ML20099C149

Proposed Tech Spec Sections 3/4.5,3/4.7 & 3/4.9 & Associated Bases,Incorporating LCO & SRs for Shutdown Cooling Sys & Core Standby Cooling Sys During Shutdown & Refueling Conditions

ML20099C149
Person / Time
Site:	Pilgrim
Issue date:	07/24/1992
From:	BOSTON EDISON CO.
To:
Shared Package
ML20099C144	List: BECO-92-079, Application for Amend to License DPR-35,revising TS Sections 3/4.5,3/4.7 & 3/4.9 & Associated Bases to Incorporate LCO & SRs for Shutdown Cooling Sys & Core Standby Cooling Sys During Shutdown & Refueling Conditions ML20099C149
References
NUDOCS 9208030327
Download: ML20099C149 (54)

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8 I Attachment B to BECo Letter 92-Proposed Page Changes Ditcard Insert TOC i TOC i TOC ii TOC ii 103 103-104 104 106 106 110 110 111 1II 112 112 115 115 119 119 120- - - -

120 122 122 154 154 158 158 158A 158A 158B 158B 15r. -158C 159 159 166 166 166A 173 173 174A 174A 197A 199A 9200030327 920724 '

PDR ADOCK 05000293~

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LA,BLE OF CONTENil

hae No.

1.0 DEFINITIONS 1 2.0 SAFETY LIMITS 2.1 Safety Limits 6 2.2 Safety Limit Violation 6 Limitino Conditions For Operation Surveillance Requiremqd l

3.1 REACTOR PROTECTION SYSTEM .1 26

3.2 PROTECTIVE INSTRUMENTATION 4.2 42 3.3 REACTIVITY CONTROL 4.3 80 A. Reactivity Limitations A 80 B. Control Rods B 81 C. Scram Insertion Times C 83 D. Control Rod Accumulators D 84 E. Reactivity Anomalies E 85 F. Alternate Requirements 85 G. Scram Discharge Volume G 85 i

3.4 STANDBY LIQUID CON 1ROL SYSlEM 4.4 95 A. Normal System Availability A 95 i B. Operation with Inoperable Components B 96 C. Sodium Pentaborate Solution C 97 D. Alternate Requirements 97 l 3.5 CORE COOLING SYSTEMS 4.5 103 l i

A. Core Spray and LPCI Subsystems A 103 B. Shutdown Cooling System (RHR) B 106 l C. HPCI Subsystem C 107 D. RCIC Subsystem D 108 E. Automatic Depressurization System E 109 F. Minimum Low Pressure Cooling System F 110 and Diesel Generator Availability G. CSCS-Shutdown and Refueling G 110 l H. Maintenance of Filled Discharge Pipe H 111 3.6 PRIMARY SYSTEM B0UNDARY 4.6 123 A. Thermal and Pressurization Limitations A 123 B. Coolant Chemistry B 124 C. Coolant Leakage C 125 D. Safety and Relief Valves D 126 E. Jet Pumps E 127 F. Jet Pump Flow Mismatch F 127a G. Structural Integrity G 127a H. Deleted H

1. Shock Suppressors (Snubbers) I 137a Amendment No. 15, 45, 65, 133, 135 i L__-_.-. _ - . - - . -

Surveillance PJL90_HL.

3.7 CONTAINHENT SYSTEMS 4.7 152 A. Primary Containment A 152 B. Standby Gas Treatment System and B 158 Control Room High Efficiency Air filtration System C. Secondary Containment C 159 3.8 RADI0 ACTIVE EFFLUENTS 4.8 177 A. Liquid Effluents Concentration A 177 B. Radioactive Liquid Effluent B 177 Instrumentation C. Liquid Radwaste Treatment C 178 D. Gaseous Effluents Dose Rate D 179 E. Radioactive Gaseous Effluent E 180 Instrumentation F. Gaseous Effluent Treatment F 181 G. Main Condenser G 182 H. Mcthanical Vacuum Pump H 183 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 194 1

A. Auxiliary Electrical Equipment A 194 B. Operation with Inoperable Eq"ipment 196 C. Diesel Generator Requirements - Cold 197A l Condition and Subtritical l 3.10 CORE ALTERATIONS 4.10 202

A. Refueling Interlocks A 202 B. Core Monitoring B 202 C. Spent Fuel Pool Hater Level C 203 D. Multiple Control Rod Removal D 203 l 3.11 REACTOR FUEL ASSEMBLY 4.11 205a i A. Average Planar Linear Heat A 205a Generation Rate (APLHGR)

B. Linear Heat Generation Rate (LHGR) B 205b C. Minimum Critical Power Ratio (HCPR) C 205b O. Power / Flow Relationship D 205d l 3.12 FIRE PROTECTION 4.12 206 A. Fire Detection Instrumentation A 206 B. Fire Hater Supply System B 206a C. Spray and/or Sprinkler Systems C 206c D. Halon System D 206d E. Fire Hose Stations E 206e F. Fire Barrier System F 206e-1 G. Alternate Shutdown Panels G 206e-1 Amendment No. 15, 27, 45, 84, 89, 113, !!A, 133 11

! LIMITING CONDITION FOR OPERATIQN SERVEILLANCE REOUIREMENT i

j 3.5 CORE COOLING SYSTEMS l4.5 CORE COOLING S1111 tis I j Anolicability Aeolicability Applies to the operational status of Applies to the Surveillance 1 the core cooling systems. l Requirements of the core cooling l l systems which are required when the ,

! corresponding Limiting Condition for l 4 operation is in effect.  ;

d l 1

Objective Obiective I

To assure the operability of the core To verify the operability of the core i cooling systems under all conditions icooling systems under all conditions l for which this cooling capability is for which this cooling (.apability is an

, an essential response to station essential response to station i abnormalities. abnormalities.

Specification Speci fication A. Care Sorav and LPCI Systemi A. Core Sorly and LPCI Systems -

! 1. Both core spray systems shall be 1. Core Spray System Testing.

operable whenever irradiated fuel 1

is in the vessel except as 1 11210 Erggyfan speci fied in 3.5. A.2, 3.5.G.1, l

3.5.G.2, 3.5.G.3 and 3.5.G.4 below I a. Simulated Once/ Operating 3

Automatic Cycle

Actuation test.

b. Pump Operability Once/ month

c. Motor Operated Once/ month Valve Operability e

d. Pump flow rate Once/3 months Each pump shall i

deliver at least

3300 gpm against i

a system head corresponding to a reactor vessel pressure of 104 psig.

e. Core Spray Header

op Instrumentation Amendment No. 42, f;2, 114, 135 103

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i W ;t1G_ CONDITION FOR OPERATION $URVEILLANCE REOUIREMENT 3.b.A Core Sorav and LPCI Syite_ms 4.5.A Core Snray_and LPCI Systems

(cont'd) (cont'd) l Check Once/ day 1

Calibrate Once/3 months i

Test Step Once/3 months  ;

1 2. From and after the date that one 2. This section intentionally left of the core spray systems is made blank i or found ta be inoperable for any reason, continued reactor 3. IPCI system Testing shall be as 1 operation is permissible during follows:

the succeeding seven days, provided that during such seven a. Simulated Once/ Operating 1 days all active components of the Automatic Cycle l other core spray system and active Actuation

components of the LPCI system and Test the diesel generators are operable,

b. Pump Once/ month

3. The LPCI system shall be operable Operability whenever irradiated fuel is in the

reactor vessel except as specified I c. Motor Operated Once/Honth

! in 3.5.A.4, 3.5.G.1, 3.5.G.2, I valve 3.5.G.3 and 3.5.G.4. I operability i 4. From and after the date that the d. Pump Flow Once/3 mcnths LPCI system is made or found to be inoperable for any reason, Each LPCI pump shall pump 4800 continued reactor operation is gpm at a head across the pump permissible only during the of at least 380 ft, succeeding seven days unless it is sooner made operable, provided that during such seven days the containment cooling system i (including 2 LPCI pumps) and active components of both core spray systems, and the diesel generators are operable. l

5. If the requirements of 3.5.A cannot be met, an orderly shutdown

, of the reactor shall be initiated and the reactor shall be in the Cold Shutdown Condition within 24

hours.

Amendment No. 42, 62, III, Ild, 135 104 r='f -

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LIMITING CONDITION FOR OPERATION SURVEILLMCf REOUIRFHENT 3.5.B Shutdown Cnolina Svitem_ E RR1 4.5.8 Shy.tdown Cop _ lina System (RHD) i

1. When in the Hot Shutdown l 1. Shutdown Cooling Syster .-

condition and not steaming to the I shall be as follows:

main condenser, two* shutdown I Cooling Loops (SDC) shall be l llem En 4 -

operable. If the requirements of l 3.5.B.1 cannot be met immediately l Shutdown Cooling Onces,.. tys initiate corrective action to l Pump and Valve return the required loop to l Operability, operable status as soon as l Each pump shall l possible or be in Cold Shutdown I be started, and I in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. I each valve i i required to l

2. When irradiated fuel is in the l provide recir- l vessel and the reactor is in the l culation of l Cold Condition, two* SDC loops I coolant through I shall be operable and I the RHR l specifica'.fon 3.9.C shall be I heat exchanger I met. !< ' e requirements of I shall be cycled i 3.5.8.2 w A be met, I through at least I immediatt ; initiate corrective i one full cycle I action to return the required I of travel if l Ioop to operable status as soon i the'SDC loop i as possible. I is not l l already operating l

3. When irradiated fuel is in the l

vessel with the reactor head l

) removed, the cavity flooded, the l l fuel pool gates removed and water l level maintained to at least l

elevation 114'0", at least one l Shutdown Cooling loop shall be l

. operable. If the requirements of I l 3.5.B.3 cannot be met, I immediately suspend all l operations involving an increase l

in the reactor decay heat load, I i

and close all secondary I containment penetrations l

, providing direct access from i secondary containment atmosphere l to the outside atmosphere within l 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. l l

NOTE: One SDC loop may oe i inoperable for surveillance l testing provided the other loop i

! is operable. l i

! Amendment No. 42, 44, 774, 735 106

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

LIMITING CDNDITION FOR OPERATION SURVEILLANCE REQQlE[HENT l 3.5.F Hinimum Low Pressure Coqlina_and 4.5.F Hinimum low Pressure Coolina Diesel GengI_ator Availability and Diesel Generator Availability

]

1. During any period when one diesel 1. When it is determined that one  !

generator is inoperable, diesel generator is inoperable, the

continued reactor operation is operable diesel generator shall be

] permissible only during the demonstrated to be operable

succeeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> unless such immediately and daily thereafter i diesel generator is sooner made until the inoperable diesel is

] operable, provided that all of repaired.

the low pressure core and containment cooling systems and 3

the remaining diesel generator shall be operable. If this recuirement cannot be met, an 4 orcerly shutdown shall be initiated and the reactor shall be placed in the Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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2. Any combination of inoperable components in the core and containment cooling systems shall not defeat the capability of the remaining operable components to i

fulfill the cooling functions.

