ML20087P362

Proposed Tech Sepcs Re Fire Protection

ML20087P362
Person / Time
Site:	Pilgrim
Issue date:	03/27/1984
From:	BOSTON EDISON CO.
To:
Shared Package
ML20087P358	List: BECO-84-047, Application for Amend to License DPR-35,consisting of Proposed Change 84-03,revising Tech Specs Re Fire Protection ML20087P362
References
NUDOCS 8404060338
Download: ML20087P362 (29)

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1 ProDosed Fire Protection Amendment to Technical SDecifications Narrative:

Pursuant to Boston Edison's commitment to provide Technical Specification Amendments on Sections 3/4.12, we have submitted the following:

Title Submittal Date Section December 28, 1983 3/4.12A Fire Detection Instrumentation November 16, 1983 3/4.128 Fire Water Supply System November 16, 1983 3/4.12C Spray and/or Sprinkler System November 16, 1983 3/4.120 Fire Hose Stations October 13, 1983 3/4.12E Gaseous Suppression System Fire Barrier System September 12, 1983 3/4.12F July 11, 1983 3/4.12G Alternate Shutdown Panels The purpose of the above submittals was to provide updated Technical Specifications which would reflect changes to the plant made to PNPS in accordance with fire protection requirements. The preparation and review of the proposal segments suggested refinements, which we have incorporated into this submiltal. The refinements are identified by a parallel line with an adjacent & ; the changes which were transmitted in prior submittals are identified by a parallel line. For reviewing convenience, Attachment A contains the Fire Protartion section, while Attachment B contains other sections which are aft..: d by the relocation of Alternate Shutdown Panels into a separate section.

Proposed Chance (Refinements)

The following describe changes from the past submittals and are contained in Attachment A:

- The Table of Contents, page ii is changed to reflect 'ew titles and l

l pagination under the rubrick of Fire Protection.

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- Action c of Section 3.12A is added, which states:

For inoperable fire detectors controlling fire suppression systems, see the respective fire suppression system section, i.e. Section 3.12C for water suppression systems or 3.12E for gaseous suppression systems.

This is added to ensure that the appropriate LCO is followed for fire detectors which are part of a suppression system rather than of the detection system.

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- -Section 4.12A has been_ changed to read "...in accordance with the applicable NFPA 72A or 720 codes...". This change is made to clarify.that Table 3.12-1 contains instruments reflecting either NFPA'72A or 720; this

'is a reminder that the particular instrument being surveilled should be tested according to the code appropriate to 'it.

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- Action b.3 of Section 3.128 is deleted. This change is made because 3.12.B.b addresses reporting which would result f rom a situation that is less than the minimum discussed in Action 3.12.B.a. Therefore 3.12.B.b.3 is redundant and unnecessary.

- The "or" associated with Actions a and b of Section 3.12.c are removed.

Instead, 3.12.C.a states ". . .except as specified in 3.12.C.b and

, 3.12.c.c." This change is made for clarity, and for consistency with

' other PNPS technical specification wording.

- Action d of' Section 3.12C is added, which ' states:

Restore the system to OPERABLE status within 14 days or prepare and

< submit a report to the Commission within the next 30 days outlining the action taken, the cause of inoperability and the plans for restoring the system to OPERABLE status.

This section currently exists in Technical Specifications as Action b. It was inadvertently left out when the November 16~, 1983 submittal was made.

Action c of 3.12C has "...an equivalent water supply" simplified to

" water".

- The EXCEPTION notes associated with Sections 3.12C and 3.12F currently -

- allow an hourly fire watch patrol in place of a continuous fire watch patrol when the subject fire protection equipment is located in a designated "HIGH RADIATION AREA". This EXCEPTION will be expanded to include areas designated as " AIRBORNE RADI0 ACTIVITY AREA".

This' change is proposed to aid in Boston Edison's effort to minimize personnel radiation exposure consistent with the safe operation of Pilgrim.

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- Table 3.12-2, associated with Section 3.120, Fire Hose Stations, was reviewed and the following 19 stations were deleted:

Reactor Aux Bay RA-43 Water Treatment Area, El 23 ft.

Radwaste & Control Area RC-73 Monitor Tank Pump Area El (-) 1_ f t.

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RC-68 Radwaste Area North Corner, El (-) 1 f t.

TB-37 Reactor Feed Pump Area, El 51 f t.

TB-38 Between Feed Pumps 'and Turbine Elev.~ 51 f t.

RC-65 Outside Microwave Room El 51'ft.

RC-62 Maintenance 0ffice Elev. 37 ft.

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RC-63-37 _ Maintenance Office Ncrth End,~El 37 ft.

RC-64 Maintenance Office Area El 23-ft.

( -RC-61 Machine Shop Across from Lathe, El 23 ft.

RC-67 Access Control _ Area El 23 ft.

j Turbine Aux Bag-L -

l' TA 87-51. - Outside. Fan Room #1., El 51 f t. l l

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-_ . . ._ _ _ ., x,_._

Off Gas Retention Blde OR-92-06 '- Retention Bldg El (-) 6 f t.

Turbine 81de TB-28 URC. Control Panel El 3 ft.

TB-27 Cond Domin Area Doorway TB-33 South Wall near VSF-102A El 51 f t.

TB-30 Southeast ' Corner Pipe . Area El 3 f t.

TB-32 South Wall El 51 ft.

TB-26 Recombiner Room Door El 37 ft.

