ML17285A242

Proposed Tech Specs Incorporating Clarifications Re Sections 3.0 & 4.0, Limiting Conditions for Operation & Surveillance Requirements.

ML17285A242
Person / Time
Site:	Columbia
Issue date:	02/09/1989
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17285A241	List: ML17285A240 ML17285A242
References
NUDOCS 8902150375
Download: ML17285A242 (96)

Text

3/4. 0 APPLICABILITY LIMITING CONDITION FOR OPERATION

3. 0. 1 Compliance with the Limiting Conditions for Operation contained in the succeeding Specifications is required during the OPERATIONAL CONDITIONS or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met.

3.0.2 . Noncompliance with a Specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals. If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the Action requirements is not required.

3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in an OPERATIONAL CONDITION in which the Specification does not apply by placing it,,y~0 applicable, in:

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1. At least STARTUP; in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,

2. At least HOT SHUT .within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and

3. At least COLD SHUTD ~ithin the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Where corrective measures are coihg@ed that permit operation, under the ACTION requirements, the ACTION may be taky Qn accordance with the'specified time limits as measured from the time of ure to meet the Limiting Condition for Operation. Exceptions to these requs ts are stated in the individual Specifications.

This specification is not applicable in 0 IONAL CONDITION 4 or 5.

474cA 3.0.4 "Entry(into an OPERATIONAL CONDITION or other specified condition shall not be made en4eee the conditions for the Limiting Condition for Operation are provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual Specifications.

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- APPLICABILITY SURVEILLANCE REOUIREMENTS 4.0.1 Surveillance Requirements shall b'e met during the OPERATIONAL CONDITIONS or other conditions specified for individual Limiting Condi ions for Operation unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:

a. A maximum allowable extension not to exceed 25K of the surveillance interval, but

b. The combined time interval for any 3 consecutive surveillance intervals JCPu4 L] interval shall constitute Sp.,g~t;~

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'the shall not exceed 3.25 times the specified surveillance interval.

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OPERABILITY requirements Surveillance requirements do not have to be for a performed on inoperable equipment.

4.0.4 Entry in.o an, OPERATIONAL CONDITION or ot specified applicable condition shall not be made unless the Surveill Requirement(s) associated with the Limiting Condition for Operation have n performed within the applicable snrveil'lance interval or as othe p:<<'A<<~ <<pr<<r f.hv oeqA

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.O.o Surveillance Requirements for inse~ i Code Class 1, 2; 8 3 components shall'~gp

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a. Inservice inspection of ASM/ e Class 1, 2, and 3 components and inservice testing of ASME Chgt Class 1, 2, and 3,pumps and valves shall be performed in ac ance with Section XI of the ASME Boiler and Pressure Vessel Co applicable Addenda as required by 10 CFR 50, Section 50.55'( , except where specific written relief has been granted by the CPPhission pursuant to 10 CFR 50, Section 50.55a(g)

(6) (i).

b. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ASM" Boiler and 'Pressure Vessel Required frequencies Code and applicable Addenda for performing inservice terminology ior inservice inspection and testing inspection and testino activities activities Weekly At least once per 7 days Monthly At least once per 31 days quarterly or every 3 months At least once per 92 days Semiannually or every 6 months ,At least once per 184 days e Every 9 months At least once per 276 days Yearly or annually least

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REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION (Continued) a) Electrically, or b) Hydraulically by closing the drive water and exhaust water isolation valves.

2. If the inoperable control rod(s) is inserted, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, disarm the associated directional control valves"* either:

a) Electrically, or b) Hydraulically by closing the drive water and exhaust water isolation valves.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

C. With more than eight control rods erable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE RE UIREMENTS 4.3..3.1. 1 The scram discharge vol rain and vent valves shall be demonstrated OPERABLE by:

a. At least once per 3 s verifying each valve to 'be open," and

h. At least once per Rdtlays cyc1ing each valve through at least one complete cycle of full'ravel.-

4.1.3.1.2 When above the low power setpoint of the RWM and RSCS, all withdrawn control rods not required to have their directional control valves disarmed electrically or hydraulically shall be demonstrated OPERABLE by moving each control rod at least one notch:

a. . At least once per 7 days, and

b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when any control rod is immovable as a result of excessive friction or mechanical interference.

4.1.3.1.3 All control rods shall be demonstrated OPERABLE by performance of Surveillance Requirements 4. 1.3.2, 4.1.3.4, 4.1.3.5, 4. 1.3.6, and 4. 1.3.7.

"These valves may be closed intermittently for testing under administrative controls.

""May be rearmed intermittently, under administrative control, .to permit testing associated with restoring the control rod to OPERABLE status.

WASHINGTON NUCLEAR " UNIT 2 3/4 1-4

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REACTIVITY CONTROL SYSTEMS CONTROL ROD MAXIMUM SCRAM INSERTION TIMES LIMITING CONDITION FOR OPERATION 3.1.3.2 The maximum scram insertion time of each control rod from the fully withdrawn position to notch position 6, based on'eenergization of the scram pilot valve solenoids's time zero, shall not exceed 7 seconds.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

ACTION:

t With the maximum scram insertion time of one or more control rods exceeding 7 seconds:

1. Declare the control rod(s) with the slow inser+ion time inoperable, and

2. Perform the Surveillance Requirements of Specification 4. 1.3.2c.

at least once per 60 days when o eration is continued with three or more control rods with maxi cram insertion times in excess of 7 seconds.

Otherwise, be in at least HOT WN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE RE UIREMENTS

4. 1.3.2 The maximum scram ion time of the control rods shall be demonstrated through measure with reactor coolant oressure greater than or equal to 950 psig and, during single control rod scram time tests, the con rol rod drive pumps isolated from the accumulators:

For all contro'. rods prior to THERMAL POWER exceeding 40Ã of RATED THERMAL POWER following CORE ALTERATIONS" or after a reactor shutdown'hat is greater than 120 days.

For specifically affected individual control rods following maintenance on or modification to the control rod or control rod drive system which could affect the scram insertion time of those specific control rods, and I

c ~ For at least 10~ of the control rods, on a rotating basis, at least once per 120 days of POWER OPERATION.

"Except movemen+ of SRM, IRM, or special movable detectors or normal control rod movement.

WASHINGTON NUCLEAR - UNIT 2 3/4 1-6

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REACTIVITY CONTROL SYSTEMS FOUR CONTROL ROD GROUP SCRAM INSERTION TIMES LIMITING COHOITIOH FOR OPERATION 3.1.3.4 The average scram insertion time of all operable control rods from the fully withdrawn position, for the four control rods arranged in a two-by-two array, based on deenergization of the scram pilot valve solenoids as time zero, shall not exceed any of the following:

Position Inserted From Average Scram Inser-Full Withdrawn tion Time Seconds 45 0.455 39 0. 920 25 2. 052 5 3.706 APPLICABILITY: OPERATIONAL COHOITIOHS 1 and 2.

ACTION:

With the average scram insertion times of control rods exceeding the above limits:

1. Declare the control rods with the slower than average scram insertion times inoperable until an analysis is performed to determine that required scram reactivity remains for the slow four control rod group, and

2. Perform the Surveillance Requirements of Specification 4.1.3.2.c at least once per 60 days when operation is continued with an aver age scram insertion time(s) in excess of the average scram insertion time limit.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE RE UIREMEHTS

4. 1 3.4 All control rods shall be demonstrated OPERABLE by scram time testing from the fully withdrawn position as required by Surveillance Requirement 4.1.3.2.

WASHINGTON HUCLEAR - UNIT 2 3/4 1-8 Amendment Ho. 45

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'EACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS LIMITING CONDITION FOR OPERATION 3.1.3.5 All control rod .scram accumulators shall be. OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1,.2, and 5".

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ACTION:

In OPERATIONAL CONDITIONS 1 or 2:

With one control rod scram accumulator inoperable, within 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />s:

a) Restore the inoperable accumulator to OPERABLE status, or b) Declare the control rod associated with the inoperable accumulator inoperable.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

2. With more than one control rod scram accumulator inoperable, declare the'associated control rods inoperable and:

a) If the control rod associated with any inoperable scram accumulator is withdrawn, immediately verify that at least one control rod drive pump is operating by inserting at least one withdrawn control rod at least one notch or place the reactor mode switch in the Shutdown position.

b) Insert the inoperable control rods and disarm the associated control valves either:

1) Electrically, or

2) Hydraulically by closing the drive water and exhaust water isolation valves.

Otherwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b. In OPERATIONAL CONDITION 5":

With one withdrawn control rod with its associated scram accumu-lator inoperable, insert the affected control rod and disarm the associated directional control valves within one hour, either:

a) Electrically, or b) Hydraulically by closing the drive water and exhaust water isolation valves.

2. With more than one withdrawn control rod with the associated scram accumulator inoperable or no control rod drive pump operating, immediately place the reactor mode switch in the Shutdown position.

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• At least the accumulator associated with each withdrawn control rod. Not applicable to control rods removed per Specification 3.9.10. 1 or 3.9.10.2.

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WASHINGTON NUCLEAR - UNIT 2. 3/4 1-9

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REACTIVITY CONTROL SYSTEMS CONTROL ROD DRIVE COUPLING LIMITING CONDITION FOR OPERATION 3.1.3e6 All control rods shall be coupled to their drive mechanisms.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 5~.

ACTION:

In OPERATIONAL CONDITION 1 and 2 with one control rod not coupled to its associated drive mechanism, within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:

1. If permitted by the RWH and RSCS, insert the control rod drive mechanism to accomplish recoupling and verify recoupling by withdrawing the control rod, and:

a) Observing any indicated response of the nuclear instrumenta-tion, and b) Demonstr that the control rod will not go to the over-travel pos Otherwise, be in a ast HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

2. , If recoupling is not gc mplished on the first attempt or, not if permitted by the RWH o ~S, then until permitted by the RWH and RSCS, declare the controlled inoperable, insert the control rod and disarm the associated~lr ctional control valves"" either:

a). Electrically, or b) Hydraulically by closing @~drive water and exhaust water

- isolation valves.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b. In OPERATIONAL CONDITION 5~ with a withdrawn control rod not coupled to its associated drive mecnanism, within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, either:

1. Insert the control rod to accomplish recoupling and verify recoupling by withdrawing the control rod and demonstrating that the control rod will not go to the overtravel position, or

2. If recoupling is not accomplished, control insert the control rod and valves"" either:

disarm the associated, directional a) Electrically, or b) Hydraulically by closing the drive water and exhaust water isolation valves.

"At least each withdrawn control rod. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

~~May be rearmed intermi,tten"ly, under administrative control, to permit testing associated with restoring the control rod to OPERABLE status.

WASHINGTON NUCLEAR - UNIT 2 3/4 1-11

REACTIVITY CONTROL. SYSTEMS CONTROL ROD POSITION INDICATION LIMITIHG CONDITION FOR OPERATION 3.1. 3.7 The control rod position'ndication system shall be OPERABLE.

APPLICABILITY: OPERATIOHAL CONDITIONS 1, 2, and 5".

ACTION:

a. In OPERATIONAL CONDITION 1 or 2 with one or more control rod position indicators inoperable, within 1 hour:

1. Determine the position of the control rod by performing a 00-7 on the process computer, or

'. Move the control rod to indicator, or a position with an OPERABLE position

3. When THERMAL POWER is:

a) Within the low po setpoint of the RSCS:

1) Declare th c trol rod inoperable, and

2) Verify position and bypassing of control rods with inopq@ "Full-in" and/or "Full-out" position indi" cat %y a second licensed operator or other tech-,

nj y qualified member of the unit technical staff.

b) Greater han the low power setpoint of the RSCS, declare the control rod inoperable, insert the control rod, and disarm the associated directional control valves"" either:

1) Electrically, or

2) Hydraulically by closing the drive water and exhaust water isolation valves.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b. In OPERATIOHAL CONDITION 5" with a withdrawn control rod position indicator inoperable, move the control rod to a position with an OPERABLE position indicator or insert the control rod.

"At least each withdrawn control rod. Not, applicable to control rods removed per Specification 3. 9. 10. 1 or 3. 9. 10. 2.

""May be rearmed intermittently, under administrative control, to permit testing associated'ith restoring the control rod to OPERABLE status.

WASHINGTON NUCLEAR - UNIT 2 3/4 1-13

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REACTIViTY CONTROL SYSTEMS 3/4.1.4 CONTROL ROD PROGRAM CONTROLS ROD WORTH MINIMIZER LIMITING CONDITION FOR OPERATION

3. 1.4. 1 The rod worth minimizer (RWM) shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2", when THERMAL POWER is less than or equal to 20~ of 'RATED THERMAL POWER, the minimum allowable low power setpoint.

ACTION:

With the RWM inoperable, verify control rod movement and compliance with the prescribed control rod pattern by a second licensed operator or other technically qualified member of the unit technical staff who is present at the reactor control con'sole. Otherwise, control rod movement may be only by actuating e manual scram or placing the reactor mode switch in the Shutdo sition.

SURVEILLANCE REOUIREMENTS 4.1.4.1 The RWM shall be demonstrate P ABLE:

a~ In OPERATIONAL CONDITION hin 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to withdrawal of control rods for the pu of making the reactor critical, and in OPERATIONAL CONDITION thin 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to RWM automatic initia-tion when reducing TH L POWER, by verifying proper indication of the selection error o at least one out-of-sequence control rod.

b. In OPERATIONAL CONDITION 2 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to withdrawal of control rods for the purpose of making the reactor critical, by verifying the rod block function by demonstrating inability to withdraw an out-of-sequence control rod.

C. In OPERATIONAL CONDITION 1 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after RWM automatic initiation when reducing THERMAL POWER, by verifying the rod block function by demonstrating inability to withdraw an out-of-sequence control rod.

By demonstrating that the control rod patterns and sequence input'o the RWM computer are correctly loaded following any loading of the program into the computer.

"Entry into OPERATIONAL CONDITION 2 and withdrawal of selected control rods is permitted for the purpose of determining the OPERABILITY of the RWM prior to withdrawal of control rods for the purpose of bringing the reactor to criticality.

WASHINGTON NUCLEAR - UNiT 2 3/4 1"16

TABLE 3. 3. 3-1 (Continued)

~EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION STATEMENTS ACTiON 30 With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement:

a. For one trip system, place the inoperable channel(s) and/or t, t trip system in the tripped condit on within 1 hou declare the associated system inoperable.

b. For both trip systems, declare the associated system inoperable.

ACTION 31 " With the number of OPERASLE channels less than required by .he Minimum OPERASLE Channels per Trip Sys em.requirement, place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; restore the inoperable channel to OPERABLE status within 7 days or declare the associated system inoperable.

ACTION 32 With the number of OPERABLE channels less than required by the L~

Minimum OPERABLE Channels per Trip System requirement, declare the associated system inoperable.

ACTION 33 " With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, place the inoperable channel in he tripped condi .ion within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ACTION 34 " With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Sys em requirement, restore the inoperable channel to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or declare the associated ECCS inoperable.

ACTION 35 With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requir ment, restore the inoperable channel to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or decl'are the associated AOS division inoperable.

ACTION 36 With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, place the jqoperabie channel in the tripped condition within 1 houMor declare the HPCS system inoperable.

ACTICN 37 " With the number of OPERABLE channels less than the Total Number of Channels, declare the associated emergency diesel generator inooerable and take the ACTION required by Specification 3.8. 1.1 or 3.8. 1.2, as appropriata.

ACTION 38- With the number of OPERABLE channels one less than the Total Number of Channels, ola e the inoperable channel in the t~ipped condition wi hin 1 hou ", ooeration may then continue until performance of the nex required CHANNEL FUNCTIONAL TEST.

WASHINGTON NUCLEAR UNIT 2 3/4 3-29

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3/4. 3 INSTRUMENTATION 3/4.3. 1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITIHG CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.

APPLICABILITY: As shown e

in Table 3.3.1"l.

ACTION:

a. Mith the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system,

'lace the inoperable channel(s) and/or that trip system in the tripped condition" within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

b. Mith the .number. of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for both trip systems, place at least one trip system"" i+the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> aod take the ACTION require Table 3.3. 1-1.

SURVE",.LLANCE REOUIREMENTS 4.3.' 1 Each reactor protection s sbhh instrumentatiean channe'l shall be demonstrated OPERABLE by the per nce of the CHAHHEL CHECK, CHANNEL FUNC, IONAL TEST and CHANNEL CA/ ION operations for the OPERATIONAL CONDITIONS and at the frequen W shown in Table 4.3. 1. 1-1.