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3.5.G CSCS-Shutdown and Refuelina l 4.5.G rSCS-Shutdown / Refueling l l 1

1. When irradiated fuel is in the i 1. Surveillance requirements are the l J vessel and the reactor is in the I same as 4.5.A. I Cold Condition, except as I specified in 3.5.G.2, 3.5.G.3 and i 3.5.G.4 below, a combination of 2 I low pressure CSCS subsystems l

) shall be operable and l specification 3.9.C shall be met. l

2. a. Hith only one low pressure I i CSCS system available, restore I the second system in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> l or suspend operations that I have a potential for draining l l the vessel. I 4

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b. With no systems available, I immediately suspend core I alterations and activities I with the potential to drain I the vessel. Restore one I system in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or establish I secondary containment within 8 l hours. 1 I

4 Amendment No. 15, 135 110

'LlH11JNG C0E01110N FOR OPLRATION S1LRVEILLANCE RE011]EWffil

3. With the reactor head removed, the cavity flooded, the fuel pool gates removed and water level maintained to at least elevation 114'0", all low pressure CSCS subsystems may be i inoperable. Specification 3.5.8 must be met.

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4. When irradiated fuel is in the reactor vessel and the reactor is in the Refueling Condition with the torus drained, a single i control rod drive mechanism may  ;

be removed, if both of the following conditions are  :

satisfied: 1 a) No work on the reactor vessel, in addition to CR0 removal, will be performed which has the potential for exceeding the maximum leak rate from a single control blade seal if it became unseated, b) i) the core spray systems are operable and aligned with a suction path from the condensate storage tanks.

ii) the condensate storage tanks shall contain at least

! 200,000 gallons of usable

water and the refueling

cavity and dryer / separator i pool shall be flooded to at ,

i least elevation 114'-0" '

l 3.5.H Maintenance of Filled 4.5.H Maintenance of Filled l Discharae Pine Discharae Pipe L

l Whenever core spray systems, LPCI The following surveillance . .

system, HPCI or RCIC are required to requirements shall' be adhered .to to be operable, the discharge piping assure that the discharge piping of from the pum) discharge of these the core spray systems, LPCI system, systems to tie last block valve HPCI and RCIC are filled:

shall be filled, y

h Amendment No. 39, 135 -111 2

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LIMITING CONDITION FOR OPERATION SURVE1LLANCE REOUIREMENT 4.5.H Maintenance of filled Discharae Piot (Cont'd)

1. Every month prior to the testing of the LPCI system and core spray I systems, the discharge piping of these systems shall be vented from the high point and water flow observed.

2. Following any period where the LPCI system or core spray systems have not been required to be operable, the discharge piping of the inoperable system shall be vented from the high point prior to the reti!rn of the system to service.

3. Whenever the HPCI or RCIC system is lined up to take suction from the torus, the discharge piping of the HPCI and RCIC shall be vented from the high point of the system and water flow observed on a monthly basis.

4. The pressure switches which monitor the discharge lines to ensure that they are full shall be functionally tested every month and calibrated every three months, l

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i Amendment No. 39, 135 112

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) EASES 1 j 3/4.58 Shutdown Coolina System (RHB1 4

j Maintaining decay heat removal (DHR) capability is a key function during j shutdown conditions. During normal refueling outage conditions, the shutdown cooling (SDC) mode of the RHR system and its supporting systems are the l primary means of removing decay heat when fuel is in the reactor vessel. An j extended loss of the DHR function can lead to coolant boiling and potentially

result in a depletion of reactor coolant and eventual uncovering of the core.

j While irradiated fuel remains in the reactor vessel during an outage, maintaining the DHR function is important to shutdown safety.

i j When the Main Steam Isolation Valves (MSIV) or the MSly drains are open and j vessel temperture is at or above 212*F, 3.5 B.1 does not apply because the

plant is in Hot Shutdown but is steaming to the main condenser.

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j Two RHR shutdown cooling subsystems are required to be OPERABLE. An OPERABLE j RHR shutdown cooling subsystem consists of one OPERABLE RHR pump, one heat

! exchanger, and the associated piping and valves. The two subsystems have a j common suction source and are allowed to have a common heat exchanger and j common discharge piping. Thus, to meet the LCO, both pumps in one loo) or one

pump in each of the two loops must be OPERABLE. Since the piping and leat '

! exchangers are passive components that are assumed not to fail, they are j allowed to be common to both subsystems, .

] Additionally, each shutdown cooling subsystem is considered OPERABLE if it can j be manually aligned (remote or local) in the shutdown cooling mode for removal l of decay heat. An RHR pump is OPERABLE when it is capable of being powered

! and able to provide flow if required.

f The specification for two SDC loops in the cold condition includes the

condition that specification 3.9.C be met. Specification 3.9.C requires one

offsite power source and either Emergency Diesel Generator operable when in

the cold condition and subcritical.

l Specification 3.5.B.3 allows refueling operations to continue with one SDC loop operable with the reactor head removed, the cavity flooded, the fuel pool 1

~

gates removed and water level maintained to at least elevation 114'0". This is acceptable because the large inventory of water acts as a diverse method of providing backup for the decay heat removal safety function. During refueling with irradiated fuel in the vessel, the reactor head removed and the cavity i' flooded the Augmented Fuel Pool Cooling loop satisfies the requirement to have one SDC loop operable once the decay heat load is within its capacity.

Activities that can increase decay heat load are the reduction of decay heat cooling or insertion of a fuel bundle. The requirement of 3.5 B.3 to close all secondary containment penetrations providing direct access to the outside atmosphere requires the isolation of secondary containment within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> if SDC is not operable.

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i Amendment No. 115

,._.__.m._ .. - _ _ _ _ _ _ _ _ - . _ _ _ . _ _ . _ _ - -_____

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l BAS 151 .

l 3.5.f Minimum low Pressure Coolina and Diesel Generator Availabi.lity  !

l- The purpose of specifications r is to ensure adequate core cooling equipment i

! is available at all times duri:.g power operation. if, for example, one core .

i spray were out of service and the diesel which powered the opposite core spray i j were out of service, only 2 LPCI pumas would be available. During shutdown i and refueling the configuration of saared equipment is different, and l requirements for some equipment are reduced or unnecessary. (Specification ,

i 3/4.5G addresses Shutdown and Refueling conditions).  ;

Continued operation is permissible for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> with one diesel generator out ,

of service. In addition, all low pressure core and containment cooling r systems and the remaining diesel generator must be operable. If these i requirements are not met the reactor must be brought to the Cold Shutdown '

j condition and low pressure cooling requirements provided in 3.5.G become i applicable, i"

Specification 3.9 must also be consulted to determine other requirements for j the diesel generators.

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Amendment No.39- 119

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

j ..

3.5.G 0 0S - Shutdown and Refueling ,

During Shutdown and Refueling conditions CSCS requirements are reduced. .

l During Refueling, with the cavity flooded, increased coolant inventory '

{ provides sufficient time to make up lost inventory without relying on low 1 Pressure Cooling. lience, with the cavity flooded the CSCS is allowed to be l unavailable.

l A minimum of two low pressure CSCS injection / spray subsystems are required to l be OPERABLE in Shutdown and Refueling. Two OPERABLE low pressure CSCS i subsystems also ensure adequate vessel inventory makeup in the event of an i inadvertent vessel draindown. For Shutdown and Refueling conditions the low pressure CSCS injection / spray system consists of two Core Spray (CS) l subsystems and the Low Pressure Coolant injection (LPCI) system configured into two loops.

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! Each CS subsystem consists of one motor driven pump, piping, and valves to l transfer water from the suppression pool or condensato storage tank (CST) to the reactor pressure vessel (RPV),

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Each LPCI loop consists of one motor driven pump, piping, and valve

• to transfer water from the suppression pool to the RPV. Only a single LPCI pump

. is required per loop because loop in.iection capacity for shutdown and refueling conditions is less than for other operational modes. One LPCI loop i may be aligned in the decay heat removal modo and be considered OPERABLE for the CSCS function, if it can be manually realigned (remote or_ local) to the

. LPCI mode and is not otherwise inoperable. Because of low pressure and low

temperature conditions in Shutdown and Refue'i ufficient time will be "

l available to manually align and initiate LPC , ation to provide core

cooling prior to postulated fuel uncovery.

i CSCS is not required during ref911ng when the sper t fuel storage pool gate is removed and the water level is maintained at i lit feet. This configuration provides sufficient coolant inventory to allow operator action to terminate the inventory loss prior to fuel uncovery in case of an inadvertent draindown.

I Specification 3.5.G.4 allows removal of one CRD mechanism while the torus is-in a drained condition without compromising core cooling capability. The available core cooling capability for a potential draining of the reactor i vessel while this work is performed is based on an estimated drain rate of 300 l gpm if the control rod blade seal is unseated. Flooding the refuel cavity and dryer / separator pool to elevation 114'-0" corresponds to approximately 350,000 gallons of water and will provide core cooling capability in the event leakage from the control rod drive does occur. A potential draining of the reactor vessel (via control rod blade leakage) would allow this water to enter into the torus and after approximately 140,000 gallons have accumulated (needed to meet minimum NPSli requirements for the LPCI and/or core spray pumps), the torus would be able to serve as a common suction header. This would allow a -

closed loop oaeration of the LPCI system and the core spray system (once re-aligned) to tie torus. In addition, the other core spray system is lined up '

to the condensate storage tanks which can supplement the refuel cavity and dryer / separator pool water to provide core flooding, if required.

l Specification 3.9 must also be consulted to determine other requirements for l the diesel generators.

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Amendment No. 120 l

MSU:

i 4.5 Core Coolina Syttems Surveillance Freauencies The testing interval for the co: e cooling systems is based on industry practice, quantitative reliability analysis, judgment and practicality. The core cooling systems have not been; designed to be fully _ testable during operation. For example, in the case of the HPCI, automatic initiation during power operation would result in pumping cold water into the reactor vessel which is not desirable. Complete ADS testing during power operation causes an undesirable loss-of-coolant inventory. To increase the availability of the l core cooling systems, the components which make up the system; i.e., i instrumentation, pumps, valves, etc., are tested frequently. The pumps and motor operated injection valves are niso tested each month to assure their operability. A simulated automatic actuation test once each cycle combined with monthly tests of the pumps and injection valves is deemed to be adequate testing of these systems.

The surveillance requirements provide adequate assurance that the subject cooling systems will be operable when required.

