident.ied in P ragraph 3.1.1 the gh 3.1."

of the M 's re r tect n Safety Evaluat on (SE) th fac hy date A-43 J uary 1, 1978. These m ificati a shall complet d as 1.13 8 specifie in Tab e 3.1 of he SE.

In additi, the li ensee sh 11 submit he addi ional in' r=ation identifie in Table 3.2 of t is SE in ac ordance ith the chedule ontained

erein, n 'the ev t thes dates f r submit 1 canno be met, e licens e shall a mit a rep rt, expl ining the circumstances, tog ther wit arevise/

d se edul K g

A 3.G.

Security Plan The licensee shall fully implement and maintain in ef fect all provisions of the Cocznission-approved physical security, guard A-107 training and qualification, and safeguards contingency plans 8.25.88 including amendments made pursuant to provisions of the 10.20.88 Miscellaneous Amendments and Search Requirements revisions to 10CFR73.55 (51FR27817 and 27822) and to the authority of 10CET.50.90 and 10CFR50.54(p). The plans, which contain Saf eguards Information protected under 10CFR73.21, are entitled: " Vermont Yankee Nuclear Power Station Physical Security Plan," with revisions submitted through March 16,1988; " Vermont Yankee Nuclear Power Station Training and Qualification Plan," with revisions submitted through November 10, 1982; and " Vermont Yankee Nuclear Power Station Saf eguards Contingency Plan," with revisions submitted through December 30, 1985. Changes made in accordance with 10CFR73.55 shall be implemented in accordance with the schedule set forth therein.

3.H.

This Paragraph Deleted

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F. rc,

VYMPS TABLE OF CONTENTS (Continued)

LIMITING CCNDITIONS OF OPERATION Pace No.

SURVEILLA11CE D.

Control Rod and Control Rod Drive Maintenance.................

232 D

E.

Extended Core Maintenance..............

233 E

F.

Fuel Movement.....................

235 F

C.

Crane Operability...........

235 C

H.

Spent Fuel Pool Water Temperature.........

236 H

l BASES 237 e

x 4.g 3.13 FIRE ROTECT N SYST 40 l

Bc5 252 N

5.0 DESIcN FEATURES...............................

253 6.0 ADMINISTRATIVE CONTROLS......

255 l Amendment No. n, H, G, 84, 95

-v-

a VYNPS 1.0 DEF:NITIONS X.

Transition Ecilinc - Transition boiling means the boiling regime between nucleate and film boiling.

Trans ttien boiling is the regime in which both nucleate and film boiling occur intermittently with neither type being completely stable.

Y.

Surveillance Frecuenev - Unless otherwise stated in these specificattens, periodic surveillance tests, checks, calibrations, and examinations shall be performed within the specified surveillance intervals.

These intervals may be adjusted plus 25%.

The operating cycle interval is considered to be la months and the tolerance stated a bove is applicable.

Z.

Surveillance Interval - The surveillance interval is the calendar time between survelliance tests, checks, calibrations, and examinations to be performed upon an instrument or component when it is required to be operable. These tests unless otherwise stated in these specifications may be waived when the instrument, component, or system is not required to be operable, but these tests shall be performed on the instrument, component, or system prior to being required to be operable.

/%

v Y

W AA. / ital F, ire Suoetession/ ater System - The v tal fi e supp ession W

water ystem 1 that art of ne fir supp ession system which prote es thos instr..ents, capone.ts, ar syst s req"; red to per' rm a s

.e shutd wn of he rea tor.

.he vit 1 fire suppres ion sy mem inc des th water upply, umps, and di tribut~ n pipi.g with a sociate sectior liting valves which provid immedi te cov rage of he Reae

.r Buil

.ng, Co trol R m Building, d Dies 1 Gener tor

' DE LETE D '

^ *** A BB. Source Check - The qualitative assessment of' channel response when the channel sensor is exposed to a radioactive source.

CC. Cose E uivalent I-131 - The dose equivalent I-131 shall be that concentration oc I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134 and I-135 actually present. The thyroid dose conversion f actors used for this calculation shall be those listed in NRC Regulatory Guide 1.109, Revision 1, October 1977.

DD. Solidification - Solidification shall be the conversion of wet wastes into a form that meets shipping and burial ground requirements.

Suitable forms include dewatered resins and filter sludges.

EE. Memberts) of the Public - Members of the public shall include all persons who are not occupationally associated with the plant.

This category does not include employees of the utility, its contractors or vendors.

Also excluded f rom this category are casual visitors to the plant and persons who enter the site to service equipment or to make deliveries.

FF. Site Soundarv - The site boundary is shown in Figure 2.2-5 in the FSAR.

GG.

Deleted HH.

Deleted G4, M4, 124 4

Amendment No. 44, 94, 44,

~r

1 VYNPS 3.10 LIMITING CONDITIONS FOR 4.10 SURVEILLANCE REQUIREMENTS OPERATION a

c.

From and after the date that one of I

the-two 24 volt 3

ECCS i

Instrumentation Battery Systems is made or found to be inoperable for any reason, continued reactor operation is permissible only i

during the succeeding three lays unless such Battery System is sooner made operable.

d.

From and after the date that the AS-2 125 Volt battery system is made or found to be inoperable for any reason, continued reactor operation is permissible provided Diesel

. Generator DC-1-1A control power is i

transferred to J

Station Battery Bl.

a ire wa h ~

'T

/anta is d

)

ns et he ab va t mi o

e ry wo our e.

From and after the date that one of the two 24 Volt Neutron Monitoring and Process Radiation Monitoring battery systems is found or made to be inoperable for any reason, continued reactor operation' J

is permissible providing the minimum channel requirements of Sections 3.1 and 3.2 for the Neutron Monitoring and Process Radiation Monitoring systems are met.