4.3. 1.2 LOGIC SYSTEM FUH L TESTS and simulated automatic operation of all channels shall be perfo ,ed at least once per 18 months.

4.3. 1.3 The PEACTOR PROTECTION SYSTEM RFSPONSE TIME of each reactor trip functional unit shown in Table 3.3. 1-2 shall be demonstrated to be within its limit at least, once per 18 months. Each test shall include at least one channel per trip system such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a speci;ic reactor trip system.

"An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION.

required by Table 3.3. 1-1 for that Trip Function shall be taken.

"~If more channels are inoperable in one trip system than in the other, place the trip system with more inoperable channels in the tripped condition, except when this would cause the Trip Function to occur.

MASriINGTON NUCLEAR - UNIT 2 3/4 3-1

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INSTRUMENTATION 3/4 3 2 ISOLATION ACTUATION INSTRUMENTATIOH LIMITING CONDITION FOR OPERATIOH

3. 3. 2 The isolation actuation instrumentation channels shown in Table 3. 3. 2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.2-2 and with ISOLATION SYSTEM RESPONSE TIME as shown in Table 3.3.2-3.

APPLICABILITY: As shown in Table 3.3.2-1.

ACTION:

a4 With an isolation actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint .value.

b., With the number of OP E channels less than required by the er Trip System requirement for one. trip Minimum, OPERABLE Charm system, place the inoper channel(s) and/or that trip sys em in the tripped condition" wi e

c. Withthe number of OPERABLE ch ~s less than required by the Minimum Trip Syst+~quirement for both t'rip systems, OPERABLE Channels per place at least one trip system""

hour and take the ACTION required b

~ e tripped condition within one le 3.3.2-1.

"An inoperable cnannel need not be placed in the@a ipped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE s atus within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION required by Table 3.3.2-1 for that, Trip Function shall be taken.

""If more channels are inoperable in one trip system than in the other, place the trip system with more inoperable channels in the tripped condition, except when this would cause the Trip Function to occur.

WASHINGTON NUCLEAR - UNIT 2 3/4 3-10

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-GGRTRGILLEI9 GQP INSTRUMENTATION END-OF" CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.4.2 The end-of-cycle recirculation pump trip (EOC-RPT) system instrumentation channels shown in Table 3.3.4.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.4.2-2 and with the END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME as shown in Table 3.3.4.2-3.

k APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL is greater than or q qW%%u i D T E A P WER.

POWER ACTION:

a. With an end-of-cycle recirculation pump trip system instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values. column of Table 3.3.4.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with the channel setpoint adjusted consistent with the Trip Setpoint value.

b. With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels per Trip System requirement for one or both trip systems, place the inoperable channel(s) in the tripped condition within one hour.

c. With the number of OPERABLE channels two or more less than required

.by the Minimum OPERABLE Channels per Trip System requirement for one trip system and:

l. If the inoperable channels consist of one turbine governor valve channel and one turbine throttle valve channel, place both inoperable channels in the tripped condition within one hour.

2. If the inoperable channels include two turbine governor valve channels or two turbine throttle valve channels, declare the trip system inoperable.

d. With one trip system inoperable, restore the inoperable trip system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or evaluate MCPR to be equal to or greater than the applicable MCPR limit without EOC-RPT within one hour" or take the ACTION required by Specification 3.2.3.

e. With both trip systems inoperable, restore at least one trip system to OPERABLE status within one hour or evaluate MCPR to be equal to or greater than the applicable MCPR limit without EOC-RPT within one hour" or take the ACTION required by Specification 3.2.3.

~If MCPR is evaluated to be equal to or greater than the applicable MCPR limit without EOC-RPT within one hour, operation may continue aadWh WASHINGTON NUCLEAR " UNIT 2. 3/4 3"41 Amendment No. 28

E

~ V INSTRUMENTATION 3/4. 3. 7 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION

-. LIMITING CONDITION FOR OPERATION 3.3.7. 1 The radiation monitoring instrumentation channels shown in Table 3.3.7. 1-1 shall be OPERABLE with their alarm/trip setpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3.7.1-1.

ACTION: I ao With a radiation monitoring instrumentation channel alarm/trip set" point exceeding the value shown in Table 3.3.7.1-1, adjust the set-point to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel, inoperable.

b. With one or more radia monitoring channels inoperable, take the ACTION required by Table 7. 1-1.

The prov i s i ons of Speci fi ca'.0.3 aazhS=GW are not applicable.

SURVEILLANCE RE UIREMENTS

4. 3. 7. 1 Each of the above required radiation mons ing instrumentation channels, shall be demonstrated OPERABLE by the pe formance of the CHANNEL CHEEK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the conditions and at the frequencies shown in Table 4. 3. 7. 1-1.

WASHINGTON NUCLEAR - UNIT 2 3/4 3-58

(

INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION LIMITING COHOITION FOR OPERATION 3.3.7.2 The seismic monitoring instrumentation shown in Table 3.3.7.2-1 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

a. With one or more of the above required seismic monitoring instruments inoperable for more than 30 days, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Repor't to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrument(s) to OPERABLE status.

b. The provision pecification 3. 0:3 ~4~4 are not applicable.

SURVEILLANCE REOJIREMENTS Each of the above require

'.3.7.2.1 smic monitoring instruments shall be demonstrated OPERABLE by the performa6 'the CHANNEL CHECK, CHANNEL FUNC-TIONAL TEST, and CHANNEL CALIBRATION op ns at the 'frequencies shown in Table 4.3.7.2"l.

4.3.7.2.2 Each of the above required seismic monitoring instruments actuated during a seismic event greater than or equal to 0.01 g shall be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a CHANNEL CALIBRATION performed within S days following the seismic event. Oata shall be retrieved from actuated instruments and analyzed to determine the magnitude of the vibratory ground motion. In lieu of any other report required by Specification 6.9.1, a Special Report shall be prepared and submitted to the Commission pursuant to Specifi-cation 6.9.2 within 10 days describing the magnitude, frequency spec rum, and resultant effect upon unit features important to safety.

WASHINGTON HUCLEAR - UNIT 2 3/4 3"61

% ~ f A INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.3 The meteorological monitoring instrumentation channels shown in Table 3.3.7.3-1 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

With one or more meteorological monitoring instrumentation channels inoperable for more than 7 days, in lieu of any other report required by Specification 6. 9. 1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrumentation to OPERABLE status.

b. The provisions of Specification 3. 0. 3 are not applicable.

+

SURVEILLANCE RE UIREMENTS 4.3.7.3 Each of the above required Wrological monitoring instrumentation channels shall be demonstrated OPER by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations "the frequencies shown in Table 4.3.7.3-1.

WASHINGTON NUCLEAR - UNIT 2 3/4 3-64

INSTRUMENTATION REMOTE SHUTDOWN MONITORIHG INSTRUMENTATION .

LIMITIHG CONDITION fOR OPERATION 3.3.7.4 The remote shutdown monitoring instrumentation channels shown in Table 3.3.7.4-1 shall be OPERABLE w'ith readouts displayed external to the con-trol room.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

ACTION:

With the number of OPERABLE remote shutdown monitoring instrumenta-tion channels less than required by Table 3.3.7.4-1, restore the inoperable channel(s) to OPERABLE status within 7 days or be in at least HOT SHUTDOMN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Og SURVEILLANCE RE UIREMEHTS 4.3.7.4 Each of the above required shutdown monitoring instrumentation channels shall be demonstrated OPERABL performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at t quencies shown in Table 4.3.7.4-1.

WASHINGTON NUCLEAR - UNIT 2 3/4 3-67

INSTRUMENTATION TRAVERSING IN-'CORE PROBE SYSTEH LIHITING CONOITION FOR OPERATION 3.3.7.7. The traversing in-core probe system shall be OPERABLE with:

Five movable detectors, drives, and readout equipment to map the core, and

b. Indexing equipment.to allow all five detectors to be calibrated in a common location;-

otherwise: with four traversing in-core probe machines, an inaccessible LPRH string may be calibrated using a traversing in-core probe scan from a symmetri~tring provided that an 'A'ype control rod pattern is in e and that the total core TIP asymmetry is less than tandard deviation).

APPLICABILITY: When the traversing in-core probe is used for:

a. Recalibration of the LPRH de ors, and b." Honitoring the APLHGR, L CPR, or HFLPD.