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l Amendment No. 135 122

i l LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7 CONTAINHENT SY1TEi$ (Con't) 4.7 CONTAINHENT SYSTEMS (Cont'd)

1. If the specifications of Item 1, above, cannot be met, and the differential pressure cannot be restored within the subsequent (6) hour period, an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition in twenty-four (24) hours, a

m. Suppression chamber water level shall be maintained between -6 to -3 inches on torus level instrument which corresponds to a downcomer submergence of 3.00 and 3.25 feet respectively.

n. i;e suppression chamber can be drained if the conditions l 3

specified in Section 3.5.G.4 l of this Technical Specification are adhered to,

o. With irradiated fuel in the I h. Containment Cooling System l vessel and reactor coolant I (Drywell Spray, Toru= Spray i greater than 212*F there shall l and Suppression Chamber i be two operable loops of I Cooling) testing shall be as l 1 Drywell Spray and Torus Spray. I follows: l Hith one loop inoperable, I restore the inoperable loop l ltem Freauency I within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in the  ; 1 Cold Condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. I 1. Pump & Valve Once/3 months I t With both loops inoperable, i Operability I restore one loop in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or l l be in the Cold Condition within i 2. Pump Capacity After pump l 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. I Test. Each maintenance l I RBCCH pump and every 3 1

p. With irradiated fuel in the i shall deliver months l vessel and reactor coolant l 1700 gpm I greater than 212*F there shall I at 70 ft. TDH. l be two locps of Suppression i Each SSHS I Chamber Cooling. With one l pump s'nall I inoperable loop, restore the I deliver 2700 I inoperable loop within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> I gpm at 55 i or be in the Cold Condition in I ft. TDH. I 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. With both loops I inoperable, restore one loop in i 3. Air test the Once/5. years 1 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in the Cold I drywell and l Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. I torus headers I and nozzles. t

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Amendment No. 17, 173 154

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[fMTTING CONDITIONS FOR OPERATION S11RVEILLANCE REOUIREMENTS 3.7.B Standby Gas Treatment System and 4.7.B Standby Gas Treatment System and Control RoonLHith Efficiency Air Control Room Hiah Efficiency Air Filtration System Filtration System I 1. Standby Gas Treatment System 1. Standby Gas Treatment System

a. Except as specified in a. (1.) At least once every 18 i

3.7.B.1.c below, beth months, it shall be trains of the standby gas demonstrated that pre >sure treatment system shall be I drop across the combined i

operable at all times when high efficiency filters and secondary containment charcoal adsorber banks is integrity is required or less than 8 inches of water the reactor shall be at 4000 cfm.

shutdown in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

! When the reactor is in the I (2.) At least once every 18

Cold Condition and I months, demonstrate that i Subcritical. electric l the inlet heaters on each train are operable and are i support requirements are I i as specified in 3.9.C. I capable of an output of at i least 14 kH.

l b. (1.) The results of the in-place cold 00P tests on (3.) The tests and analysis of HEPA filters shall show Speci fication 3.7.B.1.b.

' 299% DOP removal. The shall be performed at least esults of halogenated once every 18 months or ydrocarbon tests on following painting, fire or harcoal adsorber banks chemical release in any

.h:11 show 199% ventilation zone ialogenated hydrocarbon communicating with the

! removal. system while the system is operating that could (z.) The results of the contaminate.the HEPA

laboratory carbon sample filters or charcoal

analysis shall show 1951 adsorbers, methyl iodide removal at a velocity within 10% of (4.) At least once every 18 systgm design, 0.5 to 1.5 months, automatic mg/m3 inlet methyl iodide initiation of each branch

concentration, 170% R.H. of the standby gas and 1190*F. treatment system shall be demonstrated, with The analysis results are to Specification 3.7.B.l.d be verified as acceptable satisfied.

within 31 days after sample

removal, or daclare that (5.) Each train of the standby train inoperable and take the gas treatment system shall actions specified 3.7.8.1.c. be operated for at least 15 minutes per month,

c. From and after the date that one train of the (6.)-The tests and analysis of -

Standby Gas. Treatment Specification 3.7.B.I .b.(2)

System is made or found to shall be performed after be iaoperable for any every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system reason, continued reactor operation.

operation, irradiated fuel handling, or new fuel Amendment No. 50, 51, 52, 112 158

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

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REGUIREMENTS 3.7.8 (Continued) 4.7.B (Continued) handling over the spent fuel I b. (1.) In-place cold DOP testing pool or core is permissible shall be performed on the only during the succeeding HEPA filters after each seven days providing that the l completed or partial other Standby Gas Treatment I replacement of the HEPA train is operable. l filter bank and after any structural maintenance on

d. Fans shall operate within the HEPA filter system 110% of 4000 cfm. housing which could affect the HEPA filter bank

e. Except as specified in bypass leakage.

3.7.8.1.c, both trains of the Standby Gas Treatment (2.) Halogenated hydrocarbon System shall be operable testing shall be performed during irradiated fuel on the charcoal adsorber handling, or new fuel bank af'ter each partial or handling over the spent complete replacement of fuel pool or core. If the the charcoal adsorber bank system is not operable, or after any structural fuel movement shall not be maintenance on the started. Any fuel charcoal adsorber housing assembly movement in which could affect the progress may be completed, charcoal adsorber bank bypass leakage.

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Amendment No. 50, 51, IJ2 158A

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i i LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS i

! 3.7.8 (Continued) 4.7.B (Continued) l 2. Control Room Hiah Efficiency Air 2 .- Control Room Hiah Efficiency Air Filtration System Filtration System

! a. Except as specified in a. At least'once every 18 months the Specification 3.7.B.2.c below, pressure drop across each combined both trains of the Control Room filter train shall be' demonstrated

High Efficiency Air Filtration to be less than 6 inches of water at-System used for the processing 1000 cfm or the calculated i of inlet air to the control room equivalent.

under. accident conditions shall l be operable whenever secondary b. (1.) The tests and analysis of

. containment integrity is Specification 3.7.B.2.b-shall

' required. When in the Cold I be performed once every 18 Condition and Subtritical, I months or following painting, j- electric support-requirements i fire or_ chemical release in i are as specified in 3.9.C. I any ventilation zone

communicating with the system

b. (1.) The results of the while the-system is_ operating, j in-place cold D0P-tests on l HEPA filters shall show -(2.) In-place cold 00P testing:

l 199% 00P removal. _The shall-be performed after each j results of the halogenated complete or partial

. hydrocarbon tests on replacement.of the HEPA filter-charcoal adsorber banks bank or after-any structural i shall show 199% maintenance'on the system

, halogenated hydroca-bon housing which coult affect the

[ removal when test results HEPA' filter bank bypass

are extrapolated to the leakage, j- initiation of the-test.

l (3.) Halogenated hydrocarbon (2.) The results of the testing shall-be. performed

{ laboratory carbon sample after each complete or partial i i analysis shall show-195% ' replacement of the charcoal

methyl iodide removal at a -adsorcer-bank or after any velocity within-10% of structural maintenance

on the

l. system design, 0.05 to system housing which could 0.15 mg/m 3 -inlet methyl j affect the charcoal adsorber iodide concentration. 170% bank bypass leakage.-

4 R.H., and 1125'F. The

analysis-results are to be (4.)~ Each trainishall be_ operated

! verified as acceptable- -with the heaters in automatic

[ within.'31 days after sample removal, or. declare

'for at.least-15' minutes _every-month.

i that' train inoperabl_e and i take.the actions.specified (5.) The test and analysis of-

-in 3.7 B.2.c. Specification.3.7.B.2.b.(2)

~

, shall be' performed after every

{ 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation.

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j Amendment No. 50, 57, 52, 101, 112

=1588 i

.,s---- a... ,. u. - ...,..-- , - , . , _ . , ~ .z,- - - ,

LJMITING CCNDITIONS FOR OPERATIQN SURVEILLANCE REQUIREMENTS 3.7.B (Continued) 4.7.B (Continued)

c. From and after the date that c. At least once every 18 one train of the Control Room months demonstrate that the High Efficiency Air inlet heaters on each train Filtration System is made or are operable and capable of found to be incapable of an output of at least 14 kw.

supplying filtered air to the control room for any reason, d. Perform an instrument reactor operation or functional test on the refueling operations are humidistats controlling the permissible only during the heaters once per 18 months.

succeeding 7 days providing l the other CRHEAF train is I operable. If the system is l not made fully operable within 7 days, relctor shutdown shall be initiated and the reactor shall be in cold shutdown within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and irradiated fuel handling operations shall be terminated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Fuel handling operations in progress may be completed.

d. Fans shall operate within 210% of 1000 cfm.

4 Amendment No. 50, 51, 57, 172 158C

LIMITING CONDITf0NS FOR OPERATION SURVEILLANCE REOUIRLHENTS 3.7.C SEQadary ContainmEtt 4.7.C Secondary Containment

1. Secondary containment integrity 1. Secondary containment surveillance shall be maintained during all shall be performed as indicated modes of plant operation except below:

when all of the following conditions are met. a. A preoperational secondary containment capability test shall

a. The reactor is subtritical be conducted after isolating the and Specification 3.3.A is reactor building and placing either met, standby gas treatment system filter train in operation. Such tests

b. The reactor water shall demonstrate the capability to temperature is below 212*F maintain 1/4 inch of water vacuum and the reactor coolant under calm wind (<5 mph) conditions system is vcnted, with a filter train flow rate of not more th- 100 cfm.

c. No activity is being performed which can reduce b. (DELETED) I the shutdown margin below that specified in c. Secondary containment capability to Specification 3.3.A. inaintain 1/4 inch of water vacuum under calm wind (< 5 mph) conditions

d. The fuel cask or with a filter train flow rate of irradiated fuel is not not more than 4000 cfm, shall be being moved in the reactor demonstrated at each refueling building. outage prior to refueling.

e. No core alterations are l being performed with fuel l in the vessel. 1 I

f. No operations with a i potential to drain the i reactor vessel are in i progress with fuel in the i vessel. I

2. If Specification 3.7.C.1 cannot be met, procedures shall be initiated to establish conditions listed in Specification 3.7.C.l.a through

f. I 159

i BASES:

3.7.A & 4.7.A Primary Containment Experimental data indicates that excessive steam condensing loads can be avoided if the peak local temperature of the pressure suppression pool is

maintained below 200 F during any period of relief-valve operation with sonic conditions at the discharge exit. Analysis has been performed to verify that the local pool temperature will stay below 200"F and the bulk temperature will '

stay below 160 F for all SRV transients. Specifications have been placed on the envelope of reactor operating conditions so that the reactor can be i depressurized in a timely manner to avoid the regime of potentially high pressure suppression chamber loadings.

! In addition to the limits on temperature of the suppression chamber pool j water, operating procedures define the action to be taken in the event a i relief valve inadvertently opens or sticks open. This action would include:

! (1) use of all available means to close the valve, (2) initiate suppression l pool water cooling heat exchangers, (3) initiate reactor shutdown, and (4) if other relief valves are used to depressurize the reactor, their discharge

! shall be separated from that of the stuck-open relief valve to assure mixing and uniformity of energy insertion to the pool.

, Because of the large volume and thermal capacity of the suppression pool, the volume and temperature normally changes very slowly and monitoring these

parameters daily is sufficient to establish any temperature trends. By requiring the suppression pool temperature to be continually monitored and

! frequently logged during periods of significant heat addition, the temperature trends will be closely followed so that appropriate action can be taken. The

,2 requirement for an external visual examination following any event where potentially high loadings could occur provides assurance that no significant damage was encountered. Particular attention should be fonsed on structural discontinuities in the vicinity of the relief valve discharge since these are 4

expected to be the points of highest stress.

if a loss-of-coolant accident were to occur when the reactor water temperature

is below approximately 330 F, the containment pressure will not exceed the j 62psig code permissible pressure, even if no condensation were. to-occur. The maximum allowable pool temperature, whenever the reactoris above-212 F, shall i be governed by this specification. Thus, specifying water volume-temperature i

requirements applicable for reactor-water temgerature above 212 F provides additional margin above that available at 330 F.