Fire' Hose Stations are listed Technical Specifications because they provide either the primary or backup fire' suppression capability for a safety related. fire area. Our review of proposed Table 3.12-2 identified that the above nineteen: hose stations can be deleted without compromising the criteria for inclusion.

Existing Section 3/4.120 deals with the CO2 System.

1 In our submittal of October 13, 1983 we proposed Section 3/4.12E, which rerlected our planned substitution of a Halon 1301 system in the Cable Spreading Room (CSR).

The CO2 hose stations associated with the switchgear rooms of Elevation 23' and 37' currently referenced in 3/4.120 were replaced with waterhose 4 stations. This change was reflected in our proposal of November 11, 1983 4 werein Table 3.12-2 incorporated the two new stations.

We intended, after testing the Halon system, to provide the appropriate surveillance parameters. However, the dump test, conducted by the system

< vendor on December 15, 1983, failed to meet the specified criteria.

The vendor and we are in the process of resolving this, but resolution will not be in time to allow us to put this system in Technical Specifications.

. We propose, therefore,'to continue with our current CO2 specification modified as follows: (1)' Section 3/4.12D will become 3/4.12E, as proposed in October,1983. This is to ease changing 'it once the Halon 1301 system is made operational. (2) Reference to CO2 hose stations for the 37' elevation switchgear room and the 23' elevation switchgear room will be removed. As stated before, these have been replaced with water stations incorporated into proposed Table 3.12-2.

The Halon system will be the subject of a separate submittal when the system meets our test criteria.

- lThe following statement.is added to Section-4.12F to clarify which barriers are of concern:

Surveillance requirements for penetrations in fire barriers described in~ specification 3.12.F are as follows:

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Reason for Change These changes are being made to reflect current plant designs and configurations which have been made over the years at PNPS in accordance with fire protection requirements.

Safety Considerations These changes do not present an unreviewed safety question as defined in

-10CFR50.59. They have been reviewed and approved by the Operations Review Committee and reviewed by the Nuclear Safety Review and Audit Committee.

Sionificant Hazards Consideration ~

The NRC has provided guidance concerning the' application of standards for ,

determining whether license amendments involve significant hazards considerations by providing certain examples (48 FR 14870). One example of an amendment.that is considered not likely to involve a significant hazards consideration is "...(11)_A change that constitutes an additional limitation, restriction, or control not presently included in the technical-specifications: for example a more stringent surveillance requirement..."

Proposed technical specifications of this type are those described above that i

add restrictions'to address plant design changes or conformance to NFPA standards.

j= Those proposed changes that are deemed desirable, but do not add new restrictions, are examples of "...(vi) A change which either may result in

< some increase to the probability or consequences of a previously-analyzed accident or may reduce in some way a safety margin, but where the results of the change are clearly within all acceptable criteria..."

Based on this guidance it has been determined that the amendment request f involves no_significant hazards consideration. Under.the NRC's regulations in 10CFR50.92,- this means that operation of the' Pilgrim Nuclear Power Station in accordance with the proposed amendment would not (1) involve a-significant increase:in the probability or consequences of an accident previously-evaluated; _or'(2) create the possibility of a new or. dif ferent kind of U accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.

i Schedule of Chance This~ amendment will be effective upon receipt of approval from NRC.

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' Fee Determination 7

Pursuant to 10CFR170.12, Boston Edison classif.ies~ this change.as' a Class III amendment. Boston Edison identified this change as one covered by-check:

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1. 837526 which accompanied our letter of .lanuary 11,.1984 to Ms. Reba M. Diggs, a4 Facilities Program Coordinator, U.S. Nuclear Regulatory Commission.

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ATTACHMENT A f

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Page No.

Survelliance 4.7 152 3.7 CONTAINMENT SYSTEMS A 152 A. Primary Containment B 158 B. Standby Gas Treatment System C 159 '

C. Secondary Containment D 160 D. Primary Containment Isolation Valves 4.8 177 3.8 RADI0 ACTIVE MATERIALS 177 A

A.. Liquid Effluents B 179 B. Airborne Effluents C. (Deleted) 182 D

D. Environmental Monitoring Program E-184 E. Mechanical Vacuum Pump 194 4.9 3.9 AUXILIARY ELECTRICAL SYSTEMS 194 A

A. Auxiliary Electrical Ee11pment B 195 B. ' Operation with Inoperable Equipment 202 4.10 3.10 CORE ALTERATIONS 202 A

A. Refueling Interlocks B 202 B. Core Monitoring 203 C

C. Spent Fuel Fool k'ater Level 205A 4.11 3.11 REACTOR FUEL ASSEN3LY A.. Ave' rage Planar Linear Heat A 205A Generation Rate (APLHGR) 205A-1 B .

B. Linear Heat Generation Rate (LHGR) C 205B C. Minimum Critical Power Ratio (MCPR) 206 4.12 3.12 FIRE PROTECTION A

206 A. Fire Detection Instrumentation B 206a B. Fire Water Supply System- 206c C

C. Spray and/or Sprinkler Systems D 206d p

l D. Fire Hose Stations E 206e E. Gaseous Suppression System 206f F

F. Fire Barrier System 206g G

G .' Alternate Shutdown Fanels t

i 206k 4.0 MISCELLANEOUS RADIOACTIVE MATERIALS SOURCES 206k 4.1 Sealed Source Contamination 2061 4.2 Surveillance Requirements a

4.3 Reports 2061 4.4 Records Retention Amendment No.

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SURVEILLANCE REQUIREMENTS LIMITING CONDITION FOR OPERATION 4.12 FIRE PROTECTION 3.12 FIRE PROTECTION Fire Detection Instrumentation A. Fire Detection Instrumentation A.