ACTION:

With 'the traversing in-core system inoperable, suspend use of the system for the above applicable mo ing or calibration functions. The provisions of Specification 3.0.3 ~cM&~are not applicable.

r

, SURVEILLANCE RE UIREHEXTS 4.3.7.7 The traversing in-core probe system shall be demonstrated OPERABLE by normalizing each of the above required detector outputs within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> p'rior to use for the above applicable monitoring or calibration functions.

"Only the detector(s) in the required measurement location(s) are required to be OPERABLE:

WASHINGTON NUCLEAR - UNIT 2 3/4 3-77 Amendment No. 20

INSTRUMENTATION FIRE OETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.9 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3.7.9"1 shall be OPERABLE.

APPLICABILITY: Whenever equipment protected by the fire detection instrument is required to be OPERABLE.

ACTEON:

With th'e number of OPERABLE fire detection instruments in one or more zones:

1. Less than, but more than one-half of, the Total Number of Instruments shown in Table 3.3.7.9"1 for Function A, restore the inoperable Function A instrument(s) to OPERABLE status within 14 days o ithin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol to inspect the zone ith the inoperable instrument(s) at least once per hour.

One less that Total Number of Instruments shown in Table 3.3.7.9" Function B, or one-half or less of the Total Number of Instru gs shown in Table 3.3.7.9-1 for Function A, or with any two oqfFgge adjacent instruments inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a Q watch patrol to inspect the zone(s) with the inoperable inst". (s) at least once per hour.

b. The provisions of Specificatio 3.0. 3 ench&~h are not applicable.

SURVEILLANCE REOUIREMEHTS 4.3..7.9.1 Each of the above required fire,detection instruments which are accessible during unit operation shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST. Fire detectors which are not accessible during unit operation shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIOHAL TEST during each COLO SHUTOOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless. performed in the previous 6 months.

4.3.7.9.2 The NFPA Standard 720 supervised circuits supervision associated with the detector alarms of each of the above required fire detec.ion instruments shall be demonstrated OPERABLE at least once per 6 months.

WASHINGTON NUCLEAR - UNIT 2 3/4 3-79

r 4

INSTRUMENTATION LOOSE-PART DETECTION SYSTEM LIMITIHG CONDITION FOR OPERATION 3.3.7.10 The loose-part detection system shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.,

ACTION:

a~ With one or more loose-part detection system channels inoperable for more than 30 days, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel(s) to OPERABLE status.

b; 'The'rov'isions of Specification 3.0.3~d=~ are not applicable,.

SURVEILLANCE REQUIREMENTS

4. 3.7. 10 Each channel of the loose" detection system shall be demonstrated OPERABLE by per.ormance of a:

CHANNEL CHECK at leas o ce per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, I

.b. CHANNEL FUNCTIONAL+TI5f at least once per 31 days, and C. CHAHNEL CALIBRATION at least once per 18 months.

WASHINGTON NUCLEAR - UNIT 2 3/4 3-83

INSTRUMENTATION RADIOACTIVE LI UIO EFFLUENT MONITORING INSTRUMENTATION 1

LIMITING CONDITION FOR OPERATION 3.3.7. 11 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3.7.11-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3.11. 1.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters described in'he OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABiLITY: At all times.

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel

.alarm/trip setpoint less conservative than required by the above

"'specification, immediately suspend the release of radioactive liquid effluents monitored~ the affected channel or declare the channel inoperable.

b. With less .han he m'ni number of radioactive liquid effluent monitoring instrumentation~anneis OPERABLL, take the ACTION shown in Table 3.3.7. 11-1. Res&ithe inoperable instrumentation to OPERABLE status within the MQ specified in the ACTION or., in lieu of a Licensee Event Report, d% in why this inoperability was not corrected within the time spec in the next Semiannual Radioactive Effluent Release Report.

C. The provisions of Specifications 3+~~ivvt and 6.9.1.9h. are not applicable.

SURVEILLANCE RE UIREMENTS

'.3.7. 11 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7. 11-1.

WASHINGTON NUCLEAR - UNIT 2 3/4 3-84

I ~

lh INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONOITION FOR OPERATION 3.3.7. 12 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3.7. 12-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3. 11.2. 1 are not exceeded. The alarm/trip setpoint of these channels shall be determined in accordance with the methodology and parameters described in the ODCM.

APPLICABILITY: As shown in Table 3.3.7.12-1.

ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, immediately initiate action to suspend the

'release<<of radioactive gaseous effluents monitored by the affected channel or change the setpoint so declare the channel inoperable.

jt is acceptably conservative or

b. With less than the minimum instrumentation nu~

chapels of radioactive gaseous effluent OPERABLE, take the ACTION shown monitoring in Table 3.3.7. 12"1. Rest~the inoperable instrumentation to

A OPERABLE status within th~Re specified in the ACTION or, in lieu of a Licensee Event Rep ~explain why this inoperability was not hr h 'P specified in the next Semiannual Radioactive corrected within the Effluent Release Re The provisions o$ cifications 3.0.3, . and 6.9.1.9b. are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7. 12 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7. 12-1.

WASHINGTON NUCLEAR - UNIT 2 3/4 3"89

,REACTOR COOLANT SYSTEM coMTROLLED cop v LIMITING CONDITION FOR OPERATION (Continued ACTION: (Continued) e) Perform Surveillance Requirement 4.4.1.1.2 is <

if THERMAL POWER 25K""" of RATED THERMAL POWER or the recirculation loop flow in the operating loop's < 10K"*" of rated loop flow.

f) Reduce recirculation loop flow in the operating loop until the core plate bP noise does not deviate from the estab-lished core plate hP noise patterns by more than 100K.

dMp~~ltk 'ply 3.~ Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

" b..e With,no; reactor,:coolant system recirculation loops in operation, immediately initiate measures to place the unit in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

,SURVEILLANCE RE UIREMENTS 4.4.1.1. 1 With one reactor coolant system recirculation loop not in operation, at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> verify that:

a. The recirculation flow control system is in the Local Manual (Position Control) mode, and

b. The volumetric flow rate of the operating, loop is < 41,725 gpm.""

""This value represents the actual volumetric recirculation loop flow which produces lOOX core flow at lOOX THERMAL POWER. This value was determined during the Startup Test Program.

"""Final values were determined during Startup Testing based upon actual THERMAL POWER and recirculation loop flow which will sweep the cold water from the vessel bottom head preventing stratification.

WASHINGTON NUCLEAR " UNIT 2 3/4 4"2 Amendment No. 62

!1 l u I

REACTOR COOLANT SYSTEM 3/4.4. 4 CHEMISTRY LIMITING CONDITION FOR OPERATION 3.4.4 The chemistry of the reactor coolant system shall be maintained within the limits specified in Table 3.4.4-1.

APPLICABILITY: At all times.

ACTION:

In OPERATIONAL CONDITION 1:

With the conductivity, chloride concen.ration or p8 exceeding the limit specified in Table 3.4.4"1 for less than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during one continuous time interval and, for conductivity and chloride concentration, for less han 336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br /> per year, but with the conductivity less than 10 pmho/cm at 25'C and with the chloride. concentration less than 0.5 ppm, this need not be reported to the Commission

2. With the conductivity, chloride concentration or pH exceeding the limit specified in Table. 3.4.4-1 for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> durina one continuous time ihterval or with the conductivity and chloride concentration exceeding the limit specified in Table 3.4.4-3. for more than 336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br /> per year, be in at leas STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

With the conductivity exceeding 10 pmho/cm at 25~C or chloride concentration exceeding 0.5 ppm, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. In OPERATIONAL CONDITIONS 2 and 3 with the conductivi.y, chloride concentration, or pH exceeding the limit specified in Table 3.4.4-1 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLO SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

C. At a'll other times:

With the:

a) Conductivity or pH exceeding the limit specified in Table 3.4.4-1, restore the conductivity and pH to wi hin the limit within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or b) Chloride concentration exceedinc the limit specified in Table 3.4.4-1, restore the chloride, concentration to with-in the limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integri y of the reactor coolant system. Determ.ne that the structural integ-rity of the reactor coolant system remains acceptable for con-tinued operation prior to proceeding to OPERATIONAL CONDITION 3.