3.7.A. Containmein Coolina System-Orywell _S_prav. Torus Sorav. Suonression Chamber Cooling The containment cooling system for Pilgrim I consists of two independent loops each of which to be an-operable loop requires one LPCI pump, two RBCCW pumps and two SSW pumps. There are installed spares for margin above the design conditions. Eacgsystemhasthecapabilitytoperformitsfunction;i.e., -

removing 64 x 10 Btu /hr (Ref. Amendment 18), even with some system degradation. If one loop is out-of-service, . reactor operation is- permitted for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Amendment No. 83, 113 166

BASES:

I l j 3.7.A. Containment Coolina System (Cont'd)

With components or systems out-of-service, overall containment cooling i reliability is maintained by the operability of the remaining cooling i equipment, j

j- Since some of'the SSW and RBCCW pumps. associated with the Containment Cooling System are required for normal operation, capacity testing of individual pumps by direct flow measurement is impractical. The pump capacity test is a

. comparison of measured pump performance parameters to shop performance tests

combined with a comparison to the performance of. the previously tested pump.

i These pumps are rotated during operation and performance testing will be i integrated with this or performed during refueling when pumps can be flow l tested individually. Tests-during normal operation will be performed by

. measuring the shutoff head. Then the pump under test will be placed in i service and one of the previously operating pumps secured. Total flow j indication for the system will be compared for the two cases. Where this is not feasible due to changing system conditions, the pump discharge pressure

! will be measured and its power requirement will De used to establish flow at that pressure.

a l The Drywell Spray, Torus Spray and Suppression Chamber Cooling systems are i necessary during power operations. Specificaticn 3.7 imposes Surveillances

! and Limiting Condition: for Operation to ensure 'he operability of the equipment. When the equipment is inoperable the plant is brought to a

. condition where the equipments is not necessary.

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Amendment No. 83, 113- 166A l I

. ._ .- ~. .

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

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BASES:

3.7.B.1 an_d 4.7.8.1 (continued) 4 The test frequencies are adequate to detect equipment deterioration prior to significant defects, but the tests are not frequcnt enough to load the filters or adsorbers,- thus reducing their reserve capacity too quickly. The filter testing is performed pursuant to appropriate procedures reviewed and approved 4

by the Operations Review Committee pursuant to Section 6 of these Technical Specifications. The in-place testing.of charcoal filters is performed by i injecting a halogenated hydrocarbon into the system upstream of the charcoal

adsorbers. Measurements of the concentration upstream and downstream are i made. The ratio of the inlet -and outlet concentrations gives an overall

indication of the leak tightness of the system. A similar procedure i substituting dioctyl phthalate for halogenated hydrocarbon is used to test the HEPA filters.

Pressure drop tests across filter and adsorber banks are performed to detect

plugging or leak paths though the filter or adsorber media. Considering the 1 relatively short-times the fans will be run for test purposes, plugging _is unlikely and the test interval of once per 18 months is reasonable.

System drains and housing gasket doors are designed such.that any leakage would be inleakage from the Standby Gas Treatment System Room. This ensures that there will be no bypass of process air around the filters or adsorbers.

Only one of the two Standby Gas Treatment Systems (SBGTS) is needed to a

maintain the secondary containment at a 0.25 inch of water negative pressure upon containment isolation, if one system is made or found to be inoperable, j there is no immediate threat to the containment system performance and reactor

, operation or refueling activities may continue for seven days while repairs.

are being made to the inoperable system. .The other system must be operable.

If both trains of SBGTS are inoperable, the plant is brought to a condition where the SBGTS is not required.

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Amendment No. 42,-112 173 l

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

BASES:

3.7.B.2. and 4.7.B.2. (continued)

Air flow through the filters and charcoal adsorbers for 15 minutes each month i assures operability of the system. Since the system heaters are automatically controlled, the air flowing through the filters and adsorbers will be 570%

relative humidity and will have the desired drying effect.

If one train of the system is found to be inoperable, there is no immediate threat to the control room, and reactor operation or fuel handling may continue for seven days while repairs to the ir. operable train are being made.

The other train must be operable. If both trains of the CRHEAF system are

~

e inoperable, the reactor will be brought to a condition where the Control Room High Efficiency Air Filtration System is not required.

1 i

4 4

4 4

l Amendment No. 42,-112 174A 1

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

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LIB 111NG CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.C Diesel Generator Reauirements- l Cold Condition and Suberitical !

I

1. When the reactor is in the l

. Cold Condition and Subtritical l there shall be one offsite l

power source capable of l energizing the emergency buses t ,

- and either Emergency Diesel l Generator operable. I

I 4

2. When the reactor is in the l Cold Condition and Subtritical l l if a train or loop of a l l required system is inoperable, I the Emergency Diesel Generator l associated with the operable l train or loop must be operable.l

3. Hith no offsite power supplies I operable and/or both Emergency l Diesel Generators inoperable. l suspend core alterations, l

handling of irradiated fuel in l the secondary containment, and l l operations with a potential I for draining the vessel. [

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l t-Amendment No. 197A

BASES:

3.9.C Qiesel Generator Reouirements - Cold Condition and Suberitical i The operability of A.C. power sources when in shutdown and refuel conditions -

j assures: (1) adequate coolant inventory for the irradiated fuel in the core t in case of an inadvertent draindown of the vessel; (2) mitigation of a fuel bundle handling accident; (3) sufficient power for required support systems (e.g., decay heat removal, refueling activities, component cooling); and (4) j sufficient instrumentation and control capability for monitoring and maintaining the unit status.

4 It is unnecessary to require the sources of emergency power to be completely redundant. Specificatior. 3.9.C.1 considers emergency electrical power bus requirements met with offsite power and one emergency diesel generator operable. The remaining bus is considered opercble with just a source of

, offsite power available, i

This specification impacts other safety functions which electric pcNer supports. Each of these safety functions has been evaluated previously, and-it was concluded that the power. requirements of Specification 3.9 C.1 support the other safety functions such that shutdown risk is acceptably low.

l This specification precludes the potential for having unacceptable

combinations of system alignments, and enhances safety by. eliminating the potential for misinterpreting .3.9.C.I.

Specification 3.9 C.3 requires the suspension of core alterations, the handling of irradiated fuel in the secondary containment and operations with a potential to drain the vessel when no sources of offsite and/or emergency

power is available.

l Thus, operations which have the ootential to result in an event requiring the

operation of a safety system, such as SGTS, must be suspended if both

! emergency buses are supplied by only one source of power. -This reduces the

probability of an adverse event and maintains the reactor in a safe. condition while additional sources of power are restored.

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4

Amendment No. 199A i

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. Attachment C to BEco Letter 92-l i

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F

+

4 4

4

1ABLE OF CONTENTS Paae No1 1.0 DEFINITIONS 1 2.0 SAFETY LIMITS 2.1 Safety Limits 6 2.2 Safety Limit Violation 6 Limiting _ Conditions For Oceratior Surveillance Reauirement 3.1 REACTOR PROTECTION SYSTEM 4.1 26 3.2 PROTECTIVE INSTRUMENTATION 4.2 42 3.3 REACTIVITY CONTROL 4.3 80 A. Reactivity Limitations A 80 B. Control Rods B 81

. C. Scram Insertion Times C 83

! D. Control Rod Accumulators D 84 5

E. Reactivity Anomalies E 85 F. Alternate Requirements 85 i G. Scram Discharge Volume G 85 I 3.4 STANDBY LIQUID CONTROL SYSTEM 4.4 95

~

A. Normal System Availability A 95 B. Operation with Inoperable Components B 96 C. Sodium Pentaborate Solution C 97

, D. Alternate Requirements 97

~

3.5 CORE 00 LING SYSTEMS 4.5 103

= A. Core Spray and-L_PCI Subsystems A / sunov)O coown& sisTeAct

- 103 B.(@TriifmenFC5 ing-SuhysTejm B 106

- C. HPMubsyslem C 107 i _

D. RCIC Subsystem D '108 l E. Automatic DepressurizaMon System E 109 i F. H!nimum Low Pressure Cooling System. F 110 and Diesel Generator Availability a fmb69TedT) ofCscS filled.sH5rznuo Dischargeete Ruums G i

G.Dintenance H. Pipe H @ "h 111-I -

3.6 PRIMARY SYSTEM BOUNDARY 4.6 123-A. Thermal and Pressurization Limitations A 123

. B. Coolant Chemistry B 124 C. Coolant Leakage C 125

' D. Safety and Relief Valves D 126 E. Jet Pumps E 127-F. Jet Pump Flow Hismatch F. 127a .

G. Structural-Integrity G 127a l H. Deleted H l I. Shock Suppressors (Snubbers) I 137a -

ND~i Amen m'ent No. 75, 45, 65, 733, i i

.__-..._-m- - , _ . , ,. .- - , , _ . _ _ . . . .

Surveillang Paae No.

3.7 CONTAINMENT SYSTEMS 4.7 152  ;

A. Primary Containment A 152 B. Standby Gas Treatment System and B 158 Control Room High Efficiency *

/

Air Filtration System C. Secondary Containment C 159 3.8 RADIDACTIVE EFFLUENTS 4.8 177 A. Liquid Effluents Concentration A 177 B. Radioattive Liquid Effluent B 177 Instrumentation C. Liquid Radwaste Treatment C 178 D. Gaseous Effluents Dose Rate D 179 E. Radioactive Gaseous Effluent E 160 Instrumentation ^

F. - Gaseous Effluent Treatment F 181 G. Main Condenser G 182 H. Mechanical Vacuum Pump H 183 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 194 A. Auxiliary Eiertrical_ Equipment A 194

" B. Operation with Inoperable Equipment C. TICsEA. GE#)rM70R, REAdi%ud75- N '#^fD'MO '*'dO 196 I9'? A h .

l_ 3.10 CO9E ALTERATION 5 i.10 S M G'^-202 .

! A. Refueling Interlocks A 202 B. Core Monitoring B 202

C. Spent fuel Pool Water Level C 203

, D. Multiple Control Rod Removal D 203 4.11 205a 3.11 REACTOR FUEL ASSEMBLY l1 4. Average Planar Linear Heat A 205a -

Generation Rate (APLHGR) /

[ Linear Heat Generation Rate (LHGR)- 205b-i b. B C. Minimum Critical Power Ratio (MCPR) C 205b. ',

l D. Power /Flo' Relationship D 205d '

j l 3.I' FIRE PROTECTION 4.12 206--

i A. Fire Detection Instrumentation A 206 -- .