The fire detection 1. Each of the fire instrumentation for each fire detection instruments noted in Table 3.12-1, detection zone shown in Table shall be demonstrated 3.12-1 shall be OPERABLE. OPERABLE in accordance with the applicable NFPA APPLICABILITY: 72A or 720 codes by a At all times when equipment functional test at least once per 6 months.

in that fire detection zone is required to be OPERABLE.

2. The fire detection ACTION:

instrumentation nonsupervised circuitry With the number of OPERABLE associated with detector fire detection instruments alarms shall be less than required by Table demonstrated OPERABLE at least once per 2 months.

3.12.1;

a. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, establish a fire watch patrol to inspect the zone with the inoperable instrument (s) at least once per hour; and

b. Restore the inoperable instrument (s) to OPERABLE status within 14 days, 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 inoperable fire detectors controlling fire suppression systems, see the respective fire suppression system

.section, i.e. Section l-3.12C for water j

suppression systems or 3.12E'for gaseous suppression systems. 206 i

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l SURVEILLANCE REQUIREMENTS LIMITING CONDITION FOR OPERATION l

8. Fire Water Sucolv System 3 Fire Water Sunolv System

1. The Fire Water Supply System Tbe Fire Water Supply System shall shall be tested and verified be operable with: to be OPERABLE:

1. Two (2) 2000 gpm/125 psig fire a. by checking the volume of pumps which are arranged to water in each fire water start. automatically, tank at least once every 7 days.

2. Two (2) water supplies with a minimum storage quantity of b. by automatically starting 240,000 gallons of water in each fire pump at least each. once every month and running each pump for

3. Two (2) independent water flow thirty minutes at that paths f rom Item Nos.1 & 2 time.

above to each fire water sup-pression system. (3.12.C and c. by visually checking 3.12.0) every shutoff valve on the fire water supply APPLICABILITY system at least once every month for At all times when any safety related proper position.

equipment is required to be OPERABLE.

d. by cycling each fire ACTION: water supply system shutoff valve through its

a. With less than the above required full operation at least equipment, restore tne inoperable once per cycle.

equipment to OPERABLE status with-in 7 days or prepare and submit a e. by verifying at least report to the Consnission within the once per cycle that each next 30 days outlining the plans pump starts and delivers and procedures to be used to pro- at least 2000 gem while vide for the loss of redundancy in maintaining a system this system. pressure of at least 125 l

psig.

b. With no FIRE SUPPRESSION WATER SYSTEM OPERABLE, within 24 hrs. e

f. by performing a W_Mt.er Flow Test on the fire

1. Establish the backup Fire water yard loop at least Suppression Water System. once every year.

2. If the requirement of b.1 g. by verifying at least above cannot be met, an once every month that the f orderly shutdown of the diesel fire pump' fuel

-reactor shall be initiated storage tank contains a and the reactor shall be in minimum of 175 gallons of f the cold shutdown condition fuel oil.

.within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 206a

SURVElttANCE REQUIRENENTS LINITING CON 0! TION FOR OPERATION h. by verifying at least once per 3 months that a sample of diesel fuel f rom the fuel storage tank, obtained in accord-ance with ASTM 0270-77, is within the acceptable Af), limits specified in Table

" 1 of ASTM 0975-75 with respect to viscosity, water content, and sediment.

1. by demonstrating that the diesel starting 24-volt battery bank and charger are OPERABLE as follows:

1. at least once per week by verifying that the electrolyte level of each battery is above the plates and battery voltage is at least 24. volts.

2. at least once per 3 months by verifying that the specific gravity is appropri-ate f or continued service of the battery.

3. at least once per operating cycle by verifying that the batteries, all l plates, and battery l

' racks show no visu-al indication of l

physical damage or abnorwal deteriora-tion and the bat-

/' tery-to-battery and terminal connections l; are clean, tight, f ree of corrosion, and coated with anti-o corrosion neterial.

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SURVEILLANCE REQUIREMENTS LIMITING CONDITION FOR OPERATION Sorav and/or Serinkler Systees C

C.

Sorav and/or Serinkler Systems I

The spray and/or sprinkler systems The spray and/or sprinkler systems shall be demonstrated to be i

located in the following areas shall OPERABLE according to the following:

be OPERABLE except as noted below:

1. Each sprinkler system and

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' 1. Diesel Generator Room Preaction water spray system alarm sprinkler systems (including shall be tested at least detectors). once every year by opening the alarm bypass or in-

2. Diesel Fire Pump Fuel Oil spector test valve. Alarms f Storage Room wet pipe sprinkler in high rad area are to be system, tested once per cycle.

3. Auxiliary toiler Room wet pipe 2. Each wet pipe sprinkler system sprinkler system. shall be proven to be unob-structed by opening the in-

4. Recirculation Pump MG Set Room spector test connection at wet pipe sprinkler system. least once per cycle.

5. Standby Gas Treatment System 3. Each preaction sprinkler water spray system. system shall be trip tested at least once per cycle.