2. The provisions of Specification 3.0.3 are not applicable.

WASHINGTON NUCLEAR - UNIT 2 3/4 4-12

'I l f

t p

e REACTOR COOLANTSYSTEM 3/4.4. 7 MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.4.7 TWo main steam line isolation valves (MSIVs) per main steam line shall be OPERABLE with closing times greater than or equal to 3 and less Chan or eoual to 5 seconds.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

With one o'r more MSIVs inoperable:

Maintain at least one MSIV OPERABLE in each affected main steam line that is open and within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, either:

a) Restore the inoperable va)ve(s) to OPERABLE status, or

') lso'late the deactivated ected main steam line by use of in the closed position.

a

2. Otherwise, be in at and in COLD SHUTDOWN 'n HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.,

\

SURVEILLANCE REOUIREMENTS 4.4.7 Each of the above required MSIVs shall be demonstrated OPERABLE by verifying full closure between 3 and 5 seconds when tested pursuant to Specification 4:0.5.

WASHINGTON NUCLEAR - UNIT 2 3/4 4-24

REACTOR COOLANT SYSTEH 3/4.4.8 STRUCTURAL INTEGRITY LIHITING CONDITION FOR OPERATION 3.4.8 The structural integrity of ASHE Code Class 1, 2, end 3 components shall be maintained in accordance with Specification 4.4.8.

APPLICA8ILITY: OPERATIONAL CONOITIONS 1, 2, 3, 4, and 5.

ACTION:

With the structural integrity of any ASHE Code Class 1 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the reactor coolant system temperature more than 50 F above the minimum temperature required by NOT considerations.

b. With the, structural integrity of an~ Code Class 2 component(s) not conforming to the above requir~h s, restore the structural integrity of the affected compo the affected component(s) prio

+) to within its limit of isolate ncreasing the reactor coolant system temperature above 200'~

C. With the stt uctural integr of any ASHE Code Class 3 component(s) not conforming to the abo equirements, restore the structural integrity of the affec component(s) to within its limit or isolat the affected componen from service.

n~M SURVEILLANCE 'RE UIREHENTS 4.4.8 No requirements. other than Specification 4.0.5.

WASHINGTON NUCLEAR -.UNIT 2 3/4 4-25

r 1 fg

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6. 1.3 Each primary containment air lock shall be OPERABLE with:

a. The interlock operable and engaged such that both doors cannot be opened simultaneously, and

b. Both doors closed except when the air lock 'is being used for normal transit entry and exit through the containment, and c.. An overall air lock leakage rate of less than or equal to 0.05 L at P , 34.7 psig.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2" and

a. Viith the interlock mechanism inoperabie:

1. Maintain at least one-operable lock door closed and either return the inter lock to service with~ hours or lock at least one operable air lock door closed.

2. Operation may then conti ~nti 1 the interlock is returned to service provided that one of th @r lock doors is verified locked closed prior to each closing the shield door and at least once per shift while the 'shield doo open.

\

3. Personnel passage through the air lock is permitted provided an individual is dedicated to assure that one operable air lock door remains locked at all times so that both air lock doors cannot be

, opened simultaneously.

b. With one primary containment air lock 'door inoperable:

1. Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERABLE air lock door closed:

2. Operation may then continue until performance of the next required overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed immediately prior to each closing of the shield door and at least once per shift while the shield door is open.

WASHINGTON NUCLEAR " UNIT 2 3/4 6"5 Amendment No. 9

, I C

CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION Continued)

ACTION: (Continued) r

3. Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

C.. Mith the primary containment air lock inoperable, except as a result of an inoperabie air lock door or an inoperable interlock mechanism, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOMN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE RE UIREMENTS

'4:6.1."3 'Each primary containment .lock shall be demonstrated OPERABLE:

a. By verifying interlock ope on (i.e., that only one door in each air lock at

'. can be opened a Prior to using the air loc n Operating Conditions 1, but not required more than once er six months, 2 and 3 I

2. Following maintenance hat cou ect the interlock mechanism.

b. iiithin 72 hours fo'llowing each closing, scent when the air lock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by verifying seal leakage rate less than or equal to 0.025 L when the gap between the door seals is pressurized to 10 psig.

c. By conducting an overall air lock leakage test at P, 34.7 psig and by verifying that the overall air lock leakage rate is within.its limit:

l. At least once per 6 months , and

2. Prior to establishing PRIMARY CONTAINMENT INTEGRITY when maintenance had been performed on the air lock that could affect the air lock sealing capability".

The provisions of Specification 4.0.2 are not applicable.

~

"Exception to Appendix J of 10 CFR 50.

MASHINGTON NUCLEAR UNIT 2 3/4 6"6 Amendment No. 9

t.

~ -

~

GGN780ILILED GGPV' CONTAINMENT SYSTEMS 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3 The primary containment isolation valves and the reactor instrumentation line excess flow check valves shown in Table 3.6.3-1 shall be OPERABLE with isolation times less than or equal to those shown in Table 3.6.3-1, APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

t

a. With one or more of the primary containment isolation valves shown in Table 3.6.3-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:

1. Restore the inoperable valve(s) to OPERABLE status, or

2. Isolate each affected penetration by use of at least one de-activated automatic valve secured in the isolated position,"

or affected penetration by of at least

't'solate each use one closed manual valve or blind flange", and PP4L~P OQ ~ ~44. Ceh)$ 4 PA\AC pro" vided that the affected penetration is isolated in accordance with ACTION a.2. or a.3. above, and provided that the associ-ated system, if applicable, is declared inoperable and the appropriate ACTION statements for that system are performed.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

t With one. or more=-of the reactor instrumentation line excess flow check valves shown in Table 3.6.3-1 inoperable, operation may 'continue and the provisions of Specification+3.0.3 aa~8ak are not applicable provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either;'.

The inoperable valve is returned to OPERABLE status, or

2. The instrument line is isolated and the associated instrument is declared inoperable.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

It "Isolation valves closed to satisfy, these requirements may be reopened on an

'intermittent basis under administrative control.

WASHINGTON NUCLEAR " UNIT 2 3/4 6"19 Amendment No. 31

~

'I

TABLE 3. 6. 3-1 Continued M PRIMARY CONTAINMENT ISOLATION VALVES C) HAXIHUM ISOLATION TIHE VALVE FUNCTION AND NUMBER VALVE GROUP a Seconds

d. Other Containment Isolation Valves (Continued)

I Radiation Honitoring N. A.

PI-EFCX-72f PI-EFCX-73e Transversing Incore Probe System N:A.

TIP-V-6 TIP-V-7,8,9,10,11(e)

TABLE NOTATIONS "But greater than 3 seconds.

(a) See Technical Specification 3.3.2 for the isolation signal(s) which operate each group.

(b) Valve leakage not included in sum of Type B and C tests.

(c) Hay be opened on an intermittent basis under administrative control.

(d) Not closed by SLC actuation signal.

(e) Not subject to Type C Leak Rate Test.

(f) Hydraulic leak test at 38.2 psig.

a (g) Not subject to Type C test. Test per Technical Specification 4.4.3.2.2 (h) Tested as part of Type A test.

(i) Hay be tested as part of Type A test. If so tested, Type C test results may be excluded from sum of c other Type B and C tests..

(j) Reflects closure times for containment isolation only.

(k) During operational conditions 1, 2 8 3 the requirement for automatic isolation'oes not apply to RflR-V-8.

Except that RHR-V-8 may be opened in operational conditions 2 8 3 provided control is returned to the co control room, with the interlocks reestablished, and reactor pressure is less than 135 psig.

I' OSGN7IROILLEB QGS/

CONTAINMENT SYSTEMS f a SECONDARY CONTAINMENT AUTOMATIC ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.5.2 The secondary containment ventilation system automatic isolation valves shown in Table 3.6.5.2-1 shall be OPERABLE with isolation times less than or equal to the times shown in Table 3. 6. 5. 2-1.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3 and ".

ACTION:

With one or more of the secondary containment ventilation system automatic isolation valves shown in Table 3.6.5.2-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> either:

a. Restore the inoperable valves to OPERABLE status, or

b. Isolate each affected penetration by use of at least one deactivated valve secured in the isolation position, or

c. Isolate each affected penetration by use of at least one closed manual valve or blind flange, and QPOPIArt t eW AA QOAJ &eH W C pgkcabke provi ded that the affected penetration is isolated in accordance with ACTION

b. or c. above, and provided that the associated system, if .appli-cable, is declared inoperable and the appropriate ACTION statements for that system are performed.

Otherwise, in OPERATIONAL CONDITION 1, 2, or 3, be in at least'OT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Otherwise, in OPERATIONAL CONDITION *, suspend handling of irradiated fuel in the secondary containment, CORE ALTERATIONS and operations with a potential for draining the reactor vessel. The provisions of Specifica-tion 3.0.3 are not applicable.