Amendment No. GB, 444, 125 216

VYNPS 4.13 SURVEILLANCE REOUIRCMENTS 3.13 LIMITING CONDITIONS FOR OPERATICN 3.13 FIRE PRCTECT!CN SYSTEM 4.13 FIRE PPOTECTION SYSTEM Aeolicabilitv:

Aeolicabiliev:

Applies to the operational Applies to the surveillance status of the fire protecticn requirements of the fire systems.

protection systems.

N obiective:

obiective:

s To ssure adequate capability To verify the operability of to

• ect and suppress a fire the fire pro ection systems, which uld affect the safe shutdown f the reactor.

Soecificatic Soecif':ation:

A.

Fire Cetecti A.

ire Detecticn 1.

Except as sp ified in 1.

Each of the sensors Specification 13.A.2 specified in 3.13.A.1 below, the minim',

and their associated number of fire instruments including detection sensors an-the supervisory their associated circuitry shall be instrument for each demonstrated operable location shall be at least once per operable in accordanc 6 months.

with Table 3.13.A.1, whenever the equipe nt it protects is re aired to be operable.

2.

Frem and aft. the date i

that less t an the minimum n ' Joer of sensors their associ ed instruments are f nd to be oper ele, a fire watch sha.1 be established to

~%

i scect the location J

has b ee.o cleietecl it'h the inoperable

' T-his page, sensor or instruments at least once every A

/

hour.

Restore the required number of sensors and instruments to operable status within 14 days or submit a report within the next 30 days to the Commission as specified in 6.7.C.2 outlining the cause of malfunction and the l

plans for restoring the instrument (s) to j

cperable status.

Amendment No. 43 240

1 l

1 i

VYNPS l

3.13 LIMITING CCNDITIC!!S FOR 4.13 SURVEILI.ANCE REQUIREMENTS I

OPEPATION l

B.

Vital Fire Suceression B.

Vital Fire Sucorassion Water Svstem Water System I

-1.

Except as specified in 1.

The Vital Fire Specification 3.13.B.2 Suppression, Water and 3.13.3.3 below, the System shap be

-Vital Fire Suppression demonstra ed operable:

Water System shall be erable with:

a.

.At east once per I

m th by starting I

a.

"wo fire pumps acP pump and o-rable and lined operating it.for up o the fire IS~ minutes.

supp ssion loop.

At least once each i

b.

Water av lable month by_ verifying frem the each valve in the l'

Connecticut.iver.

flow path is in its correct position.

c.

An operable fl (For electrically l

path capable of supervised valves, j

l taking suction fro adequate 1

the Connecticut verification is a River and visual check of transferring the electrical water through the indication.)

distribution piping with operable c.

At least once each l.

sectionali:ing year by performance E

control or of a system flush 1

isolation valves o of the yard fire l

the yard hydrant loop.

curb valves an the t

hose station d.

At least once per isolation va ves.

? months by c'

ling each 2.

From and after the date tes ble valve in that less th the the't ow path above requi* d through at least equipment is operable, one comp. te cycle restore t e component of full er vel.

to oper le status within days or submit e.

At least once ach a rep.c within the 18 months:

next 0 days to the Com ission as specified 1)

By performing l

1 6.7.C.2 outlining a system e plans and functional l-rocedures to be used test by to provide for the loss simulating of redundancy in this sequential system.

automatic start of the 3.

With the fire suppression fire pumps as water supply system applicable to inoperable; maintain the Vital Fire a.

Establish a backup Suppression fire suppression Water System water system within pressure of at 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; and least 125 psig.

Amendment No. 43 241

=

I 4

l VYNPS a

1 3.13 LIMITING CCMDITIONS FCR 4.13 - SURVEILLANCE RE;UIREMENTS l

OPERATION b.

Submit a Special 2)

~By verifying Report as specified that each pump will develop a in 6.7.C,2; flow of at-1)

By telephone least 2500 gpm within at a discharge l

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, pressure of at lease 115 psig 2)

Confirmed by corrected for.

telegraph, river water mailgram, or level.

facsimile transmission

)

Cycling each no later than valve in the i

he first flow path that w -king day is not

]

foi owing the testable I

even and during plant cperation 3)

In writi through at within 14 ays least one 1

following th complete cycle

event, of full outlining the travel.

j action taken, the cause of f.

At'.least once per the 3 years by inoperability perf:rming a flow-and the plans test in accordance and schedul with Chapter 5, i

for restor ng Section II, of the

~

the syst to Fire Protection operabl

Handbook, 1

statu, or' 14th Edition, ublished by the

-]

c.

Ifa.a ve cannot t tional Fire be ful' lied, place Pr ection-the r actor in het Asso.iation, star by within the ne e six (6) hours 2.

The fire pu...

diesel i

,d in cold engine shall.

shutdown with the demonstrated OP RABLE:

following thirty (30) hours, a.

At least once r

month by verifying;'

1)

The fuel storage tank contains at least i

150 gallons of fuel, and 2)

The diesel starts from ambient conditions and operates for at least 20 minutes.

Amendment No. 43' 242

-w,,r y

.c

~

VYNPS 3.13 LIMITING CONDITIOt!S FOR 4.13 SURVEILLANCE REOUIREMENTS OPERATION b.

At least once per quarter by-verifying that a sample of diesel fuel from the fue storage tank is within the acceptable limi specified in Table 1 of AST.4 D97 5 - 6 8 w th respect to viscosity,. w er content, and sediment.

At least o ce per 18 months y verifying the dieselas arts from mbient onditions the uto-start s -nal and operates to 3 0_ minutes whi e loaded with the ire pump.

3.

The fir

..p diesel startir, 2 -volt batte ban and charg r shal be demo trated PERABLE:

a.