6. Hydrogen Supply 011 Unit preaction sprinkler system. 4. Each water spray system shall be trip tested automatically

7. Turnine Basement Addition wet by simulated actuation of the pipe sprinkler system. heat detectors at least once per cycle.

APPLICABILITY _

5. At least once per 3 years. a At all times when equipment in the spray / flow test through each open sprinkler protected area is required to head spray / sprinkler header shall be performed and each be OPERABLE.

open head spray / sprinkler ACTIONS: nozzle shall be verified to be unobstructed.

a. From and af ter the date that a spray and/or sprinkler system is ande or found to be INOPERABLE, within one hour establish a continuous fire watch patrol with backup suppression, except as speci-i fied in 3.12.C.b. and 3.12.C.c.

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6. If the suppression system of l 3.12.C.1, or 5 is inoperable, establish an hourly fire watch patrol with backup suppression provided that the detection system n in that fire area and the detectio l and suppression system for the

' redundant fire area is operable.

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LIMITING CONDITION FOR OPERATIOff SURVEILLANCE REQUIREMENTS

c. If two or more detectors of '

3.12.C.1 are found or made'to ' ',

be inoperable, within one '

hour charge that sprinkler

. system piping with water. '

h d. Restore the system to OPERABLE status within 14

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days or prepare and submit a report to the Commission within the next 30 days outlining the action taken, the' cause of inoperability .

and the plans for restoring the system to OPERABLE status.

t EXCEPTION:. When the fire area protected by a spray and/or sprinkler system is designated "HIGH RADIATION AREA / AIRBORNE RADI0 ACTIVITY AREA", an hourly

fire watch patrol may be established (e.g. for ALARA considerations) in lieu of a continuous fire watch patrol.

D. Fire Hose' Stations' D.- Fire Hose Stations

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The interior fire hose stai.lons Each interior fire hose station shown in Table 3.12-2 shall be shall be verified to be OPERABLE:

4 OPERA 8i.E.T <

, 1. At -least once per month by

.;- visual inspection of the APPLICABILJJ1:

y 7-station to assure that the At all times when the equipment in the hose and aozzle are properly area protected by the fire hose installed, station is required to bs OPERABLE.

• 2.

At least once per cycle by ACTION. removing the hose for.

, inspection, replacing any With a hose station INOPERABLE, . degraded coupling gaskets and provide an_ additional' equivalent '

reracking.

capacity hose for the unprotected area i at/from an OPERABLE hose station, *

3. At least once per three (3)

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- within one-(1) hour. years.by:

- a. partially opening each I #

hose-station valve to verify valve operability and no obstruction.

+- b. by conducting a~ .,

l i hydrostatic test:of each; h'ose:

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• LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS

1) at a pressure 50 l psig greater than the maximum i available pressure at that hose station, or

2) annually at the applicable service test pressure as listed in Table 821 of the " Standard for Care, Maintenance and Use of Hose" NFPA No.

i 198-1972, or

c. by replacing each hose with a new or used hose which has been hydrostatically tested in accordance with the pressures specified in 4.12.0.3.b.

E. CO2 System jf E. CO2 SYSTEM The CO2 System shall be The following CO2 system shall demonstrated OPERABLE:

be OPERABLE with a minimum level of 60% and a minimum pressure of 1. At least once per 7 days by 275 psig in the associated storage verifying the CO2 storage tank (s). tank level and pressure.

i 1. Cable Spreading Room 2. At least once per cycle by verifying the system valves-APPLICABILITY: and associated ventilation dampers actuate automatically At all times when the equipment in and manually to a simulated i the area is required to be- actuation signal. A brief j OPERABLE. flow test shall be made to i verify flow from each nozzle.

l -ACTION: (" Puff Test").

a. With~a CO2. system inoperable, establish a continuous fire watch patrol

' with backup fire suppression l

equipment for,the' unprotected area (s) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

.206e

SURVEILLANCE REQUIREMENTS LIMITING CONDITION FOR OPERATION E. [0 2_ SYSTEM (Cont'd)

b. Restore the system to OPERABLE status within 14 days or prepare and submit a report to the Commission within the next 30 days outlining the action taken, the cause of inoperability and the plans for restoring the system to OPERABLE status.

Fire Barrier System F. Fire Barrier Penetrations F.

Surveillance requirements for All fire barrier systems providing penetrations in fire barriers seDaration of redundant safe described in specification 3.12.F shutdown systems shall be are as follows:

functional.

1. Fire Barrier Penetration Seals APPLICABILITY:

Each fire barrier penetration At all times when the safe seal shall be verified to be shutdown systems are required to functional by a visual be operable. inspection at least once per operating cycle and ACTION: subsequent to any installation, modification or With one or more of the required maintenance affecting the fire barrier systems seal, nonfunctional, within one hour f either establish a continuous fire 2. Fire Doors watch patrol on one side of the af fected barrier or verify the Each fire door shall be OPERABILITY of an automatic fire tested once per cycle for detection or suppression system on operability of closure and at least one side of the latching mechanisms and for nonfunctional fire barrier and integrity.

establish an hourly fire watch patrol. 3. Fire DamDers EXCEPTION: When the Fire Areas on Each fire damper shall be BOTH sides of the effected fire tested once per cycle for barrier are designated "HIGH operability and integrity.

Agg RADIATION AREAS / AIRBORNE.

RADI0 ACTIVITY AREA", an hourly fire watch patrol may be a

established (e.g. for ALARA considerations) in lieu of a continuous fire watch patrol.