- SURVEILLANCE RE UIREMENTS

~.o. 5.2 Facn secondary containment ventilation system automatic isolation valve shown in Table 3.6.5.2-1 shall be demonstrated OPERABLE:

a. Prior to returning the valve to service after maintenance, repair, replacement work is performed on the valve or its associated actuator, control, or power circuit by cycling the valve through at least one complete cycle of full travel and verifying the specified isolation time.

b. During COLD SHUTDOWN or REFUELING at least once per 18 months by verifying that on a containment isolation test signal each isolation valve actuates to its isolation position.

By verifying the isolation time to be within its limit when tested pursuant to Specification 4.0.5 "When irradiated fuel is being handled in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

WASHINGTON NUCLEAR " UNIT 2 3/4 6-39 Amendment No. 31

~CONTROLLED COPY 0 PLANT SYSTEMS 3/4. 7. 5. SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.5 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or'5'microcurie of alpha emitting material shall be free of greater than or equal to 0.005 microcurie of removable contamination.'PPLICABILITY:

At all times.

ACTION:

a. With a sealed source having removable contamination in excess of the above limit, withdraw the sealed source from use and either:

1. Decontaminate and repair the sealed source, or

2. 'Dispose'of the sealed source in accordance with Commission Regulations.

b. The provisions of Specification 3.0.3 and=~M are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.5. 1 Test Re uirements - Each sealed source shall be tested for leakage and/or contamination by:

a. The licensee, or

b. Other persons specifically authorized by the Commission or an Agreement State.

The test method shall have a detection sensitivity of at least 0.005 microcurie per test sample.

4.7.5.2 Test Fre uencies - Each category of sealed sources, excluding startup sources and 'fission detectors previously subjected to core flux, shall be tested at the frequency described below.

Sources in use - At least once per 6 months for all sealed sources containing radioactive material:

1. With a half-life greater than 30 days, excluding Hydrogen 3,. and

2. In any form other than gas.

WASHINGTON NUCLEAR " UNIT 2 3/4 7-16

PLANT SYSTEMS 3/4.7.6 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYSTEM

'LIMITING CONDITION FOR OPERATION 3.7.6.1 The fire suppression water system shall be OPERABLE with:

a. At least two of the three OPERABLE fire suppressionyumps, each with a capacity of 2000 gpm pumping from the circulating water basin, or one 2500 gpm diesel-driven pump pumping from the secondary water supply tank, with their discharge aligned to the fire suppression header.

b. Two separate fire water supplies, with a minimum contained volume of 300,000 gallons in the recirculating water pump house inlet basin and 280,000 gallons in the secondary water supply tank.

c. An OPERABL'E flow path capable of taking suction from the circulating water pump house inlet basin and the secondary water supply tank and transferring the water through distribution piping with OPERABLE sectionalizing control or isolation valves to the yard hydrant curb valves, the last valve ad of the water flow alarm device on each sprinkler or hose stan and the last valve ahead of the deluge valve on each deluge or system required to be OPERABLE per Specifications 3.7.6.2, 3. and 3.7.6.5.

APPLICABILITY: At all times.

a. Mith two 2OOO gpm pumps or the 2501)@m pump and/or one water supply

'"inoperable, r'estore at least two 2000 pumps and the 2500 gpm pump and two fire water supplies to 0 E status within 7 days or provide Specification 3.0.3 ~~~

alternate .backup pump or s are not ap

The prov'isions of cable.

b. With the fire suppression water system otherwise inoperabl'e, establish a backup fire suppression water system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE RE UIREMENTS 4.7.6.1. 1 The fire suppression water system shall be demonstrated OPERABLE:

a. At least once per 7 days by verifying the minimum contained water supply volume.

b. At least once per 31 days on a STAGGERED TEST BASIS by starting each electric motor-driven fire suppression pump and operating it for at least 15 minutes on recirculation flow.

c. At least once per 31 days by veri fying that each valve (manual, power operated, or automatic) in the flow path is in its correct position.

WASHINGTON NUCLEAR - UNIT 2 3/4 7-18

'PLANT SYSTEMS 0

SPRAY AND SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.6.2 The following pre-action and deluge spray and sprinkler systems shall be OPERABLE:

f

a. Radwaste Building:

1. Cable spreading room, elev. 484', system ~65.

2. Cable chase and corridor, elev. 441'o 525', system ~66.

3. Control Bldg. emergency charcoal filters, elev. 525'., system 0>(MA"OV-54A and MMA"DV-548.

4. Control Room, Elev. 501', automatic spriaklers office areas only

b. Diesel Generator Building:

l. ..DG room 1~nd day tank room, elev. 441', system 879.

2. DG .1A day pump. room, elev. 441', system 080.

3. OGvroom 18 ay tank room, elev. 441', system ~81.

4.'G

~

1B day ta p room, elev. 441', system ~82.

5. HPCS OG room a y tank room, elev. 441', system 083.

6. HPCS DG day tank p room, elev. 441', system 484.

c. 'eactor Building:

1. Standby gas treatment system charcoal filters, elev. 572',

system OSGT-OIV-lA-l, OSG IV-1A-2, O'SGT-DIV-1A-3, OSGT-DIV-18-1, I"SGT"OIV-1 and r"SGT-DIV"18-3.

Sump vent filter system chere+ filters, elev. 572',

system KOREA-OV-2A and KOREA-DV-ZB.

APPLICABILITY: Mhenever equipment protected by the spray and/or sprinkler systems is required to be OPERABLE.

ACTION:

a. Mith one or more of the above required spray and/or sprinkler systems inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol.

!he provis ons. of Specification 3.0.3 ~~~ are not apolicable.

"~S:-:!!I=!ON WUCLEAP. - Uf'!: 2

PLANT SYSTEMS HALON SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.6.3 The 18 Halon systems in the PGCC 'units in the control room shall be OPERABLE with the storage tanks having at least 95K of full charge weight and 90K of full charge pressure.

'APPLICABILITY: Mhenever equipment protected by the Halon systems is required to be OPERABLE.

ACTION:

Mith one or more of the above required Halon systems inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a continuous fire watch with backup f re suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire'atch" patrol.

b. The provisions of Specificati 3.0.3~d&~are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.6.3 OPERABLE:

Each of the above req 'alon systems shall be demonstrated

a. At least once p  % days by verifyino that power-operatec+Iv automatic) in the flow path is in each valve (manual, its correct pos i ti on.

b. At least onc er 6 months by verifying Halon storage tank quantity and pressure.

c. At least once per 18 months by:

1. Verifying the system, including associated ventilation system fire dampers and fire door release mechanisms, actuates, manually and automatically, uoon receipt of a silmulated actuation signal, and

2. Performance of a flow test through accessible headers and nozzles to assur e no blockage.

d. At least once per 36 months by verifying Halon storage tank weight.

MASHINGTON NUCLEAR - UNIT 2 3/4 7"23

I I J

PLANT SYSTEMS FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION

3.7.6.4 The fire hose stations shown in Table 3.7.6.4-1 shall be OPERABLE.

APPLICABILITY: Whenever equipment in the areas protected by the fire hose stations is required to be OPERABLE.

ACTION:

a. With one or more of the fire hose stations shown in Table 3.7.6.4-1 inoperable, provide'ated wye(s) on the nearest OPERABLE hose station(s). One outlet of the wye shall be connected to the standard length of hose provided for the hose station. The second outlet of the wye shall be connected to a length of hose sufficient to provide coverage for the area left unprotected by the inoperable hose sta'tion. Where it can be demonstrated that the physical routing of the fire hose would result in a recognizable hazard to operating technicians, plant equipment, or the hose itself, the fire hose shall be stored in a roll at the outlet of the OPERABLE hose station. Signs shall b ounted above the gated wye(s) to identify the proper hose to use. above ACTION shall be accomplished within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if the ino le fire hose is the primary means of fire suppression; otherwis te the additional hose within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. The provisions of Specificat'i 0.3~~~ are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.6.4 Each of the fire hose stations shown in 3.7.6.4-1 shall be demonstrated OPERABLE:

a. At least once per 31 days by a visual inspection of the fire hose stations accessible during plant operation to assure all required equipment is at the station.

b. At least once per 18 months by:

1. Visual inspection of the fire hose stations not accessible during plant operation to assure all required, equipment is at .