At least on e per week by verl'ying that:

1)

The electrolyt level of ea h battery is above the plates, and 2)

The overall ba t t e ry voltage is 3 24 volts, b.

At least once per quarter by.

verifying that the specific gravity is appropriate for continued service of the battery.

c.

At least once per 18 months by verifying that:

Amendment No. 43 243

l l

VYNPS 3.13 LIMITING C0!CITIONS FCR 4.13 SURVEILLANCE REQUIRDtEMTS O P E RATION 1)

The batteries.

cell plates and battery racks show no visual indication of physi a1 dar e or i

abe rmal i

d erioration, nd 2)

The ba t t e ry-to-battery and terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material.

j C.

Fire Rese Stations C

Fire Hese Stations 1.

Except as specified in shall be verified to be 1.

Each fire hose station 3.12.C.2 below, all hose stations inside operable:

the Reactor Building, Turbine Building, and a.

At least monthly by those inside the visual inspection Administration Building /

of the station to j

which provided coverag assure all of the Control Room equipment is Building shall be available, operable whenever equipment in the

.eas b.

A. least once each protected by the ire 18 onths by hose stations i remo ng the hose required to be for i pection and operable.

replaci degraded coupling askets 2.

With one o more of the and rerack'ng.

fire hose stations specifi in 3.13.C.1 c.

At least one each above i.eperable, route year by an ad itional hydro-staticall equi alent capacity testing each fire hose to the outside hose at unprotected area (s) 250 lbs.

from an operable hose station within one d.

At least once per hour.

3 years by hydro-statically testing inside hose at 150 lbs.

Amendment No. 44, 67 244

~

)

4 I

VYNPS i

4.13 SURVEILLANCE RE;UIRC4E2.is 3.13 f.,IMITING CON :ITIONS FOR i

OPERAT!0N e.

AC '. east once per 3 years, partially open hose station valves to. verify

{

valve operability -

and no b' ekage.

Svstem D.

Mich Pressure 2_Svstem D.

Hich P.

ssure CO 2 1.

Except s specified in 1.

The CO2 ystem-located Specifi tion 3.13.D.2, in the able vault,

{

the CO2s tems located swite, ear room, and i..

in the cabl vault, dies 1 fire pump day switchgear r m,

and taF reem shall be i

diesel fire pu..

day d.onstrated operable.

f-tank rocm shall e operable, wheneve a.

At least once per equipment in the ar six months by 2

protected by the syst verifying each CO2 is required to be cylinder does not

'i operable.

contain less than l

90% of its initial F

2.

From and after the date

charge, that the CO2 system in the cable vault or a b.

At least once per switchgear room is 18 months by inoperable, within one verifying that' the hour a fire watch shall system, including be established to associated-inspect the location at ventilation least once every hour, dampets, will

~

provided t. hat the fir actuate detection system is utematically to ; a.

operable in accord ce s'mulated actuation with 3.13.A.

If-e si al.

fire detection s stem, is also inopera le, c.

At. lea t once per within one ho a

operati cycle a continuous fi.e watch flow path est shall be es ablished shall be pe f o rraed with backu fire to verify fl suppress n equipment.

through each Restore he CO2 system'

noztle, to cpe able status withi. 14 days or sube.t a report within th next 30 days to the C..aission as specified in 6.7.C.2 outlining the cause of inoperability.and the plans for restoring the CO2 sys em to operable status.

Amendment No. 44, G, 117 245

\\

VYNPS 3.13 LIMITING CC:OITIONS FOR 4.13 SURVEILLANCE REQUIRD4CtrS OPERATION 3.

From and after the date that the CC, system in the diesel fire pump day tank room is inoperable, within one hour a fire watch shall be established to inspect the location at least once every hour.

Restore the system to nerable status within 1 days or submit a re rt within the next j

30 ys to the Commi sion as specified in 6.7 C.2 outlining the cau - of inoperabi ity and the plans for.estoring the system to o rable status.

E.

Vital Fire Barrier E.

Vital Fire Barrier Penetration Fire Sea Pena / ration Fire Seals 1.

Exc ept as specified in 1

vital fire barrier Specification 3.13.E.

penetration seals shall below, vital fire be verified to be barrier penetration functional by visual seals protecting the inspection at least Reactor Building, once per operating Control Room Building, cycle and following any and Diesel Genera tor repair.

Rooms shall be intact.

2.

From and after the date a vital fire barrier penetration fire seal is not intact, a continuous fire wate shall be establishe on at least one side f the affected penetration wit in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

F.

Sorinkler Svster, F.

Sorinkler sters 1.

Except as specified in 1.

Each of t.

sprinkler specific tion 3.13.F.2 systems spe ified in

below, hose sprinkler Table 3.13.F.1 shall be syste., listed in demonstrated operable:

Tabl 3.13.F.1 shall be ope able whenever 6.

At least once per i

e-ipment in the area 12 months by p otected by those cycling each aprinklers is required testable valve in to be operable.

the flow path through at least one complete cycle of full travel.

Amet:dment :to. 44, 67 246 i

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

i 1

)... -

VYNPS i

}

3.13 LIMITING CONDITIONS FOR 4.13 SURVEILLANCE REOUIREMENTS OPERATION i

i 2.

From and after the date b.

At least once each i

that one of the month by verifying sprinkler systems each valve in the pecified in flow path is

.n its'

+

le 3.13.F.1 is correct pos' tion.

4 ino erable, a fire (For elect ically l

'}

wate shall be supervise valves, estabi' hed within one adequate hour to 'nspect the verific tien is 4.

location-th the visua' check of inoperable rinkler elec.ical 4

system at le t once ind4:ation )

1 every. hour.

R tore the sprinkler sy tem to c.

least once per operable status w hin 8 months by;

}

14 days or submit a report within the ne 1.