B. Fire Water Supply System B 206a C. _ Spray and/or Sprinkler Systems- C 206c

-0 206d

! D. Halon System

. E. Fire Hose Stations E 206e g i F. Fire Barrier System :F 206e-1 G. Alternate Shutdown Panels- G

-206e-l[/__

m, m ANndsnc40' If,27,4E,2J,29.II2,II4,h ii

U_HITING CONDITION FOR OPERATION SURVEILLANCE REOUIREMENT 3.5 Q Rf,_ @ ! M C '

Q U ![G 4.5 CORE CD-C N B Hf b COOLING SY3JpiS SYSTE C #

6pp_lhability Apolicability Applies to thg operational status of Applies to the Surveillan the core @ M ]4 cooling Requirements of the core ew}

systems. (Tuppr-ess4on--polo ccoling systems which '

afe Tsiiilfred when the corresponding Limiting Condition for operation is in effect.

q Qhiective Obiective

To assure the operability of the core To verify the o erability of the core ed-huppr4s44en--pee cooling systems

$ @uilder alTToTditions for which thisii @ un @ efgall g cooling systems coridit ons for which this cooling capability is an essential

~

cooling capability is an essential response to station abnormalities. response to station abnormalities.

Speci fication Soecification hA.

y Core Sorav and LPCI Systems A. Core Ser.ity and LPCI Systems ks, 1. Both core spray systems shall be C/ operable whenever irradiated fuel 1. Core Spray System Testing.

is in the vessel ard pr.ur -

T c4 Nor--.up from > Col 4- J t.em Frecuency CondFt4ettr-+Ecpt u speci fi ed in-

_ -- e a. Simulated Once/ Operating

. 5. s-A . 2 bt4eml=

Automatic Cycle Actuation test.

w Hap lM f ki .O b. Pump Operability Once/ month

? 2 U k 15 N /, 3,5'C., Z- c. Motor Operated Once/ month 3,f.fr.3) d '3.f(,,e/ A g; , Valve Operability

d. Pump flow rate Each pump shall Once/3 months h

deliver-at least

'3300 gpm against a system head corresponding to a reactor vessel pressure cf 10^ psig,

e. Core Spray Header op Instrumentation Amendment-No. 42, 62, Ild, -

103-

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Qi[ TING CONDITION FOR OPERATION SURVEILLANCE REOUIREMENT kh3.5.A Core Sorav and LPCI SyltJmi 4.5.A Core Sorav and LPCI Systems /

v (cont'd) (cont'd)

Check Once/ day- )

Calibrate Once/3 months Test Step Once/3 months

2. From and after the date that one 2. This section intentionally left I

1. ) of the core spray systems is made blank > /

k9 or found to be inoperable for any b reason, continued reactor 3. LPCI system Testing shall be'as . /

operation is permissible during follows: M the succeeding seven days, provided that during such seven a. Simulated Once/ Operating days all active components of the Automatic Cycle other core spray system and active Actuation

./ components of the LPCI system and Test the diesel generators are operable.

b. Pump Once/ month

3. The LPCI system shall be operable Operability whenever irradiated _ fuel is in the reactor vesselfr-an4-pM7w-4e c. Motor Operated Once/ Month frR*a -tor-staIJup_ fror a C01d J Valye L_ exc Q specified in operability

3. .A. ..- .-.F. 3.f. G l,1.f.G.E .

.) 3. f. .3 . 4, d. Pump Flow Once/3 months

)4. From and after the date that the LPCI system is made or found to be Each LPCI pump shall pt'mp 4800 inoperable for any reason, gpm at a head across the pump

< continued reactor operation is of at least 380 f t.

permissible only during the succeeding seven days unless it is sooner made operable, provided that during such seven days the containment cooling system (including 2 LPCI pumps) and

' ~~

active components of both core

) $ spray systems, and the diesel generatorfRITiMTTor cper-aMs i M-suth c'=ponents i f no-ntemat I worse-of-pow" were an44able-operable.

(h nw g 5. If the requirements of 3.5.A cannot be met, an orderly shutdown of the reactor shall .be initiated and the reactor shall be in the Cold Shutdown' Conaition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

w ,

4ev44en-44$

mEhament No. 42,- (2,-117 Ild, [ l_04

1 .

oved, t3 f4- IfMp %

j & d ,, c4 4 7. 4.1. h. - - -

LIMITING CONDITION FOR OPERATION SURVEILLANCE REOUIREMENT SnoTbn.M slioTVod 2

h3.5.B J

Coolina System (IG#}t.5.8 O(t_ inyt;Coolina System (RgR , ,

1

-- ~~m s+rrnm0 '

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btent-as-+ pee 4-fi ed i n 3. 5. B. 2 \ 1. cat & T.:nf., Cooling system l p,, 1. {and-3. 5. r . 3 bel ow, both- I Testing shall be as follows V/

+ont444 ment cocHng ty&44n loop t l

sh:11 be operable

• navar- t freauency 4r44diated f el U . i a: i n the reartof f - -

i vetteband-reaeter--EGGlant- / a. Pump t. Valye Once/3 months .

-teaterature is great +r-than f Operability l NFf r-aM-pr4cr to reactor N J

b. Pump Capacity

+tetup-f+om+C+1d Cond444en]

_-w l

i Test Each RBCCW After pump maintenance K

, i

2. [ftest--end e f te r - t he da t e that ene-m' pump shall and every 3

a+ntainment cccling ;y; tem iccp '

deliver 1700 gpm months.

! i+-made or found te be i noperaMe. at 70 ft. T04. '

j Iforanyrease, cont +ncedreacter Each SSHS pump

3 eper+t4en 1; permis;ible only shall deliver 2700

- 4ur4ag-the-Succeeding 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s- .gpm at 55 ft. TOH.

unicss such system loop i; sooner - -- -~ --- _

j made Operabic, provided that ne c. Air test on Once/5 years 4

other-contalnasat-toe 1ing :y: ten- drywell and

iccp, incinding it;-as

Oc!:ted- torus headers

dic;c! generator, i

Operab!c. and nozzles

! 3. H -the-rcquirement; cf 3.5.B Freauency eannot be m.ct, an crderly It

thetha shm be i itiated ;M Once/31 days Shutdown Cooling ,

i the-r+ aster ch:11 be i C0ld-i htjoun Condi-t4eF{ rithi" 24 "){

y M L 4 C7 i

, When in the Hot Shutdown $N'['_5ID'.L p ' a lj y ' @ p u g

• j-i g condition and not m.in rondenser, tw hutdown aming to the ~ q.g.,t -

kg

[

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Cooling Loops (SDC) shall be operable. If the requirements of MNM W With the reactor M M ffa .+cm/ h Dc. -

3.5.B.1 cannot be met _immediately initiate corrective action to head the fuelremoved, pool gatesthe cavity-removed andflooded, M o

return the required loop to \

water level maintained to at  %

operable status as soon as least elevation 114'0", at least

lpossible and be in Cold-Shutdown one Shutdown Cooling loop shall-74t 0; i in 2.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. 4 be operable, If the requirements l

'  % of 3.5.8.3 cannot be met When irradiated fuel is ir the immediately-suspend all vessel and the reactor is in the operations involving an increase Cold Condition, twotSDC loops in the reactor decay heat-load, shall be-operable and and close all secondary _

specification 3.9 C shall be containment penetrations met. If the requirements of providing direct access from

[r,4 3.5.B.2 cannot be met immediately secondary containment atmosphere 1

initiate corrective action to to the outside atmosphere within h return the required loop to operable status as soon as 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

etC~ ,, i

• tb:0 : 6~ 4 S: t .f.m,.p o g k acamrt n, u. m,@... W "- 20s e 6 % & w% W ~e np.

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l LIMITING CONDITION FOR OPERATION SURVEILLANCE REOUIREMENT 3.5.F Minimum Low Prassure_fpp_ lina ana 4.5 F Hinimum low Pressure Cooling Diesel Generator Availabil(ty and Diesel Generator Availability

1. When it is determined thct one

. 1. During any period when one diesel diesel generator is inoperable, th i

. generator is inoperable, operable diesel generator shall be continued reactor operation is demonstrated to be operable 3 n s permissible only during the immediately and daily thereafter succeeding . hours unless such until the inoperable diesel is diesel generator is sooner made repaired.

operable, provided that all of

, the low pressure core and ,

containment enoling systems and the remaining diesel generator shall be operable. If this

! requirement cannot be met, an orderly shutdown shall be initiated and the reactor shall be placed in the Cold Shutdown

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

2. Any tombination of inoperable components in the core and containment cooling systems shall not defeat the capability of the