'the station.

2. Removing the hose for inspection and reracking, and

3. Inspecting all gaskets and replacing any degraded gaskets. in the couplings.

c., At least once per 3 years by:

1. Partially opening each hose station valve to verify valve OPERABILITY and no tl ow blockage.

2. Conducting a hose hydrostatic test at a pressure of 150 psig or at least 50 psig above the maximum fire main operating pressure, whichever is greater.

WASHINGTON NUCLEAR - UNIT 2 3/4 7" 24

PLANT SYSTEMS YARO FIRE HYORANTS AND HYORANT HOSE HOUSES LIMITING CONDITION FOR OPERATION 3.7.6.5 The yard fire hydrants and associated hydrant hose houses shown in Table 3.7.6.5-1 shall be OPERABLE.

APPLICABILITY: Whenever equipment in the areas protected by the yard fire hydrants is required to be OPERABLE.

ACT IOII:

a. With one or more of the yard fire hydrants or associated hydrant hose houses shown in Table 3.7.6.5-1 inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> have sufficient additional lengths of 2 1/2 inch diameter hose located in an adjacent OPERABLE hydrant hose house to provide service to the unprotected area(s) if the inoperable fire hydrant or associated hydr'ant hose house is the primary means of -fire suppression;

'therwise, provide the additional hose within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. The provisions of Speci ation 3.0.3 an~~ are not applicable.

SURVEILLANCE RE UIREMENTS P+

4.7.6.5 Each of the yard fire hydrants an+ ciated hydrant hose houses shown in Table 3.7.6 '-1 shall be demonstrated OPE At least once per 31 days by visual i tion of the hydrant hose house to assure all required equipment the hose house.

At least once per 6 months, during March, pril or May and during September, October,'or November, by visually inspecting each yard fire hydrant and verifying that the hydrant barrel is dry and that'the hydrant is not damaged.

C. At least once per 12 months by:

1. Conducting a hose hydrostatic test at a pressure of 150 psig or't least 50 psig above the maximum fire main operating pressur'e; whichever is greater.

2. Replacement of all degraded gaskets in couplings.

3. Performing a flow check of each hydrant.

WASHINGTON NUCLEAR UNIT 2 3/4 7-26

V'

~ gt

PLANT SYSTEMS 3/4.'7.7 FIRE-RATED ASSEMBLIES LIMITING CONDITION FOR OPERATION 3.'7.7 All fire-rated assemblies, including walls, floor/ceilings, cable tray enclosures and other fire barriers, separating safety"related fire areas or separating portions of redundant systems important to safe shutdown within a fire area, and all sealing devices in fire"rated assembly penetrations, includ-ing fire doors, fire windows, fire dampers, cable, piping and ventilation duct penetration seals and ventilations seals, shall be OPERABLE.

APPLICABILITY: At al l times.

ACTION:

a ~ With one or more of the above required fire-rated assemblies .and/or sealing devices inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a continuous fire watch on at least one side of the affected assembly(s) and/or sealing device(s) or ver y the OPERABILITY of fire detectors on at least one side of t perable assembly(s) and/or sealing device(s) and establish urly f'ire watch patrol.

b. The provisions of Specifica 3. 0. 3 ~cd=9=k. are not app1 i cab 1 A..

SURVEILLANCE RE UIREMENTS 4.7.7. 1 Each of the above required fire"rated a lies and penetration sealing devices shall be verified OPERABLE at leas e per 18 mohths by performing a visual inspection of:

a. The exposed surfaces of each fire"rated assembly.

fire fire b.

C.

Each window, damper, and associated At least lOX of each type of sealed penetration.

changes in appearance or abnormal degradations are found, a visual

'f hardware.

apparent inspection of an additional 10K, of each type of sealed'penetration,.

shall be made. This inspection process shall continue until a 10K sample with no apparent changes in appearance or abnormal degrada-tion is found. Samples shall be selected such that each penetration seal will be inspected at least once per 15 years.'ASHINGTON NUCLEAR - UNIT 2 3/4 7-28

't I ~ g'I t

F

~ CQNTPOLLrO COP%

ELECTRICAL POWER SYSTEMS, PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION 3.8.4.2 All primary containment penetration conductor 'overcurrent protective devices shown in Table 3 '.4.2-1 shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

a. With one or more of the p rimary contain ment penetration conductor overcurrent protective devices shown in Table 3.8.4.2"1 inoperable, declare the affected system or component inoperable and apply the appropriate ACTION statement for the affected system and:

1. For 6.9 kV circuit breakers, de-energize the 6.9 kV circuit(s) by tripping the associated redundant circuit breaker(s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and verify the redundant circuit breaker to be tripped at least'nce per 7 days thereafter.

'.- For 480 -volt circuit breakers, remove the inoperable circuit breaker(s) from service by removing the fuses within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and verify the fuses associated with the inoperable breaker(s) to be removed at least once per 7 days thereafter.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLO SHUTDOWN within the follgwing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

CpcpagiatJ Aha,y coufhtsc, cop

b. over-current devices in 6.9 kV circuits which have their redundant circuit breakers tripped or to 480 volt circuits which have the fuses asso-ciated with the inoperable circuit breaker removed.

SURVEILLANCE RE UIREMENTS 4.8.4.2 Each of the primary containment penetration conductor overcurrent

.a. 't protective devices shown in Table 3.8.4.2-1 shall be demonstrated OPERABLE:

1.

least once per .18 months:

By verifying that the medium voltage, 6.9 kV, circuit breakers are OPERABLE by selecting, on a rotating basis, at least lOX of the circuit breakers of each voltage level and performing:

a) A CHANNEL CALIBRATION of the associated protective relays, and b) An integrated system functional test which includes simulated automatic actuation of the system and verifying

'that each relay and associated circuit breakers and overcurrent control circuits function as designed.

c) For each circuit breaker found inoperable during these functional tests, an additional representative sample of.

at least 10K of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.

WASHINGTON NUCLEAR " UNIT 2 3/4 8-21

~4 RADIOACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION

3. 11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radio-active materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5'mrems to any organ, and

b. During any calendar year to less than or equal to 3'mrems to the total body and to less than or equal to 10 mrems to any organ.

APPLICABILITY: At al 1 times.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid luents exceeding. any of the above limits, in lieu of

~

a Licensee Report, prepare and submit to the Commission within 30 days, pur to Specification 6.9.2, a Special Report that identifies the e(s) for exceeding the limit(s) and defines the

'corrective aetio at have been taken to reduce the releases and the proposed corr Q actions to be taken to assure that subsequent

~

releases vill be in Wo liance with the above limits. This Special Report shall also inc (1) the results of radiological analyses

'of the dri~king water s and (2) the radiological impact on finished drinking water ies with regard to the requirements of 40 CFR Part 141.

b. The provisions of Specificati 3.0.3wnd~~ are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

WASHINGTON NUCLEAR " UNIT 2 3/4 11-5

<< I RADIOACTIVE .EFFLUENTS LI UID RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste treatment system shall be OPERABLE. The appro-priate portions of the system shall be used to reduce the releases of radio-activity when the projected doses due to the liquid effluent, from each reactor unit, to UNRESTRICTED AREAS (see Figure 5.1-3) would exceed 0.06 mrem to the total body or 0.2 mrem to any organ, in a 31-day period.

e APPLICABILITY: At all times.

ACTION:

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the liquid radwaste treatment system not in operation, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days pursuant to.Specification 6.9.2 a Special Report that includes the following

~

information: 1

~

l. Explanation of why liquid radwaste eing discharged without

~ ~

treatment, identification of any i rable equipment or sub-.

systems, and the reason for the erability,

2. Action(s) taken to restore ~%i operable equipment to OPERABLE status, and

3. Summary description of ion(s) taken to prevent a recurrence.

b. The provisions of Specif'c on 3.0.3 aa~h4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.11.1.3.1 Doses due to liquid releases from-each reactor unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM.

/

4.11.1.3.2 The installed liquid radwaste treatment system shall be demon-.

strated OPERABLE by meeting Specifications 3.11.1.1 and 3.11.1.2.

ts WASHINGTON NUCLEAR

- UNIT 2 3/4 ll"6

0 RADIOACTIVE EFFLUENTS LI UID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in any outside, temporary tanks shall be limited to the limits calculated in the ODCM such that a complete release of the tank contents would not result in a concentra-tion at the nearest offsite potable water supply that would exceed the limits specified in 10 CFR Part 20 Appendix B,Table II.