Cycling each 30 days to the.

valve in.the i

commission as specified flow path that i

5 in 6.7.C.2 outlining is not the cause of the testable.

malfunction and the during plant plans for restoring the operation j

system to operable through at i

status, least one i

complete cycle i-of full i

travel.

I 2.

A visual I

inspection of the sprinkler I.

headers to j

erify their j

i egrity, and t

3.

A vi al inspec on of each no. le's spray are to verify that the spray i

pattern'is not obstructed.

4.

Verifying that automatic valves actuate to their correct position from a test signal.

d.

At least once per 3 years by performing a flew test threugh each open head sprinkler header and verifying each open head sprinkler no::le is unobstructed.

Amendment No. 67 247 q

rw g-i-

w-'-

r T-a-v-

-e-T-

-a---

a-

l l

VYNPS 3.13 LIMITING CCtCITIONS FOR 4.13 SURVEILLANCE RE2":REMENTS l

OPERATION 1

l C.

Foam Svstems G.

Foam Svstems 1

1.

Except as specified in 1.

The foam system Specification 3.13.G.2 specified in 3.13.G below, the shall be demonstrated i

Recirculation M.C.

Set operable.

oam System shall be l

r c erable with its foam a.

At leas once per cc entrate tank full 12 me..hs by (100 allons) whenever cycl'..g each the Re irculation M.G.

tes able valve in Sets ar operating.

t flow path

)

j

.rcugh at least 2.

From and a er the date one c:mplete cycle that the Rec."culation of full travel.

M.G.

Set Foam stem is inoperable, a f1 e

. At least once per watch shall be 18 months by:

established to insp ct the location at leas 1.

Cycling each once every hour; and a valve in the j

foam no::le shall 5e flow path that brought to the Reactor is not Building elevation testable containing the during plant Becirculation M.G.

cperation Sets.

A 100 gallon through at foam concentrate supply least one shall be available on complete cycle

site, cf '

11 travm 3.

Except as specified

• Specification 3.13.

.4 2.

A visual below, the Turbine inspection of l

Building Foam Sys em the foam shall be operab with system and l

its foam conce trate quipment to tank full

. -ify (150 gallone, in grity, and 4.

From and fter the date 3.

A visu 1 that the Turbine inspect. n of Buildi Foam System is the inope able a portable Recirculation foam nozzle shall be M.G.

Set Foam bro ght to the Turbine System foam B.lding Foam System nozzle area to cation.

A 150 gallen verify that foam concentrate supply the spray shall be avatlable pattern is not on-site.

obstructed.

l 4.

Foam concentrate l

samples shall be taken and analy:ed for a::eptability.

l l

Amendment No. GG, 90 248 I

i

l l

VYNPS i

i l

3.13 LIMITING CONDITIONS FOR 4.13 SURVEILLANCE REOUIREMENTS l

OPERATION At least once p r 3 years by performing air low test hrough t

Reci culation i

M.G. S foam head and ve 'fyl g each foam z:le i nobstruct d.

i l

l l

l t

l l

t t

i i

i Amendment No. 67 249

i I

VYMPS i

TABLE 3.13.A.1 FIRE DETECTION SENSORS Minimum No. of Sensors Recuired to Be coerable Sen ar Location Heat Flame Sobke j

1.

Cable Spreading R om & Station Battery Room 23 20 2.

Switchgear Room 3.

Diesel Generator Room A) 2 4.

Diesel Generator Room (B 2

5.

Intake Structure (Service '.ter) 1 1

1

)

6.

Recire Motor Generator Set Ar a 3

8 7.a Control Room Zone 1 (Control Ro Ceiling) 14 7.b Control Room Zone 2 (Control Room anels) 18 7.c Control Room Zone 3 (Control Room Pa._ls) 25 7.d Control Room Zone 4 (Control Room Pane )

10 7.e Control Room Zone 5 (Exhaust & Supp 2

Ducts) 8.a Rx Bldg. Corner Rm NW 232 1

8.b Rx Bldg. Corner Rm NW 213 (R.C) 1 1

8.c Rx Bldg. Corner Rm NE 232 8.d Rx Bldg. Corner Rm NE 2 a 1

8.e Rx Bldg. Corner Pm S~ 232 1

8.f Rx Bldg. Corner P SE 213 1

8.g Rx Bldg. Corner ra SW 232 1

8 9.

HPCI Room 10.

Torus are 12 16 11.

Rx Blde. Cable Penetration Area 12.

Refuel Floor 13 1

13.

Diesel Oil Day Tank Room (A) l' l'

1 14.

Diesel Oil Day Tank Room (8) l' l'

3 15.

Turbine Leading Bay (vehicles)

• NOTE:

The Diesel Day Tank Rooms require only one detector operable (1 flame or 1 smoke).

Amendment No. 44, 67 250

i l

\\

r 1

WNPS TABLE 3.13. F.1 SPRUDCLER S*

TEMS 1

1.

Reactor Building Penet ati Area Preaction Sysr.em 2.

Diesel Generator Roo..

S' tem 3.

Diesel Generato com B Syste..

4.

Turbine Lo ing Bay System i

i 1

5.

Dies -driven Fire Pump System l

1 l

l Amendment No. 67 251 t

_ _ _ _.. - ~ _ _. - _. _ - _

_ _ _ _ _ =. _.. _

-.m l

VYNPS BASES:

3.13 & 4 13 FIPE PROTECTION SYSTO4S On May 11, 1976, Vermont Yankee received a letter from the NRC requesti g that an in-depth evaluation of the existing fire protect ion systems b performed using Branch Tcchnical Position (BTP) APCSB

.5-1 as a guide. Concurrent with this evaluation a fire hazards ana, sis of the entire pl nt complex was required.

In an effort to clarif-the BTP an Appendix A w s subsequently issued to specifically addres operating plants. Enclose with this Appendix the NRC requested tha proposed Technical Specific ions on fire protection also be subm' ted.