206f

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS G. Alternate Shutdown Panels G. Alternate Shutdown Panels

1. Alternate shutdown pansis for 1. Components listed below shall the systems listed below be operated from the shall be OPERABLE at all alternate shutdown panels times that the system is once/ cycle.

required to be operable except as specified in Core Spray 3.12G.2.

Motor operated valves.

a. Core Spray

b. RHR RHR

c. RBCCH

d. Salt Service Water Motor operated valves

e. HPCI utilizing the MCC 8-17 RCIC alternate power source, f.

g. Automatic Depressuriza-tion SSHS

h. Diesel Generators Pumps

2. With any of the alternate shutdown panels inoperable, RBCCHS immediately verify that fire detection with automatic fire Pumps and motor operated suppression for the Cable valves.

Spreading Room is OPERASLE.

If fire detection with 2. Alternate shutdown panel automatic fire suppression capability for the systems cannot be determined listed below shall ba operable, take appropriate verified to be operable action as described in once/ cycle.

Section 3.12.E of the Tech.

Spec. RCIC HPCI

3. The syrtems listed below shall be tested as follows:

AUTOMATIC DEPRESSURIZATION SYSTEM (ADS)

Perform a test from the alternate shutdown panel to verify that the relief valve solenoids actuate.

Test shall be performed after each refueling outage prior to startup.

DIESEL GENERATORS Once/ refueling outage the diesel generator control circuits shall be isolated from the Cable Spreading Room and the diesel generator started and loaded.

206g

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TABLE 3.12-1 .

. FIRE DETECTION INSTRUMENTS $

Total No. Minimum Building / Local Panel No./ Detectors Instruments g Fire Area Elevation Zone No. In Zone Operable In Zone ag Reactor. Building 91'3" C225/ 5 C-2 2 2 g Clothes Change Area a

g Reactor Building 3'0" C222/ 2A 11 9 RBCCW "A" Reactor Building 3'0" C222/B 13 11 RBCCW "B" Reactor Building 51'0" C96/A/B 8 7 Recirc. Pump M.G. Set Room Turbine Building .

37' C94/3 11 9 Switchgear Room "A"-

Turbine Building 23' C221/1B 7 6 Switchgear Room "B" C94/2 13 10 Turbine Building 37' C94/7 3 2 Battery Room "A" Turbine Building 23' C94/8 3 2 Battery Room "B"

0ff Gas Retention 23' C113/1 4 4 Building Control Room Cabinets 37' C 94/6 1 1 C221/3 3 3 C221/4 3 3 C221/5 3 3 C221/6 3 3 Ej C22!/7 3 3 p C221/8 3 3 C221/2 5 4 Vital M.G. Set Room 23' C221/1 5 4

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TABLE 3.12-1 ,

FIRE DETECTION INSTRUMENTS Total No. Minimum Acceptable g Local Panel No./ Detectors No. of Operable a Building /- In Zone Detectors In Zone Fire Area Elevation Zone No.

h.

k l Reactor Building (-)l7'6" C224/4A 3 2 2 RHR- Core Spray "A" o

Reactor Building (-)l7'6" C223/3C 3 2 RHR - Core Spray "B" 2 i Reactor Building (-)17'6" C223/3D 1

C223/3E 2 HPCI 2 1 Reactor Building (-)l7'6" C223/3A 2 1 RCIC C223/3B 23' 12 10 Reactor Building C224/4E 6

C224/4F 7 CRD - East C124/4C 9 8 C224/4D 9 8 C224/4G S 4 C224/4H 2 2 Reactor Building 23' C223/3F 9 8 CRD - West C223/3J 10 8 C223/3G 10 8 C223/3H 11 9 C223/31 2 2 18 16 Reactor Bullding 51' C225/5A1 C225/5A2 6 5 C225/5A3 2 2 4 3 C225/5A4 8 7 Reactor Building 74'3" C225/5B2 Fuel Pool Heat Exchanger Area 18 16 Reactor Building 74'3" C225/5Bl 2

C225/5B3 2 North Side 6 5 Reactor Building 91'3" C225/5C3 Standby Liquid ~

Control System-g Tank Area 26 22

$ Reactor Building 91'3" C225/5C1 North Side

TABLE 3.12-2 FIRE HOSE STATIONS

!I REACTOR BUILDING-SECONDARY CONTAINMENT ACCESS LOCK 3

z Sta. # Sta. #

P RB-13-ll7 North Wall, Elev. 117' SL-81-23 Reactor Bldg. Truck Lock RB-06-ll7 South Wall, Elev.117' Elev. 23' RB-12-91 North W all, Elev. 91' RB-05-91' Standby Liquid Control, REACTOR AUX. BAY System Area, Elev. 91' RB-ll-74 North Wall, Elev. 74' RA-41-23 Auxiliary Plant Heating Boiler Room RB-04 Fuel Pool Heat Exchanger Elev. 23' Area, Elev. 74' RA-42-06 RBCCW Loop B Area RB 51 ' North Wall, Elev. 51' Elev. 3' RB-03-51 Outside MG Set Room - RA-44-06 Condensate Demin./ Resin Corridor West Wall, Elev. 51' Area Elev. 3' RB-10-51 Inside North MG Set Airlock A Elev. 51' RADWASTE & CONTROL AREA &,

RB-14-23 Decontamination Room North Wall, Elev. 23' RC-57-01 Radwaste Stairway to Turbine RB-07-23 West Wall,-RHR Loop B Bldg. Elev. -l '