! remaining operable components to

fulfill the cooling functions, t _

~~~~

-Hhen-4 er a d i a t ed-fueMs--in-t he+e-a c4or-ve s s 41-and-the4ea st or-4s-4 n /MS6[2 ~l -r /asce~,.1

-the-Cold--Shutdown-<ondRionr -both- 4 f, 4

-core-s p ray-sys t emh--t he-4:PGI-and- 3 6 b.

containment--cool 4ng-systeas-aay-be 4noperablegov4ded-no-verk is beFng-4one-whteh-has-the-potent 44! for drain 4ng-the-reac-tor-Venel, - - - -

. Dartag-awefue44ag-eutage-feea y-per4cd of 30 day &r-r-efus44ng-oper- g at40u ny continue provided that-one core spray-system-or-the4PGI-r- +ys-tem is operable cr--

Speel4kat4on-M. F . 5 i s m^ t .

~

. When irradiated fuel is in the j reactor vessel and the reactor is

/ in the Refueling Condition with 3.6.Gf[ the torus drained, a single gg control rod drive mechanism may be removed, if both of the 999 following conditions are satisfied:

W 1.*

Visic" Amen IT. H,h 110

& yge & Db f*6L IIO i

i 4

3.5.G CSCS-Shutdown and Refuelina 4,5.G CSCS-Shutdown /Refuelina 1

i

1. When irradiated fuel is in the 1. Surveillance requirements are the vessel and the reactor is in the same as 4.5.A.

Cold Condition, except as specified in 3.5.G.2, 3.5.G.3 and 3.5.G.4 below, a combination of 2 low pressurc CSCS subsystems shall be operable and i

specification 3.9.C shall be met.

2. a. With only one low pressure CSCS system available, restore the second system in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or suspend operations that have a potential for draining the vessel.

b. With no systems available immediately suspend tore alterations and activities with the potential to drain the vessel. Restore one system.in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or establish secondary containment within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

l

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1 .

LIMITING CONDITION FOR OPERATION SURVEILLANCE REOUIREMENT .

i

[3$.binhc5 I +-0004 OlesM-enerator-AvM31td+H+ /

a) No work on the reactor ves-sel in addition to CR0 re- ..

fh hs h p e for dmq exceedgngthemaximum leak rate from a single gg,fg,b g pt control blade seal if it m became unseated. fgg l)d m /

b) i) the coie spray systems \ 3.

are operable and aligned When irradiated fuel is in the 3

> with a suction path from G ([1 vessel during Refueling, with the reactor head removed, the cavity the condensate storage flooded, the fuel pool gates tanks. ii) the condensate removed and water level storage tanks shall contain a+ least 200,000 gallons of maintained to at least elevation

! 114'0", all low pressure CSCS

usable water and the subsystems may be inoperable.

, refueling cavity and dryer /

l separator flooded to(j}po,)o1 least shall be j elevation 114'-0" ~G' s le f4-b l- 3.5,H ikintenance of Filled Discharae 4.5.H Haintenance af Filled Discharae Elst P_i_92

[7 Whenever core spray systems, LPCI The following surveillance requirements system, HPCI or RCIC are required to shall be adhered to to assure that the

/ be operable, the discharge piping from discharge piping of the core spray

- J the pump discharge of these systems to systems, LPCI system, HPCI and RCIC are the last block valve shall be filled. filled:

~

1.

hi b . -

Every the LPCImonth systemprior to the and core spray systems, the discharge piping of 19 testing of()

these systems shall be vented from 9 b b> d .the high point ?nd water flow observed.

2. Following any period where the LPCI

& # g #u [.y- system or core spray systems have not been required to be operable, m e mG the discharge piping of the inoperable system shall be vented

@Y I I from the high point prior to the return of the system tc service.

SKAQ

' h . 29, @, 5) 111

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

] LIMITING CONDITION FOR OPERATION SURVEILLANCE REOUIREMENT

/ 4.5 H tiaintenance of Filled h) Y. [ /// M A 1 Discharoe Pioe (Cont'd) h "'<A 3. Whenever-the HPCI or RCIC system is lined up to take suction from uk,o NcW, jff i

the torus, the discharge piping of l the HPCI and RCIC shall be vented from the high point of the system i 3 b g' Y and water flow observed on a j mq monthly basis.

My g 4. The pressure switches which monitor the discharge lines to ensure that they are full shall be l

j @ ' j functionally tested every month and calibrated every three months.

i i

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'll Amen @ent No. 39, 112 l

3/ M 8 ILASIS/:,-

/ 5HoTBoW4 '

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.5.

LEentehenB Cooli na Sys teni(R.M R.) /

-' r'~

- -~~~e -m / ,

. The containment cooling system for Pilgrim I consists of two independent loops J each of which to be an operable loop requires one LPCI pump, two RBCCH pumps, and two SSH pumps to be operable. There are installed spares for margin above the design conditions. Each sys function;i.e., removing 64x10gemhasthecapabilitytoperformits Btu /hr (Ref. Amendment 18), even with some '

/'

system degradation. If one loop is out-of-service, reactor operation is permitted for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. h Hith components or systems out-of-service, overall core and containment cooling reliability is maintainei by the operability of the remaining cooling- ,- j equipment.

Since some of the SSH and RBCCH pumps are required for normal operation, capacity testing of individual pumps by direct flow measurement is

'U impractical. The pump capacity test is a comparison of measured pump \

performance parameters to shop performance tests combined with a comparison to the performance of the previously tested pump. These pumps are rotated during operation and performance testing will be integrated with this or performed during refueling when pumps can be flow tested individually. Tests during normal operation will be performed by measuring the shutoff head. Then the pump under test will be placed in service and one of the previously operating pumps secured. Total flow indication for the system will be compared for the two cases. Where this is not feasible due to changing system conditions', the g pump discharge pressure will be measured and its power requirement will be I

(w used to establish flow at that pressure.

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MSES: j y .pJ 3/4.58- Shutdown Coolina System (RHR) t{ 44p fegg Maintaining decay heat removal (DHR) capability is a key function during shutdown conditions. During normal refueling outage conditions, the shutdown cooling (SDC) mode of the RHR system and its supporting systems are the primary means of removing decay heat when fuel is in the reactor vessel. An extended loss of the DHR function can lead to coolant boiling and potentially result in a depletion of reactor coolant and eventual uncovering of the core.

While irradiated fuel remains in the reactor vessel during an outage, maintaining the DHR function is important to shutdown safety.

When the Main Steam Isolation Valves (MSIV) or the MSIV drains are open and vessel temperture is at or above 212 F, 3.5.B.1 does not apply because the plant is in Hot Shutdown but is steaming to the main condenser.

Two RHR shutdown cooling subsystems are required to be OPERABLE. An OPERABLE

, RHR shutdown cooling subsystem consists of one OPERABLE RHR pump, one heat exchanger, and the associated piping and valves. The two subsystems have a common suction source and are allowed to have a common heat exchanger and common discharge piping. Thus, to meet the LCO, both pumps in one loop or one

, pump in each of the two loops must be OPERABLE. Since the piping and heat exchangers are passive components that are assumed not to fail, they are allowed to be common to both subsystems.

Additional'y, each shutdown cooling subsystem is considered OPERABLE if it can be manually aligned (remote or local) in the shutdown cooling mode for removal of decay heat. An RHR pump is OPERABLE when it is capable of being powered and able to provide flow if required.

The specification for two SDC loops in the cold condition includes the

condition that specification 3.9.C be met. Specification 3.9.C requires one offsite power source and either Emergency Diesel Generator operable when in the cold condition and subcritical.

Specification 3.5.B.3 allows refueling operations to continue with one-SDC loop operable with the reactor head removed, the cavity flooded, the fuel pool gates removed and water level maintained to at least elevation 114'0". This is acceptable because the large inventory of water acts as a diverse method of providing backup for the decay heat removal safety function. During refueling with irradiated fuel in the vessel, the reactor head removed and the cavity

, flooded the Augmented Fuel Pool Cooling loop satisfies the requirement to have one SDC loop operable once the decay heat load is within its capacity.

Activities that can increase decay heat load are the reduction of decay heat cooling or insertion of a fuel bundle. The requirement of 3.5.8.3-to close all secondary containment penetrations providing direct access to the outside atmosphere requires the isolation of secondary containment within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> if SDC is not operable.

i Amendment No. 115

_ . - _ _ . _ _ _ _ _ _ . . . . _ . . _ _ _ . __ m-.. . - _ _ . . . _ . . . . _ _ . . _ _ . _ _ . . __ _ . , _ _ _ . _ - --

l l; .

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3 1

i BASES:

j- 3.5.F Minimum Low Pressure Cooline and Diesel Generator Availability

. . _ wo

the purpose of Specification F is toyThat adequate core cooling equip-4 ment is available at all timesp lf, for example, one core spray were out of

- service anc Enc cinel which powered the opposite core spray were out of service, only 2 LCDI pumps would be availableMritts ciucling cutert+

%et---mapi ; ice c ir prTTwwe;-an+-etreing such @c ther-ai4-Icw pres- ~

! sure ec c cecl-inc ava ca: nav bc g .41_U g This speiiification prcvides

{

ttat should this occur, no work' will be performed on the primary system which could lead to draining the vessel. This work would include work on- certain control rod drive componencs and recirculation system. Specificatio Lal-l l lows remval sf one CRD tacchanism while the torus is in a drained condition h1

' without compromising core cooling ca; sbility. - The-available core cooling 7'Q j capability for a potential draining of the reactor vessel while this work g i - is perfomed is based on an eatimated drain rate of 300 gpm if the control rod

l. ~ [' ,

blade seal is unseated. Flooding the refuel cavity and- dryer / separator ~ .b[4k V ' pool to elevation 114'-0" corresponds to approximately 350,000' gallons of '

i - water and will provide core cooling capability in the event leakage from the control rod drive does occur. A potential draining of the reactor vessel M.-

(via control rod blade leakage) would allow this water to enter -into the

. torus and after approximately 140,000- gallons have accumulated (needed to 4-i meet minimum NPSli requirements for the LPCI and/or core spray pumps), the 3.f. G.

75'- torus would be able to serve as a common suction header. This-would al-

/ h low a closed loop operation of the LPCI system and the core spray system

/ { (once re-aligned) to the torus. In addition, the other core spray system i > is lined up to the condensate storage-tanks which can supplement the re-

. fuel cavity and dryer / separator pool water to provide core flooding, if -

b r equir ed.

! Q ~ Specification 3.9 must also be consulted to determine other requirements for

-the diesel generators.

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Con +inued operation is permissible for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> with one diesel generator out of service. In addition, all low pressure core and containment cooling systems and the remaining diesel generator must be operable. If these requircments are not met the reactor must be brought to the Cold Shutdown condition and low pressure cooling requirements provided in 3.5.G become j applicable.

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z.s.m This specification r y c3 that should ECCS .--cut of service, no we d will bc performed on the p;in~.y ;ysicm which c id leed tu ui a ni niu un: w s 3 e l ."

Streh work M uder verb an e n rh i n -c4nt r red dr";c component; and the recirculatien sy; tem. Specification' allows removal of one CR0 mechanism while the torus is in a drained condi ion without compromising core coolinge-capability. The available core cooling capability for a potential draining of the reactor vessel while this work is performed is based on an estimated drain rate of 300 gpm if the control rod blade seal is unseated. Flooding the I refuel cavity and dryer / separator pool to elevation 114'-0" corresponds to i approximately 350,000 gallons of water and will provide core cooling i capability in the event leakage from the control rod drive does occur. A

! potential draining of the reactor vessel (via control rod blade leakage) would l

allow this water to enter into the torus and af ter approximately 140,000 gallons have accumulated (needed to meet minimum NPSH requirements for the l

LPCI and/or core spray pumps), the torus would be able to serve as a common l

suction header. This would allow a closed loop operation of the LPCI system and the core spray system (once re W igned) to the-torus. In addition, the l other core spray system is lined up to the condensate storage tanks which can l