The subject section 3.13

.13 and the following specific b es are those specifications evolvin from these efforts.

6 l

A.

The smoke, heat and me detectors provide e early warning fire detection capability ne essary to detect oblems in vital areas of the plant.

Surveillance equirements as ure these sensors and their associated instrumen to be ope able. When the equipment I

protected by the detectors i not re aired to be operable, specifications covering the se or and instruments do not apply.

l B,C, The Vital Fire Suppression Wat S-t em, CO2 systems, sprinkler D, F, systems and foam systems spe oficati s are provided to meet and pre-established levels of stem opera ility in the event of a G

fire. These systems pro.de the necess protection to assure I

safe reactor shutdown.

Periodic surveill ce testing provides assurance that vital ire suppression syste..

are operable.

E.

Vital fire barri penetration fire seals are p vided to assure that the fire sistance rating of barriers is no reduced by a a

penetration.

urveillance inspections shall be pe ormed to insure that the in egrity of these seals is maintained.

l The die 1 fira pump has a design consumption rate of 18 allons of fuel r.r hour; therefore, 150 gallons provides for greater than j

8h rs of operation. Additional fuel can be delivered in a ut or hour and additional fuel is on site. When the equipment rotected by the fire protection systems is not required to be operable, the specifications governing the fire protection system do not apply.

l l

l l

4 Amendment No. 44, 67 252

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VYMPS l

1 i

1 5.

The Radiation Protection Supervisor or Plant Health Physicist shall meet or exceed the qualifications of Regulatory Guide 1.8, Revision 1 (Septer.ber 1975).

6.

The Shift Engineer shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.

7.

If the Operations Supervisor does not possess a Senior Operator License, then an Assistant Operations Supervisor shall be designated that does possess a i

Senior Operator License. All instructions to the shift i

crews involving licensed activities shall then be approved by designated Assistant Operations Supervisor.

8.

The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate on-site manager; however, they shall have sufficient organi:ational freedom to ensure their independence frcm operating pressures.

v

'Y E.

Fire Br gade o' at lea t 5 me ers sh 1 be intain n-site e all

.mes.*

This e ludes member of th minimu. shift

.ew nec ssary r safe shutdo of the plant l

and ary/ perso el req' ired to other essenti 1 functions duri/g a fir emerge c A

f l

l l

l l

i i

1. Fire Br' ade com osition

..ay be les than th minimum equiren nts for a period f time

.o t to e eed 2 hou s in orde to accc :.odate nexpec-d absen e of Fir Brigade members p ovided ir ediate a tion is taken rest re the F re Brig o to with'. the mir. mum requ recents.

J%

/

N h

i Amendment No. n, n, M, M, 84, in, 1 : '., 131 256

._-___.._m 0

4

?

t VYNPS l

l I

f.

Investigate reported instances of violations of Technical Specifications, such investigations to include reporting, evaluation, and recommendations to prevent recurrence, to the Manager of Operations.

g.

Perform special reviews and investigations and i

render reports thereon as requested by the Chairman l

yr of the Nuclear Safety Audit and Review Committee.

l l

7.

Authority a.

The Plant Operation Review Committee shall be

advisory, I

b.

The Plant Operation Review Committee shall o

i recommend to the Plant Manager approval or

' "" " **** ""d*" *** ' ' '"' "'"

'h, Rewew 4 Ae Pre NI*"C%"

Preb.cMon prem W i

l

[

Mpbukg pr cedw*S 1,

In the event of disagreement between the recommendations of the Plant Operation Review Committee and the actions contemplated by the l

l Plant Manager, the course determined by the l

Plant Manager to be the more conservative will be followed with immediate notification to the l

Manager of Operations.

c.

The Plant Operation Review Committee shall make tentative determinations as to whether or not f

proposals considered by the Committee involve unreviewed safety questions. This determination shall be subject to review by the Nuclear Safety.

Audit and Review Committee.

l 8.

Records Minutes shall be kept at the plant of all meetings of the Plant Operation Review Committee and copies shall be sent to the Manager of Operations and the Nuclear Safety Audit and Review Committee.

B.

Nuclear Safety Audit and Review Committee i

i l

1.

The Committee shall consist of at least six (6) persons:

l.

a.

Chairman b.

Vice Chstrman l:

c.

Four techgically qualified persons who are not members of the plant staff.

l d.

No more than three membera shall be selected from the organization reporting to the Manager of Operations, e.

The Committee will obtain advice and counsel from scientific or technical personnel employed by the Company or other organizations whenever the Committee considers it necessary to obtain further l

scientific or technical assistance in carrying out its responsibilities Amendment No. 66, 121 259 I

l l

'tYNPS l

Any reportable occurrence shall be reported to the Manager of operations and shall be reviewed by the Plant Cperations Review Committee. This Committee shall prepare a separate, sequentially numbered, report for each reportable occurrence.

Each report shall describe the circumstances leading up to and resulting from I

the occurrence, the corrective action taken by the shif t, an attempt to define the cause of the occurrence, and shall recommend appropriate action to prevent or reduce the probability of a repetition of the occurrence.

i Copies of all such reports shall be submitted to the Chairman of l

the Nuclear Safety Audit and Review Committee for review and to I

the Manager of operations for review and approval of any recommendations.

1 l

6.4 ACTION TO BE TAKEN IF A SAFETY LIMIT IS EXCEEDED 1

l Applies to administrative action to be followed in the event a l

safety limit is exceeded.

i If a safety limit is exceeded, the reactor shall be shutdown immediately. An immediate report shall be made to the Manager of Operations. A complete analysis of the circumstances leading up to and resulting f rom the situation together with recemmendations

[

by the Plant operations Review Committee shall also be prepared.