Stairway, Elev. 23' RC-69-01 Outside Radwaste Control RB-02-23 West Wall, RCIC Stairway Room Elev. -l' Elev. 23' RC-56-23 Water Box Scavenging Pump RB-16-23 Reactor Bldg. Access Area, Elev. 23' Lock Elev. 23' RC-58-23 Stairway Outside Vital MG Set RB-15-03 CRD Quadrant Room Elev. 23' Elev. 2'9" RC-72-23 Corridor Switchgear Room B RC-17-03 .RHR Quad Loop A Elev. 23' Elev. 2'9" TB-39-51 East Wall Near B-8 Load Center RB-08-03 RHR Quad Loop B Elev. 51 '

Elev. 2'9" n> RB-01-03 RCIC Quad E[ Elev. 2'9"

TABLE 3.12-2 (Continued) 3I '

• RADWASTE & CONTROL AREA (Continued)

TURBINE BUILDING

. kI S. .Sta. # RC-59-37 Stairway Outside Control Room

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Elev. 37' P' /TB-35  : West End.Eley. 6' RC-66-37 Radiation Chemical Lab -

TB-29-06 East Wall Elev. 6' Elev. 37' TB-31-51 South Wall,' Elev. 51' TB-34-51 West Wall Elev. 51'

-TURBINE AUX.-BAY'

. TA-86-51 Outside Standby Gas Room 0FF-GAS RETENTION BUILDING OR-91-23 . Retention Building, Elev. 23' OR-93-05 Retention Building, Elev. S' A

DIESEL GENERATORS DG-46 Diesel Generator Room A DG-47-23 -Diesel Generator Room B INTAKE STRUCTURE-t IS-96-23 Near Fire' Pumps' m

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1 3/4.12A FIRE DETECTION INSTRUMENTATION i

OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This 1

capability is required in order to detect and locate fires in their early stages. Prompt detection of the fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.

In the event that a' portion of the fire detection instrumentation is inoperable, increasing the frequency of fire watch patrols in the affected areas is required to provide detection capability until the inoperable

,i instrumentation is returned to operability.

3/4.128. C. D. E FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire

'r suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety related equipment is located. The fire suppression system consists of the water system, spray and/or sprinklers, CO 2 and fire . hose stations.

The collective capability of the fire suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire protection program.

In the event that portions of the fire suppression system are inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the affected equipment can be restored to service.

In the event that portions of the fire suppression water system become inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the affected equipment can be restored to service.

In the event that the fire suppression water system becomes inoperable, immediate corrective measures must be taken since this system provides the major . fire suppression capability of the plant. The requirement for a twenty-four hour report to the Commission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.

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. BASES 3/4.12F FIRE BARRIER SYSTEM The functional integrity of the fire barrier system ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility.

A functional fire barrier system, is considered to be the barrier itself with all penetration seals doors and dampers intact o operable. rapidly involving several areas of the facility prior to detection and The fire barrier systems are a passive element in the extinguishment. facility fire protection program and are subject to periodic inspections.

Safe shutdown systems are those systems which must operate after a loss of offsite power and are required to achieve and maintain safe shutdown (hot and cold shutdown) conditions.

During peruds of time when the barriers are not functional, either,

1) a continuous fire watch patrol is required to be maintained in the vicinity of the affected barrier, or 2) the automatic fire detection or suppression system on at least one side of the affected barrier must be verified OPERABLE and an hourly fire watch A patrol established fire watch patrol isuntil the a compensatory barrier is restored to functional status.

measure to survey area (s) in which the active and/or passive fire detection, suppression or barrier system (s) are in a degraded mode and is utilized for detection and reporting of fires.

.The surveillance requirements are considered to be adequate since they were detereined using accepted industry reference material as a basis applying good engineering judgement and station operating considerations.

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BASES TTE Alternate Shutdown Panels The alternate shutdown system, independent of cabling and equipment in the f ' Cable Spreading Room is provided to effectThis safe is shutdown of Pflgrim accomplished by in- in the event of a fire in the Cable Spreading Room.

stalling 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 amerpency shut-These isolation switches are ocated in down stations outside the CSR.

siternate shutdown panels and are 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 '

available to quickly detect confine and extinguish fires occurring The infire any Portion of the room where safety-related equipment is located.

detection / suppression system consists of an independent smoke detection system, an automatic Halon 1301 Fire Suppression system and fire The hose i

stations available outside the doorways to the Cable Sprea or automatic suppression is adequate to minimize potential damage to safety-related equipment and is a major element in the facility fire protection program.

An emergency shutdown procedure, which is compatible with the desigt. modifi-cations and plant operator availability,provides step-by-step actions toO initiate safe shutdown operation.

cables passing through the CSR is initiated as soon as a fire which is not imediately extinguishable is detected and confirmed in the CSR.

Alternate shutdown panels are provided for the following systems:

a. Core Spray

k. RHR

c. RBCCW

d. Salt Service Water

e. HPCI

f. RCIC

g. Automa. tic Depressurization System

h. Diesel Generators 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 an frequent testing not warranted.for' testing the diesel generators preve inoperable during nomal power operation.ing outage for the Au existing surveillance frequency for this system.to be perfomed du tions will allow for safe cccess to the ADS solenoids.