supplement the refuel cavity and dryer / separator pool water to provide core -

flooding, if required.

Specification 3.9 must also be consulted to determine other requirements for the diesel generators.

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

i 1 .

3.5.G CSCS - Shutdpwn and Refuelino

During Shutdown and Refueling conditions CSCS requirements are reduced.

l During Refueling, with the cavity flooded, increased coolant inventory provides sufficient time to make up lost inventory without relying on Low

~

i Pressure Cooling. Hence, with the cavity flooded the CSCS is allowed to be unavailable. '

l' i

i A minimum of two low pressure CSCS injection / spray subsystems are required to j_' be OPERABLE in Shutdown and Refueling. Two OPERABLE low pressure CSCS j subsystems :lso ensure adequate vessel inventory makeup in the event of an ,

! inadvertent vessel draindown. For Shutdown and Refueling conditions the low pressure CSCS injection / spray syst?m consists of two Core Spray (CS) subsystems and the Low Pressure Coolant injection (LPCI) system configured  ;

into two loops.

Each CS subsystem consists of one motor driven pump, piping, and valves to transfer water from the suppression pool or condensate storage tank (CST) to the reactor pressure vessel (RPV).

3.1 1 . Each LPCI loop consists of one motor driven nmp, piping, and valves to i -

trunsfer water frcm the suppression pool to .he RPV. Only a single LPCI pump

! , is required per loop because loop injection capacity for shutdown-and-refueling condittuns is less than for other operational modes. One LPCI loop

, may be aligned in the decay heat removal mode and be considered OPERABLE for j_j the CSCS function, if it can be manually realigned (remote or local)_ to the i ; LPCI mode and is not otherwise inoperable. Because of low pressure and low 4 .' temperature conditions in Shutdown and Refueling sufficient time will be l . available to manually align and initiate LPCI operation to provide core jq cooling prior to postulated fuel uncovery, t .

!j CSCS is not required during refueling when the spent fuel storage pool gate is  :

i ; removed and the water level is maintained at i 114-feet. This configuration  !

!q provides sufficient coolant inventory to allow operator action to' terminate i j the inventory loss prior to fuel uncovery in case of an inadvertent draindown.

;8

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SY .

2 poSL /k), N & 3.5^ (,-

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CSc5-g{ g m n 1

E

l BASES:

4.5 Condden n.d Coolina Systems Surveillance Etgguratit.1 The testing interval for the core 6(ndMlalissM? I cooling systems is based on industry practice, quantitative rellalilTiri anaTysis,- judgment and practicality. The core cooling systems have not been designed to be fully testable during operation. For example, in the case of the HPCI, automatic initiation during power operation would result in pumping cold water into the reactor vessel which is not desirable. Complete ADS testing during power operation causes an undecip bie loss-of-coolant inventory. To increase the availability of the coredne%EWene~i13 cooling systems, the components which make up the system; i.e., instilim-@6tH Ton, pumps, valves, etc., are tested frequently. The pumps and motor operated injection valves are also tested each month to assure their operability. A simulated automatic actuation test once each cycle symbined with monthly tests of the pumps and injection valves is deemed to be adeounte testing of these systems. , y ' g-Thesurveillancerequirementsprovideadequateassurancethattheffor+-ai'34

e g hJ tooling systems will be operable when required.

Revision 148 Amendment No. 135 '122

_ _ - - - - - - - - _ - - 1

i UME HLCON0!HOSSl0LOPERMJON. _SURYllLLAKLRLOUIRLEMI __

3.7 COMMEINLSySl[M5 (Con't) 4.7 COMMNMNLS1SILHSEntM) -

1. If the specifications of Item i

i. above, cannot be met, and 1 the differential pressure 5

j cannot be restored within the subseauent (6) hour period, an . 8g 'p gg ) '

gr j

i orderly shutdown shall be initiated and the reactor shill be in a cold shutdown condition in 4.wenty-four (24) hours.

([Af[ V t

i m. Suppression chamber water level shall be maintained between -6 i

to -3 inches on torus level h. Containment Cooling System ,

(Drywell Spray. Torus Spray

1. instrument which corresponds to a downtomer submergence of 3.00 and Suppression Chamber  ;

and 3.25 feet respectively. Cooling) testing shall be as '

gollows: ,

1 , n. The suppression chamber can be lig f_tegency drained if the conditions as specified in Sectionf 3.5.r.33 / 1. Pump & Valve Once/? mnths

cirAf.j4 M f this Technical T g, p, (,, q Operability 7; 1pecGTcaNon are adhered to.

2. Pump Capacity Af te r ;...op Test.Each mail.terence o 'Hith irradiated fuel in the RBCCH pump and every 2, b vessel and reactor coolant shall deliver months greatef than 212'F there shall 1700 gpm

. #l '

be twc* loops of Drywell Spray at 70 ft. TDH.

Y } and Torus Spray._ p j

ach

]

] 4

. ~ ' '

M UOO N Withoneloopinoperabie' gpm at 55 4

k' k j restore the inoperable loop ft. TDH.

I' / within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in the Cold Condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. 3. Air test the Once/5 years '

' Hith both loops inoperable, drywell and restor? one loop in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or torus headers 4} <y }] }9 aN be in the Cold Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

and nozzles.

) p. Hith irradiated fuel in the 9 vessel and reattor coolant

greater than 212*F there shall f E

' be two loops of Suppression Chamber Cooling. % hu)4A44 M N

_ !W .. -?  ?

/ W ~

HithoneinoperabielooI' $c,. G Y.C5.(

restore-the inoperabis loop within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in the Cold Cor.dition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, ggQi. , \ Hith both loops inoperable, Amen M wil's 17, # L3 s- i restore one loop in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or 154-

.\ be in the Cold Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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

t N ilqEW111a5mRIRA.110h SUMIILLANCEJf 0vlE L91S_ __

3.7.B St andby _GaLT reairent_Syltetan.d 4.7.B Standby _ Gas T reatmenL5yste.m and ContraLgpom Hith Jifit ifnty Air Con t t0LRoomjiigh_I f Lttlerity_A i r Lii tIAtic.L5y11tm filt ratioL535 tem

1. Standby Gas Treatment System 1. Standby Gas Treatment System vj '. a. Except as specified in a. (1.) At least once every 18 3.7.B.l.c below, both trains months, it shall be of tne standby gas treatment demonstrated that pressure

~g3374Ct-4@A, s drop across the combined 9+aer+t+TCr MA+d-for- i high efficiency filters

.opwaten-4-wtA44tn&J and chatccal ad5orber shall be ~oceTaBe at aTT b6nks is less than 8 times when secondary inches of water at 4000 conteinment integrity is cfm.

required or the reactor shall he shutdown in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. (2.) At least once every 18 months, demonstrate that

b. (1.) The results of the -

the inlet heaters on each in-plate cold DOP tests train are operable and are on HEPA filters shall capable of an output of at show 2991 00P removal. ( least 14 kH. -

The results of I halogenated hydrocarbon (3.) The tests and analysis of 4 tests on charcoal Specification 3.7.B.I .b.

edsorber banks chall l shall be performed at -

' show 199% halogenated least once every 18 months

, hydrocarbon removal. or following painting, fire or :hemical release (2.) The results of the in any ventilation zone laboratory carbon communicating with the sample analysis shall system while the system is

, show 1951 methyl iodide operating that could

, removal a'. a velocity contaminate the HEPA

within 101 of system filters or charcoal design, 0.5 to 1.5 adsorbers, mg/m3 inlet methyl iodide contentration, (4.) At least once every 18 1701 R.H. and 1190'F. months, automatic k: i The analysis resu,ts initiation of each branch

,. are to be verified as of the standby gas

/( (l' a m ptable within 31 treatment system shall be

< days after sample { demonstrated, with

/)

y removal, or declare that ' rain inoperable Specification 3.7.B.I.d satisfied.

- and take the actions specified 3.7.B.I.c. (5.) Each train of the standby T gas treatment system shall If

c. From and after the date that i be operated for at least one train of the Standby Gas 15 minutes per month.

Treatment System is made or found to be inoperable for (6.) The tests and analysis of

. any reason, continued resctor i Specification operation, irradiated fuel } 3.7.B.l.b.( shall be

@\')

handling, or new fuel performed after every 700

~. _

w ,&

hours of system operation.

Qhmeht Amen 10, f1. 52 N NM $# E 74/ Qg 158 Y U d .a. k Q Tk "bW

b j .

LIMUINGl0ND1110MLLOR_0tERAL10N - SURV[RLANCLR(QUIR@(N]$_

i i 3.7.B (Continued) 4.7.8 (Continued)

\ .,

>' /t$4.

. handling over/ spent fuel b. (1 ) In-place cold DOP 1 0001 or core is permissible testing shall be only during the succeeding performed on the HEPA g, seven days providing that filters after each g .-! P" 2 hem all Oct he completed or partial  !

ccqcnents of the other , replacement of the j standby gas treatment train 14/ HEPA filter bank and i sh:11 be dt crM rated-tet+ af ter any structural j operable, 3 maintenance on the HEPA filtee system

! d. Fans shall operate within housing which could i 1 110% of 4000 cfm. affect the HEPA l filter bank bypass -

e. Except as specified in leakage.

1 3.7.B,1.c, both trains of i

the Standby Gas Treatment (2.) Halogenated

. .h System shall be operable hydrocarbon testing '

,1 during irradiated fuel shall be performed on e

'} handling, or new fuel the charcoal adsorber

' q handling over the spent fuel pool of core. If the bank after each partial or complete

, system is not operable, replacement of.the i

e t

fuel movement shall not be charcoal adsorber j started. Any fuel 3ssembly

,'- bank or after any j movement in progress may be structural

,1 completed. maintenance on the

'l charcoal adsorber 3

' housing which could affect the charcoal adsorber bank bypass i leakage.

I I

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l

LIM 1111G COND1110X5l0LONRAl10N SUBYULLANCLREQUIREMMS 3.7.8 (Continued) 4.7.B (Continued)

2. ContraLRoonttilghlflicitetyJlt 2. CenirnLRonJ19tLEf fi CienCy_ldt Ultatia.lyitem flltation_Syltelti

, a. Except as specified in a. At least once every 18 months the y Specification 3.7.B.2.c below, pressure drop across each combined v both trains of the Control Room filter train shall be demonstrated High Efficiency Air filtration to be less than 6 inches of water at System used for the processing 1000 cfm or the calculated of inlet ett to the control room equivalent.

und ditr hccident 9 condi,tionsFEE D4TEeb b. eneratw4++-t+qthed-(1.) The tests and analysis of f or-opwa(4on-of-eaeh-t rab-of- Specification 3.7.B.2.b $hal1

-the-+y3teMall be opefable be performed once every 18

'Wieirever secondary containment months or fol!owing painting, integrity is required and during fire or chemical release in fuel handling opcrations. .

any ventilation zone communicating with the system

b. (1.) The resulh of the while the system is operating.

in-place cold DOP tests o HEPA filters shall show (2.) In-place cold 00P testing 199% DOP removal. The shall be perfornied af ter each results of the halogenated complete or partial hydrocarbon tests on replacement of the HEPA filter charcoal adsorber banks bank or after any structural C all show 199% maintenance on the system

. halogenated hydroce.rbon housing which could affect the removal when test results HEPA filter bank bypass are extrapolated to the leakage, initiation of the test.

' (3.) Halogenated hydrocarbon (2.) The results of the testing shall be performe' laboratory carbon sample after each complete or partial analysis shall show 195% replacement of the charcoal methyl iodide removal at a adsorber bank or after any velocity within 10% of structural maintenance on the system delign, 0.05 to system housing which couid 0.15 mg/m3 inlet methyl affect the charcoal adsorber iodide concentratien,170% bank bypass leakage.

R.H., and 2.125'F. The

/ analysis results are to be verified as acceptable (4.) Each train shall be operated

' with the heaters in automasic within 31 days after for at least 15 minutes every-sample removal, or declare

([ri ,

that train inoperable and f month.

U,/ take the actions specified (5.) The test and analysis of

< in 3.7.B.2.c. Specification 3.7.8.2.b.(2) shall be performed after every g g 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation.

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Amendment'No.50,Et,52,70I,h 158B

LIM 111NG_CGDil10NS FOREIM110N SURVE!1LANCLREQUIREME!!IS ._

3.7.B (Continued) 4.7.B (Continued) j / c. From and after the date that c. At least once every 18 j one train of the Control Room months demonstrate that -

7 High Efficiency Air the inlet heaters on each Filtration System is made or train are operable and j

j found to be incapable of supplying filtered air to the capable of an output of at least 14 h

((t

/

j control room for any reason,

reactor operation or d. Perform an instrument q refueling operations are functional test on the

} pi permissible only during the humic. stats controlling j succeeding 7 days providing the heaters once per 18 ,

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Acttve-c:cponents 9 the months. >

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, other CRHEAF train theM - S