This report shall be submitted to the Manager of Cperations and the Chairman of the Nuclear Safety Audit and Review Cc=mittee.

Reactor operation shall not be resumed until authorited by the U.S. Nuclear Regulatory Commission.

l 6.5 PLANT OPE *ATING PROCEOURES A.

Detailed written procedures, involving both nuclear and non-nuclear safety, including applicable check-of f lists and instructions, covering areas listed below shall be prepared ar.d approved.

All procedures shall be adhered to.

1.

Normal startup, cperation and shutdown of systems and ccmponents of the facility.

2.

Refueling operations.

3.

Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, l

suspected Primary System leaks and abnor=al reactivity changes.

4.

Emergency conditions involving potential or actual l

release of radioactivity.

5.

Preventive and corrective maintenance operations which j

could have an effect on the safety of the reactor.

l 6.

Surveillance and testing requirements.

7.

Fire protection program implementationfl.cluding.inimum

[ lire c*1gace qN;reme ts anc c saning.

The er.ning prog: m shal' meet or exceed t e requi ements

+

Sect'en 27

. the NF*

Code 1 6.

Tr ining s ssions wil be s:P duled a plant o eration permit ut wil be-co.pleted a speci' ed subj ts ann' ally.

itial ire (i igade e aining

..all be e mplete by Marc' 13, 19 8.

l Amendment No. +&,

+G, 83 262

.m.

'o VYNPS e.

Land Use census. Seecification 3.0.3 i

With a land use censuJ not being conducted as required by Specification 3.9.D, prepare and submit to the commission within 30 days a special report which identifies the reasons why the survey was not conducted, and what steps are being taken to correct the situation.

?

f.

ital fire Proc /etion Svstem,-

r-See ification 3.13 Wher require by Sect' n 3.13, special eports sha 1 be sub itted to he Comm'ssion fe lowing-e t

di covery o certain noperab e sensor,

i strument, ccmpon ts, or stems in the vic 1 ire prot etion sy em.

Notes outine si veillane testing or desig modificat on of se sors, in truments componen s, or sy ems whi. lead e operati n of sen rs, ins ruments, compen nts, or s seems i a degrad mode do l

not r quire spe ial rep. ting exc c who e test themselv s revea a degrade mode

^

A 3.

Environmental Radiolecical Monitorine l

Radiological Environmental Surveillance Reports covering the operation of the unit during previous calendar -year shall be submitted prior to May 1 of each year.

The annual Radiological Environmental Surveillance Report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impact of the plant operation on the environment.

l-The annual Radiological Environmental Surveillance Report shall include summarized and tabulated results of all radiological environmental samples taken during the

]

l report period pursuant to the table and figures in the l

OCCM.

In the event that some results are not available l

for inclusion with the report, the report shall be l

. submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

i With the level of radioactivity in an environmental sampling media at one or more of the. locations specified 4

d in Table 3.9.3 exceeding the reporting. levels of Table.3.9.4, the condition shall be described in the next annual Radiological Environmental Surveillance Report only if the measured level of radioactivity was net the result of plant effluents. With the radiological environmental monitoring program not being conducted as specified in Table 3.9.3, a description of i

che reasons for not conducting the program as required and the plans for preventing a recurrence shall be i

included in the next annual Radiological Enviror. mental l

Surveillance Report.

Amendment No.'&+,

95 275 l

. ~..

t United States Nuclear Regulatory Commission l

l Enclosure B New Technical Specification Pages l

l l

l

7 c.

A verification or coding system for emergency messages between Vermont Yankee and the state police headquarters of the respective states and the Commonwealth.

j 14.

Vermont Yankee shall furnish advance notifications to MDPH, or to another Commonwealth agency designated by MDPH, of the time, method and proposed route through the Commonwealth of any shipments of nuclear fuel and wastes to and from the Vermont Yankee facility which will utilize railways or roadways in the Commonwealth.

F.

Vermont Yankee shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated January 13.1978, and supplemental SERs, subject to the following provision:

Vermont Yankee may make changes to the approved Fire Protection Program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

3.G Security Plan 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 Miscellaneous Amendments and Search Requirements revisions to A-107 10CFR73.55 (51FR27817 and 27822) and to the authority of 10CFR50.90 and 8.25.88 10CFR50.54(p). The plans, which contain Safeguards Information protected 10.20.88 under 10CFR73.21, are entitled: " Vermont Yankee Nuclear Power Physical Security Plan," with revisions submitted through March 16,1988; " Vermont Yankee Nuclear Power Station Training and Qualification Plan," with revisions-submitted through November 10,1982; and " Vermont Yankee Nuclear Power Station Safeguards Contingency Plan," with revisions submitted through December 30,1985. Changes made in accordance with 10CFR73.55 shall be implemented in accordance with the schedule set forth therein.

3.H This Paragraph Deleted l

l

I

+

VYNPS TABLE OF CONTENTS l

(Continued) 1,Il4ITING CONDITIONS OF OPERATION Pace No.

SURVEILLANCE D.

Control Rod and Control Rod Drive

(

Maintenance.

232 D

l E.

Extended Core Maintenance.

233 E

l F.

Fuel Movement.....

235 F

G.

Crane Operability......

235 G

H.

Spent Fuel Pool Water Temperature.

236 H

BASES 237 i

l 3.13 DELETED j

5.0 DESIGN FEATURES....

253 l

6.0 ADMINISTRATIVE CONTROLS....

255 l

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I Amendment No M, 44, G, 64, 96,

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VYNPS l

l 1.0 DEFINITIONS i

X.

Transition Boiling - Transition boiling means the boiling regime l

between nucleate and film boiling. Transition boiling is the regime 1

l in which both nucleate and film boiling occur intermittently with neither type being completely stable.

Y.