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St%*EILIANCE REQt'IREMEh7 LIMITING '.0hT1710NS FOT< OPERATION 4.5 CORE Aht C0h7AlhEh7 COOLIhG 3.5 CORE AhT C0h7AINMEh7 COOLING SYSTEMS SYSTEMS Applicability Applicability Applies to the Surveillance Require-Applies to the operational status of ment of the core end suppression poel tha core and suppression pool cooling cooling subsystems which are required

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subsystems. when the corresponding limiting Cond2-tion for operation is in effect.

Objective Objective To verify the operability of the core To assure the operability of the core and suppression pool cooling subsystems and suppression pool cooling subsystems under all conditions for which this under all conditions for which this cooling capability is an essential re-cooling capability is an essential re- sponse to station abnormalities.

spense to station abnormalities.

Specification Specification A. Core Spray and LPCI Subsysters A. Core Spray and LPCI Subsystems

1. Core Spray Subsystem Testing.

1. Both core spray subsystems shall be operable whenever irradiated Item Trequer.cy fuel is in the vessel and prior to reactor startup from a Cold Simulated Once/ Operating Condition, except as specif2ed a.

Automatic Cycle in 3.5.A.2 below. Actuation test.

b. Pump Once/menth Operability

c. Motor Operated Once/m: nth Valve Opera-bility

d. Pump flow rate.Each t

pump shall deliver at least 3600 gpm against a system head corres-ponding to a reactor ves-sel pressure at 104 psig.

e. Core Spray Headerap Instrumen-tation 103

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.' l SURVEILLANCE REQUIRDfENT I.1MITING CONDITIONS FOR OPERATION 4.5.A Core Spray and LPCI Subsystems 3.5.A Core Spray and LPCI Subsystems (Cont'd) l (Cont'd)

Check Once/ Day Calibrate Once/3 months Test Once/3 months

2. When it is determined that one ccre

2. From and after the date that one spray subsystem is inoperable, of the core spray subsystems is the operable core spray subsystee, made or found to be inoperable the IPCI subsystem and the diesel for any reason, continued reactor generators shall be demonstrated to operation is permissible during be operable immediately. The the succeeding seven days, pro- operable core spray subsyster vided that during such seven days shall be demonstrated to be all active components of the operable daily thereafter.

other core spray subsystem and active components of the LPCI subsystem and the diesel gen-erators are operable.

3. LPCI Subsystem Testing shall be

3. The LPCI Subystems shall be as follows:

operable whenever irradiated fuel is in the reactor vessel, a. Simulated Automa- Once/Sper-and prior to reactor startup tic Actuation a tir.g from a Cold Condition, except Test Cycle as specified in 3.5.A.4, 3.5.A.5 and 3.5.F.5. b. Pump Operability Once/menth Motor Operated Once/ month' c.

Valve Operability Pump Flow Once/3 d.

months Three LPCI pumps shall deliver 14,400 gpa against a system 4

head corresponding to a ves-l l

sel pressure of 20 psig.

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I.IMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMEhT

• 3.5.B Containment Coolina subsystem 4.5.B containment Coolina Subsystem

1. Except as specified in 3.5.B.2, 1. Containment Cooling Subsyster Test-3.5.B.3, and 3.5.T.3 below, ing shall be as follows:

both containment cooling subsys-tes loops shall be operable when- Item Trequen y ever irradiated fuel is in the reactor vessel and reactor cool. ant a. Pump & Valve Once/3 months temperature is greater than 212*T, Operability and prior to reactor startup from a Cold Condition,

b. Pump Capacity After pamp Test.Each RBCCW maintenance pump shall deli- and every 3 ver 1700 rpm months at 70 Ft. TDH.

Each SSWS pump shall deliver 2700 gpm at 55 ft. TDH.

c. Air test on once/5 years drywell and torus headers and nozzles

• Conditional relief granted from this LCO for the period October 31, 1980 through November 7, 1980.

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106 Amendment No. %

SURVEILLANCE REQUIREMEb7 LIMITING CONDITIONS FOR OPERATION 4.5.B Containment cooling Subsystem (Cont'd)

• 3.5.B Containment Cooling Subsystes

2. When one containment cooling sub-

2. From and after the date that one systes loop becomes inoperable, the containment cooling subsystes loop operable subsystes loop and its is made or found to be inoperable associated diesel generator shall for any reason, continued reactor be demonstrated to be operable in-operation is permissible only dur- mediately and the operable contain-ing the succeeding seven days ment cooling subsystem loop daily unless such subsystem loop is sooner made operable, provided thereafter.

that.the other containment cooling subsystem loop, in-cluding its associated diesel generator, is operable. ,

3. If the requirements of 3.5.B can-not be met, an orderly shutdown shall be initiated and the reac-tor shall be in a Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

C. HPCI Subsystem C. HPCI Subystem

1. HPCI Subsystem testing shall be

1. The HPCI Subsystem shall be oper-performed as follows:

able whenever there is irradiated fuel in the reactor vessel, reactor s. Simulated Once/ operating pressure is greater than 104 psig, Automatic cycle and prior to reactor startup from Actuation a Cold Condition, except as speci- Test fied in 3.5.C.2 and 3.5.C.3 below.

b. Pump Opera- Once/ month bility i

c. Motor Opera- Once/ month ted Valve Operability

d. Flow Rate Once/3 months at 1000 Psig

e. Flow Rate Once/ operating

, at 150 psis cycle

• Conditional relief granted from this LCO for the period October 31, 1980 through November 7, 1980.