! u> 4c:non:tiat+4 operable 4 If l the system is not made fully l operable within 7 days, i reactor shutdown shall be initiated and the reactor shall be in cold shutdown I within the next 36 hour4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />s-and

irradiated fuel handling

operations shall be i terminated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.- -

i d I fuel handling operations in progress may be completed.

d. Fans shall operate within -

1107. of 1000 cfm.

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4.7.C S c e n nd t ry Contain-mnt 1~

3.7.C Serendarv Contninw nt

1. Secondnry cont ainnent turv eil l ant e 1, Sceendary c o n t e i r.r.e n t int (t- shall be perforned as indicated belew; l rity thall be cafntained duriur. t.11 todes of plant A I rcopc tnt ienal s econd ary cer.t cint.e nt a.

4 i

operation treept ' hen t.11 of capability ic:.t ihn11 te eend;:ted t h t- sollevior, conditions are nfter inclitthl' the re c e t or bui htir; 5 trect-cx t . and placing ei t her s t r.nd!'y r ta j

ment syste m filter train in op at ten.

c. The reacter it r,uberitical and Euch t es t e r.h611 demonr,t rat e t he j Epecif tentien 3.3.A it. met.

l capability to maintnin 1/4 ath (< 5 gn) of We reccter veier trtgernture water vacuum under ctilm vind

b. conditient with a filter train ficv

is belov

';P'r and the reactor rate of not rxare t.han 4000 ein.

j c oolant cyctec is vented. e -

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b. A4444,**4 ta14,hati_.t w h 4 d

c. l'o activity is beine perforced, dimin r4be-fh+;- oper Hot--eve +e---

j which can redete the shutdown wJar * 'A*'p Me ""C<r cf differ w.

turgin belev that r.pecified ir. +ny bweMA u ! H e t i t i e r 1 r un, Lpecification 3.3.A. #h)W io e t mni n+ f er- e f ca. ten j s 4u14.5

d. ne fuel crth or irrtdiated e /. _~

j fuel is not tcing rt.oved in the Secondary containment copability to j

q3 reneto- buildint,. c.

neintain 1/4 inch of vnter vetuum i

" y - under colta vind (($ eph) cenditions 2 If Speciffention 3.7.C.1 can- with a filter train flow rate of not not be net, proecdures shall t:.are than 4000 cfm, chall be der.an.'

5)f be initiat ed to establir.h con-T strated at each reiucling cutrice V ditions listed in $recificatior f prior to refueling.

3.7.C.1. a through M

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{ Emperimental data indicates that excessive steam condensing loads can be j avoided if the peak local temperature of the pre #sure suppression pool is

• j maintained below 200*f during any period of relief-valve operation with sonic 3 conditions at the discharge exit. Analysis has been performed to verify that i the local porl temperature will stay below 200*F and the bulk temperature will

stay below 160*F for all SRV transients. . Specifications have been placed on the envelope of reactor operatirg conditions so that the reactor can be depressurized in a timely manner to avoid the regime of potentially high pressure suppression chamber loadings.

In addition to the limits on temperature of the suppression chamber pool water, operating procedures define the action to be taken in the event a relief valve inadvertently opens or sticks open. This action would include:

i (1) use of all available treans to close the valve, (2) inttlate suppression i pool water cooling heat exchangers, (3) initiate reactor shutdown, and (4) if .

other reliei valves are used to depressurize the reactor, their discharge shall be separated from that of the s Nck-open relief valve to assure mixing and uniformity of energy insertion to the pool.

l Because of the large volume and thermal capacity of the suppression pool, the

volume and temperature normally changes very slowly and monitoring these 1

parameters daily is sufficient to establish any temperature trends. By

requiring the suppression pool temperature to be continually monitnred and

' frequently logged during periods of significant heat addition, the temperature I

trends will be closely followed so that appropriate action car. be taken. .The requirement for an external visual examination following any event where 4

potentially high loadings could occur provides assurance that no significant i damage was encountered.

Particular attention should be focused on structural i

discontinuities in the vicinity of the relief valve discharge since these are expected to be the points of highest stress.

If a loss-of-coolant accident were to occur when the reactor water temperature i

is below approximately 330*F, the containment pressure will not exce:d the 62psig code permissible pressure, even if no condensation were to occur. The maximum allowable pool temperature, whenever the reactor is above 212*F, shall i

be governed by this specification. Thus, specifying water volume-temperature requirements applicable for reactor-water temperatu7 abc e 212*F provides

!, additional margin above that available at 330*F.

I - .

3.7.A. Containment Coolina System-Drywell Snrav. Torus Sorav.-Suppressio~n M l Chamber Co911D9 i

The containment cooling system for Pilgrim I consists of two independent loops each of which to be an operable loop requires one LPCI pump, two RBCCW pumps and two SSW pumps. There are installed spares for margin above the design conditions, Eacgsystemhasthecapabilitytoperformitsfunction;i.e.,

removing 64 x 10 Blu/hr (Ref. Amendment 18), even with some system

~

degradation. If one loop is out of-service, reactor operation is permitted for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

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Cont ainmont Cooling _Syst em (Cont 'dl  !

bithcomponentsor systems cut-of service, overall containment cooling reliability is maintained by the operability of the remaining cocling equipment.

Since some of the SSW and RBCCW pum;,s associated with the Containment Cooling i System are required for normal operation, capacity testing of individual pumps .

. by direct flow measurement is impractiral. The pump capacity test is a '

/ comparison of measurec pump performance parameters to shop performance tests combined with a comparison to the performance of the previously tested pump.

l These pumps are rotated during operation and performance testing will be integrated with this or performed during refueling when pumps can be flow ftestedindividually. Tests during normal operation will be performed by measuring the shutoff head. Then the pump under test will be placed in service and one of the previously operating pumps secured. Total flow indication for the system will be compared for the two cases. Where this is not feasible due to changing system conditions, the pump discharge pressure will be measured and its power requirement will be used to establish flow at that pressure, ,

The Drywell Spray, Torus Spray and Suppression Chamber Cooling systems are-necessary during power operations. Specification 3.7 imposes Surveillances ,

and limitin; Conditions for Oparation to ensure the operability of the '

equipment. When the equipment is inoperable the plant is brought to a condition where the equipments is not necessary.

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3.7.B.1 arid 4.7.]LLLcon11Midl The test frequencies are adequate to detect equipment deterioration prior to significant defects, but the tests are not frequent enough to load the filters or adsorbers, thus reducing their reserve capacity too quickly. The filter

^

testing is performed pursuant to appropriate procedures reviewed and approved by the Operations Review Committee pursuant to Section 6 of these Technical Specifications. The in-place testing of charcoal filters is performed by injecting a halogeaated hydrocarbon into the system upstream of the charcoal adsorbers. Heasurements of the concentration upstream and downstream are made. The ratio of the inlet and outlet concentrations gives an overall indicition of the leak tightness of the ystem. A similar procedure substituting dioctyi phthalate for halogenated hydrocarbon is used to test the HEPA filters.

Pressure drop tests across filter and adsorber banks are performed to detect plugging or leak paths thouch tSe filter or adsorber media. Considering the relatively short times the m will be run for test purposes, plugging is.

unlikely ar.d the test interval of once per 18 months is reasonable.

System drains and housing gasket doors are designed such that any leakage would be inleakage from the Standby Gas Treatment System Room. This ensures that there will be no bypass of process air around the filters or adsorpers.

,wv24. m A w d Only one of the two Standby Gas Treatment Syst s(SBG1S)isneeledto maintain the secondary containment at a 0.25 i ch of water negative pressure upon containment isolation. If one system is found to be inoperable, thcre is no immediate threat to the containment system performance and reactor operation k-the eventor ererefueling SBCTS i:activities may i noper:ble, continuegd+nt-+ystem':hile the-red .. repairs are being m Oc-t4 w -tempenentt ei be-te:ted wktH- 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />;. -TM+-wbshn htes the- availability of ik operabl e cy: tem-and--}ve t t 't es - centAnad-r4a[ter er r44o44*g-4 pe If both trains of SBGTS are inoperable, e plant is brought to a condition where the SBGTS is not required.

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OIRiD Amendment No. 42, 173

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

BbSIS:

LLL2aL4.7.B1JIon11aued)

}'

Air flow through the filters and charcoal adsorbers for 15 minutes each month }

assures operability of the system. Since the system heaters are automatically t controlled, the air flowing through the filters and adsorbers will be 1707.

relative humidity and will have the desired drying effect.

,p Q.v ti fit S at^+d-k$ t  %

,l If one train of)4fe system is found to be inoperable, ere is no immediate f' l threat to the jebntrol room, and reactor operation or uel handling may continue forta 'imited peM ed of tirS while repairs re being made. JW h6 j ovent en: CPHEAM+at- 1:, 'noperabic, the redundant systWs-eet4*e-tomponents wA4L4s-4464+ddh4n-NK+ue. If both trains of the CRHEAf system are j l

inoperable, the reactor will b brought to a condition where the Control Room High Efficiency Air Filtratio System is not required. /

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Amendment o. 42 7 174A

1

' ' ' I

) llMITING CONDil!D!iS FOR OPERA 110N SEVEILLANCE REOL,lREli[jfLS 3.9=C Diesel _ Genera 19I -

l StquirementiCold Condition  ;

and Subtritical '

k j 1. When the reactor is in the i

! Cold Condition and '

} Subtritical there shall be '

] one offsite power source >

j capable of energizing the emergency buses and either '

l Emergency Diesel Generator 1 operable.

I 1

l 2. When the reactor is in the i i

4 Cold Condition and Subcritical if a train or

} loop of a required system is

inoperable, the Emergency i Diesel Generator associated 1

{ with the operable train or-loop must be operable, i

i

3. With no offsite power -

! supplies operable and/or both j Emergency Diesel Generators

! inoperable, suspend core

[ alterations, handling :r i irradiated fuel in the ,

, secondary containment, and -

! operations with a potential l for draining the vessel. ,

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LAmendment No.

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3.9.C Diesel Gtperaigr_Reauirements - Cold Conditiqn and Subcritk al The operability of A.C. power sources when in shutdown and refuel conditions l) i assures: (1) adequate coolant inventory for the irradiated fuel in the core in case of an inadvertent draindown of the vessel; (2) mitigation of a fuel j bundle handling accident; (3) sufficient power for required support systems (e.g., decay heat removal, refueling activities, component cooling); and (4)

. sufficient instrumentation and control capability for monitoring and

maintaining the unit status.

( lt is unnecessary to require the sources of emergency power to be completely redundant. Specification 3.9,0.1 considers emergency electrical power bus

, recairements met with offsite power and one emergency diesel generator J operable. The remaining bus is considered operable with just a source of offsite power available.

! This specification impacts other safety functions which electric power

supports. Each of these safety functions has been evaluated previcusly, and j it was concluded that the power requirements of Specification 3.9.C.1 support

the other safety functions such that shutdown risk is acceptably low, i 1his spec fication precludes the potential for having unacceptable combinations of system alignments, and enhances safety by eliminating the l pc ential for misinterpreting 3.9.C.I.

Specification 3.9.C.3 requires the suspension of core alterations, the

handling of irradiated fuel in the secondary containment and operations with a potential to drain the vessel when no sources of off

ite and/or emergency power is available.

l Thus, operations which have the potential to rtsult in an event requiring the operation of a safety system, such as SGTS, must be suspended if both emergency buses are supplied by only one source of power. This reduces the ,

j probability of an adverse event and maintains the reactor in a safe condition while additional sources of power are restored.

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1%a Pne-m Amendment No. 199A P

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