Surveillance Frequency - Unless otherwise stated in these specifications, periodic surveillance tests, checks, calibrations, and examinations shall be performed within the specified surveillance intervals.

These intervals may be adjusted plus 25%.

The operating cycle interval is considered to be 18 months and the tolerance stated above is applicable.

1 Z.

Surveillance Interval - The surveillance interval is the calendar time between surveillance tests, checks, calibrations, and examinations to be perftimed upon an instrument or component when it is required to be operable. These tests unless otherwise stated in these specifications may be waived when the instrument, component, or system is not required to be operable, but these tests shall be performed on the instrument, component, or system prior to being required to be operable.

l AA. DELETED BB. Source Check - The qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

CC. Dose Equivalent I-131 - The dose equivalent I-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134 and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in NRC Regulatory Guide 1.109, Revision 1, October 1977.

i DD. Solidification - Solidification shall be the conversion of wet wastes i

into a form that meets shipping and burial ground requirements.

)

Suitable forms include dewatered resins and filter sludges.

l EE. Member (s) of the Public - Members of the public shall include all persons who are not occupationally associated with the plant.

This category does not include employees of the utility, its contractors or vendors. Also excluded from this category are casual visitors to the plant and persons who enter the site to service equipment or to make deliveries.

FF. Site Boundary - The site boundary is shown in Figure 2.2-5 in the FSAR.

GG.

Deleted HH.

Deleted I

l Amendment No. M, M, 44, M, M, 4-M, M 4, 4

. - ~. -.- _ -

VYNPS 3.10 LIMITING CONDITIONS FOR 4.10 SURVEILLANCE REQUIREMENTS OPERATION c.

From and after the date that one of the-two 24 volt, ECCS Instrumentation Battery Systems is made or found to be inoperable for any reason, continued reactor operation is permissible only during the succeeding three days unless such Battery System is sooner made operable.

d.

From and after the date that the AS-2 125 Volt battery system is made or found to be inoperable for any reason, continued reactor operation is permissible provided Diesel Generator DG-1-1A control power is transferred to Station Battery Bl.

l e.

From and after the date that one of the two 24 Volt Neutron Monitoring and Process j

Radiation Monitoring battery systems is found or made to be inoperable for any reason, continued reactor operation is permissible providing the minimum channel requirements of Sections 3.1 and 3.2 for the Neutron Monitoring and Process Radiation Monitoring systems are met.

Amendment No. 56, 114, 145, 216

m.. -. _ -. __

I i

l VYNPS 3.13 LIMITING CONDITIONS FOR 4.13 SURVEILLANCE REQUIREMENTS OPERATION

(

l This page has been deleted.

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Amendment No. 43, 240

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-... ~. - -

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WNPS l

3.13 LIMITING CONDITIONS FOR 4.13 SURVEILLANCE REQUIREMENTS OPERATION i

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This page has been deleted.

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Amendment No. 44, 241

._.,m VYNPS l

3.13 LIMITING CONDITIONS FOR 4.13 SURVEILLANCE REQUIREMENTS OPERATION l

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i This page has been deleted.

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Amendment No. 44,-

242 l

VYNPS 3.13 LIMITING CONDITIONS FOR 4.13 SURVEILLANCE REQUIREMENTS OPERATION This page has been deleted.

. Amendment No. 44, 243

VYNPS 3,13 LIMITING CONDITIONS FOR 4.13 SURVEILLANCE REQUIREMENTS OPERATION This page has been deleted.

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I' Amendment No. O, G, 244

.. _ _. _ _. _. - _. _.. ~ -.

m._.,_...

VYNPS 3.13 LIMITING CONDITIONS FOR 4.13 SURVEILLANCE REQUIREMENTS OPERATION i

I l

l This page has been deleted.

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Amendment No. 44 f4, 444, 245 l

l

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

VYNPS 1

3.13 LIMITING CONDITIONS FOR 4.13 SURVEILLANCE REQUIREMENTS 3

OPERATION 4

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1 9

4 This page has been deleted.

i g

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l Amendment No, G, 9, 246

-.. ~. - -

. _ -. - ~......... -.. -. -

a I

I

.i VYNPS l

4 I

3.13 LIMITING CONDITIONS FOR 4.13 SURVEILLANCE REQUIREMENTS OPERATION l

d j

.)

1 N

i 3

1 This page has been deleted.

1.

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i J.

.j -

4 t

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2 l

Amendment No. 9, 247 i

wr w..

~_

_, _.. ~... _... _.. _.. _ _...... _ _..

VYNPS 3.13 LIMITING CONDITIONS FOR 4.13 SURVEILLANCE REQUIREMENTS I

OPERATION i

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This page has been deleted.

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Amendment No. 9, %,

248 l

. - _ ~ - -........

. -.. =

.. ~

s.

VYNPS l

i 3.13 LIMITING CONDITIONS FOR 4.13 SURVEILLANCE REQUIREMENTS OPERATION i

ip.

This page has been deleted.

[

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l 4

e Amendment No. 6-7, 249 1

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m

VYNPS l

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1

[.

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i I

This page has been deleted.

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I r

I Amendment No. 44, M,

250

. <........ ~..... - -. ~ -,....... - - -.. -.. -.... ~ - -

-... -.. -. ~ -. -.. -... -. -. =..

a 4

s w

e J

VYNPS 1.4

I i

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4 i

4 W

1-This page has been deleted.

i f

f f

e 1

l' 4

f I

-l Amendment No. 9, 251

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+,,

VYNPS This page has been deleted.

I t

L Amendment No. 44, 67, 252

l VYNPS 5.

The Radiation Protection Supervisor or Plant Health Physicist shall meet or exceed the qualifications of Regulatory Guide 1.8, Revision 1 (September 1975).

6.

The Shift Engineer shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.

7.

If the Operations Supervisor does not possess a Senior Operator License, then an Assistant Operations Supervisor shall be designated that does possess a Senior Operator l

l License.