107 AmendmentNo.iQ(

LIMITING CONDITIONS FOR OPEMTION SURVEILLANCE REQUIREMENT 3.5.C HPCI subsystes (Cont'd) 4.5.C HPCI Subsystes (Cont'd) 1 The RPCI pump shall deliver at l least 4250 gpa for a system head corresponding to a reactor pres-sure of 2000 to 150 psig.

2. From and after the date that the 2. When it is determined that the HPCI EPCI Subsystes is made or found to Subsystem is inoperable the RCIC, be inoperable for any reason, con- the LPCI subsystem, both core spray tinued reactor operation is per- subsystems, and the ADS subsystem missible only during the succeed- ,

actuation logie shall be demon-ing seven days unless such subsys- strated to be operable immediate-tes is sooner made operable, pro- ly. The RCIC system and ADS sub-viding that during such seven days system logic shall be demonstrated all active components of the ADS to be operable daily thereafter.

subsystem, the RCIC system, the LPCI subsystem and both core spray subsystems are operable.

3. If the requirements of 3.5.C can-not be set, an orderly shutdown shall be initiated and the reac-ter pressure shall be reduced to or below 104 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.5.D Reactor Core Isolation Coolins 4.5.D Reactor Core Isolation Coeling (RCIC) Subsystem (RCIC) Subsystem

1. The RCIC Subsystem shall be oper- 1. The RCIC Subsystem testing shall able whenever there is irradiated be performed as follows:

fuel in the reactor vessel, the reactor pressure is greater than a. Simulated Once/ operating 104 psig, and prior to reactor Automatic cycle startup from a Cold Condition, Actuation except as specified in 3.5.D.2 Test below.

b. Pump Opera- Once/mooth l

bility

c. Motor Opera- Once/sonth

. ted Valve Operability l

108 Amendment No. 51

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k.IMITINGCONDITIONSIOROPERATION 4.5.D Riceter Care Isolatien Coolsna 3.5.D Riacter Cera Isalatica Ceolses (RCIC) Subsystra (Ccnt'd)

[RCIC) Subsystem (Cont'd)

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d. Flow Rate once/3 months at 1000 Psig

e. Flow Rate Once/ operating at 150 cycle Psig The RCIC pump shall deliver at least 400 gpa for a system head corresponding to a reac-tor pressure of 1000 to 150 psis.

2. From and after the date that the 2. When it is determined that the RCIC RCICS is made or found to be inop- subsystem is inopera'ule, the HPCIS able for any reason, continued shall be demonstrated to be oper-able immediately and weekly there-reactor power operation is permis-sible only during the succeeding after.

seven days provided that during such seven days the MPCIS is oper-able.

3. If the requirements of 3.5.D cannot be met, an orderly shutdown shall be initiated and the reactor pres-sure shall be reduced to or below 104 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.5.E Automatic Depressurization 4.5.E Automatic Depressurization System (ADS) System (ADS)

The Automatic Depressurization Sub- 1. During each operating cycle the

1. following tests shall be performed system shall be operable whenever there is irradiated fuel in the on the ADS:

reactor vessel and the reactor a. A simulated automatic actua-pressure is greater than 104 psig tion test shall be performed and prior to a startup from a prior to startup after each Cold Condition, except as speci-refueling outage, fied n 3.5.E.2 below.

b. With the reactor at pressure, each relief valve shall be manually opened untti a cor-responding change in reactor pressure or main turbine by-l pass valve positions indicate that steam is flowing from the valve.

109 AmendmentNo.$

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$na t antst uhva a kub: run vez.ua un 4.9 AUXILIARY ELECTRICAL SYSTEM

, ,, ,3.9 AUXILIARY ELECTRICAL SYSTEM Applicability:

Applicability:

Applies to the suailiary electrical Applies to the periodic testing re-power system.

quirements of the auxiliary elec-trical systems.

Objective:

Objective:

To assure an adequate supply of elec- Verify the operability of the trical power for operation of those auxiliary electrical system.

systems required for safety. l Speciffeation: Specification:

Auxiliary Electrical Equipment A. Auxiliary Electrical Equipmer.t A.

Surveillance The reactor shall not be made criti- 1. Diesel Generaters cal unless all of the following con-

a. Each diesel generator shall be ditions are satisfied. manually started and loaded once each month to demonstrate opera-

1. At least one offsite transmission tional readiness. The test shall line and the startup transformer are available and capable of auto- continue for at least a one hour natically supplying auxiliary power period at rated load.

to the emergency buses.

During the sonthly generator test

2. An additional source of offsite power the diesel generator starting a2r consisting of one of the following: compressor shall be checked for operation and its ability to re-

c. A transmission line and shutdown trans- charge air receivers. The opera-former capable of supplying power to tion of the diesel fuel oil trans-the emergency 4160 volt buses. fer pumps shall be demonstrated, and the diesel starting time The main transformer and unit auxiliary to reach rated voltage and fre-b.

transformer available and capable of quency shall be logged.

rupplying power to the emergency 4160 volt buses.

l 3. Both diesel generators shall be oper-t able. Each diesel generator shall have a minimum of 19,800 gallons of diesel fuel on site.

b. Once per operating cycle the con-dition under which the diesel gen-erstor is required will be sieu-lated and a test conducted to dem-onstrate that it will start and accept the emergency load within the specified time sequence. The results shall be logged.

194 Amendment No. $

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