All instructions to the shift crews involving licensed activities shall then be approved by designated Assistant Operations Supervisor.

8.

The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate on-site manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

1 l

i t

i i

l l

4 Amendment No. 44, H, M, M, M, M, m, m, 256

f~

c, VYNPS f.

Investigate reported instances of violations of Technical Specifications, such investigations *o include reporting, evaluation, and recommendations to prevent recurrence, to the Manager of Operations.

g.

Perform special reviews and investigations and render reports thereon as requested by the Chairman of the Nuclear Safety Audit and Review Committee.

h.

Review of the fire protection program and implementing procedures.

l i

7 Authority a.

The Plant Operation Review Committee shall be advisory.

b.

The Plant Operation Review Committee shall recom-mend to the Plant Manager approval or disapproval of proposals under Items 6 (a) through (d) above.

1.

In the event of disagreement between the recommendations of the Plant Operation Review j

Committee and the actions contemplated Fj the 1

Plant Manager, the course determined by the Plant Manager to be the more conservative will be followed with immediate notification to the Manager of Operations.

i c.

The Plant Operation Review Committee shall make tentative determinations as to whether or not proposals considered by the Committee involve unreviewed safety questions. This determination shall be subject to review by the Nuclear Safety Audit and Review Committee.

8.

Records Minutes shall be kept at the plant of all meetings of the Plant Operation Review Committee and copies shall be l

sent to the Manager of Operations and the Nuclear Safety Audit and Review Committee.

l B.

Nuclear Safety Audit and Review Committee 1

1.

The Committee shall consist of at least six (6) persons:

a.

Chairman b.

Vice Chairman c.

Four technically qualified persons who are not members of the plant staff.

d.

No more than three members shall be selected from the organization reporting to the Manager of Operations.

e.

The Committee will obtain advice and counsel from scientific or technical personnel employed by the Company or other organizations whenever the Committee considers it necessary to obtain further scientific or technical assistance in carrying out its responsibilities.

Amendment No. 66, 141, 259 1

a

.n VYNPS Any reportable occurrence shall be reported to the Manager of Operations and shall be reviewed by the Plant Operations Review Committee. This Committee shall prepare a separate, sequentially i

numbered, report for each reportable occurrence.

Each report j

shall describe the circumrtances leading up to and resulting from

)

l the occurrence, the corrective action taken by the shift, an attempt to define the cause of the occurrence, and shall recommend appropriate action to prevent or reduce the probability of a j

repetition of the occurrence.

Copies of all such reports shall be submitted to the Chairman of the Nuclear Safety Audit and Review Committee for review and to the Manager of Operations for review and approval of any recommendations.

6.4 ACTION TO BE TAKEN IF A SAFETY LIMIT IS EXCEEDED l

I Applies to administrative action to be followed in the event a safety limit is exceeded.

If a safety limit is exceeded, the reactor shall be shutdown immediately. An immediate report shall be made to the Manager of Operations. A complete analysis of the circumstances leading up to and resulting from the situation together with recommendations by the Plant Operations Review Committee shall also be prepared.

This report shall be submitted to the Manager of Operations and the Chairman of the Nuclear Safety Audit and Review Committee.

Reactor operation shall not be resumed until authorized by the U.S. Nuclear Regulatory Commission.

6.5 PLANT OPERATING PROCEDURES A.

Detailed written procedures, involving both nuclear and i

non-nuclear safety, including applicable check-off lists and instructions, covering areas listed below shall be prepared and approved.

i l

All procedures shall be adhered to.

1.

Normal startup, operation and shutdown of systemt and components of the facility.

i 2.

Refueling operations.

3.

Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, suspected Primary System leaks and abnormal reactivity changes.

I 4.

Emergency conditions involving potential or actual release of radioactivity, i

l 5.

Preventive and corrective maintenance operations which could have an effect on the safety of the reactor.

6.

Surveillance and testing requirements.

7.

Fire protection program implementation, i

Amendment No. 44, 46, 84, 262

1 i

(

VYNPS l

l e.

Land Use Census, Specification 3.9.D l

With a land use census not being conducted as i

required by Specification 3.9.D, prepare and submit

]

to the Conni'ssion within 10 dsys a special report which identifies the reasons why the survey was not i

l conducted, and what steps are being taken to l

correct the situation.

l 3.

Environmental Radiological Monitoring Radiological Environmental Surveillance Reports covering 1

the operation of the unit during previous calendar year shall be submitted prior to May 1 of each year.

The annual Radiological Environmental Surveillance Report shall include summaries, interpretations, and an analysis of trends of the results of the radiological l

environmental surveillance activities for the report period, including a comparison with operational controls

[

(as appropriate), and previous environmental surveillance reports and an assessment of the observed impact of the plant operation on the environment.

]

The annual Radiological Environmental Surveillance t

Report shall include summarized and tabulated results of 1

l all radiological environmental samples taken during the report period pursuant to the table and figures in the ODCM.

In the event that some results are not available j

for inclusion with the report, the report shall be l

submitted noting and explaining the reasons for the d

l missing results. The missing data shall be submitted at l

soon as possible in a supplementary report.

i j

With the level of radioactivity in an environmental sampling media at one or more of the locations speci2ied i

in Table 3.9.3 exceeding the reporting levels of i

Table 3.9.4, the condition shall be described in the next annual Radiological Environmental Surveillance l

Report only if the measured level of radioactivity was j

not the result of plant effluents. With the radiological environmental monitoring program not being conducted as specified in Table 3.9.3, a description of 1

the reasons for not conducting the program as required and the plans for preventing a recurrence shall be included in the next annual Radiological Environmental Surveillance Report.

i l

1 l

i 4

4 4

i Amendment No. 64, 95, 275

)