APPLICABILITY: At al 1 times.

ACTION:

With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents"to within the limit, and describe the events leading to this conditi in the next Semiannual Radioactive Effluent 'Release Report.

I

b. The provieion8 gPSpecifi tati on 3.0.3 mocL&di~are not applicahie.

Py SURVEILLANCE RE UIREMENTS 4.11.1.4 The quantity of radioacts terial contained in each of the above listed tanks shall be determined to hin the above limit by analyzing a representative sample of the tank's co s at least once per 7 days when radioactive materials are being added to he tank.

WASHINGTON NUCLEAR " UNIT 2 3/4 11"7

RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES

.LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrads for and less than or eqbal to 10 mrads for beta radiation and, gamma'adiation

b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

APPLICABILITY'. At al 1 times.

ACTION Mith the calculated air dose. from radioactive noble gases in gaseous effluents exceeding any of the above Event Report, prepare and submit to the lim, in lieu of a Licensee ission within 30 days, pursuant to Specification 6.9.2, a Sp Report that identifies the cause(s) for exceeding the limit( nd defines the corrective actions that have been. taken to red he releases and the proposed corrective actions to be taken to re that subsequent releases will be in compliance with th o limits.

b. The provisions of Specificat' 0. 3 and&~ are not applicable.

SURVEILLANCE RE UIREMENTS 4.11.2.2 Cumulative dose contribu ions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days. P MASHINGTON NUCLEAR - UNIT 2 3/4 11-12

RADIOACTIVE EFFLUENTS f

DOSE - IODINE-131 IODINE-133 TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, .to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:

a.'uring any calendar quarter: Less than or equal to 7.5 mrems to any organ and,

b. During any calendar year: Less than'or equal to'5 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the cf ted dose from the release of iodine-131, iodine-133, tritium, and onuclides in particulate form with half-lives greater than 8 ~ in gaseous effluents

'imits, in lieu ~~Licensee Event Report,exceeding any of the above prepare and submit to the Commission wi~n 0 days, pursuant to Specification 6.9.2, a Special Report that d ifies the cause(s) forfexceeding the limit '.

and defines the corre actions. that have been taken to reduce the releases and the pr ~d corrective actions to be taken to assure that subsequent rOfj@gs will be in compliance with the above limits.

b. The provisions of Specificati 3.0.3 +a~~ are f

not applicable.

SURVEILLANCE RE UIREMENTS

4. 11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

WASHINGTON NUCLEAR - UNIT 2 3/4 11-13 r

RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM sha'll be in operation in either the normal or cha'rcoal bypass mode. The charcoal bypass mode shall not be used unless the offgas post"treatment radiation monitor is OPERABLE as specified in Table 3.3.7.12-1.

APPLICABILITY: Whenever the main condenser steam jet air ejector (evacuation) system is in operation.

ACTION:

With the GASEOUS RADWASTE TREATMENT SYSTEM not used in the normal mode for more than 7 days, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to

'Specification 6.9.2, a Special Report which includes the following information:

Identification of the inoperable eq 0 ent or subsystems and the reason for inoperability,

2. Action(s) taken to restore the ~byrerable equipment to OPERABLE status, and

3. Summary description of ac Ao ops) taken to prevent a recurrence.

b. The provisions of Specificati 3.0.3~~~are not applicable.

SURVEILLANCE RE UIREMENTS 4.11.2 ' The GASEOUS RADWASTE TREATMENT SYSTEM shall be verified to be in operation in either the normal or charcoal bypass mode at least once per 7 days whenever the main condenser steam jet air ejector (evacuation) system is in operation.

WASHINGTON NUCLEAR - UNIT 2 3/4 11-14

l II I

41 I 1 I 1 4

RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.2.5 The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERA8LE and shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent

'releases from each reactor unit to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) when averaged over 31 days would exceed 0.3 mrem to any organ in a 31-day period.

'I APPLICA8ILITY: At all times.

ACTION:

ae With the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than 31 days, or with gaseous waste being discharged without treat-ment and in excess of the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission within .30 days, pursuant to Specifi ion 6.9.2, a Special Report which includes the following inrcormation

l. Identific o~of the inoperable equipment or subsystems, the reason f~ e inoperability, F and

2. Actionis) takenPP~estore the inoperable equipment to OPERABLE status, and

3. Summary description tion(s) taken to prevent a recurrence.

b. The provisions:of Specificat 3.0.3 aach3=~are not applicable.

SURVEILLANCE REOUIREMENTS

4. 11.2.5. 1 Doses due to gaseous release from each reactor unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM.

4. 11.2.5.2 The VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by operating the VENTILATION EXHAUST TREATMENT SYSTEM.'equipment for at least 10 minutes, at least once per 92 days unless the appropriate system has been utilitized to process radioactive gaseous'effluents during the previous 92 days.

~~ m MASHINGTON NUCLEAR - U¹T 2 3/4 11-15

RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.6 The concentration of hydrogen in the main condenser offgas treatment system shall be limited to less than or equal to 4X by volume.

APPLICABILITY: Whenever the main condenser steam jet air ejector (evacuation) system is in operation.

ACTION:

With the concentration of hydrogen in the main condenser offgas treatment system exceeding the limit, restore the concentration to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

b. The provisions of Specification 3.0.3 ~d~~ are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.6 The concentration of hydrogen in the condenser offgas treatment system shall be determined to be .within the ab ,limits by continuously monitoring the waste gases in the main cond offgas treatment system with the hydrogen monitors required OPERABLE b a e 3.3.7. 12-1 of. Specifica-tion 3.3.7. 12.

~b WASHINGTON NUCLEAR - UNIT 2 3/4 11-16

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RADIOACTIVE EFFLUENTS VENTING OR PURGIHG LIMITING CONDITION FOR OPERATION 3.11.2.8 VENTING or PURGING of the Mark II containment drywell shall be through the standby gas treatment system or the primary containment vent and purge system. The first 24.hours of any vent or purge operation shall be through one standby gas treatment system.

APPLICABILITY: Whenever the drywell is vented or purged.

ACTIO H:

'a ~ With the requirements of the above specification not satisfied, suspend all VENTING and PURGING of the drywell.

b. The provisions of Specification 3.0.3 ~~~are not applicable.

SURVEILLANCE RE UIREMENTS 4.11.2.8.1 The containment drywell shall be determined. to be aligned for VENTING or PURGING through the standby gas treatment system or the primary containment vent and purge system within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to start of and at least once per

.12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during VENTING or PURGING of the drywell.

r

4. 11.2.8.2 Prior to use of the purge system through the standby gas treatment system assure that:

a. Both standby gas treatment system trains are OPERABLE whenever the purge system is in use, and

b. Whenever the purge system is in use during OPERATIONAL CONDITION 1 or 2 or 3, only one of the standby gas treatment system trains may be used.

4.11.2.8.3 The containment drywell shall be sampled and analyzed per Table 4. 11-2 of Specification 3. 11.2. 1 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the start of and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during VENTING and PURGING of the drywell .

through other than the standby gas treatment system.

WASHINGTON NUCLEAR - UNIT 2 3/4 11-18

F RADIOACTIVE EFF LUENTS 3/4. 11. 3 SOLID RADIOACTIVE WASTE LIMITIHG CONDITION FOR OPERATION 3.11.3 Radioactive wastes shall be SOLIDIFIED'or dewatered in accordance with the PROCESS CONTROL PROGRAM to meet shipping and transportation requirements during transit, and disposal site requirements when received at the disposal site.

APPLICABILITY: At all times.

ACTION:

a. With SOLIDIFICATION or dewatering not meeting disposal site,and shipping and transportation requirements, suspend shipment of the inadequately processed wastes and correct the PROCESS CONTROL PROGRAM, the procedures and/or the solid waste system as necessary to'revent recurrence.

b. With SOLIDIFICATION or dewatering not performed in accordance with

'he PROCESS'CONTROL PROGRAM, (1) test the improperly processed waste in each c ainer to ensure that requirement it meets burial ground and shipping (2) take appropriate administrative action to prevent recurrence.

c. The provisions o cification 3.0.3 wnd~M are not applicable.

RE UIREMENTS 'URVEILLANCE 4.11.3 SOLIDIFICATION of at leas every tenth batch of each type of

~ representat-;ve test specimen from at leas~

dioac:ive wastes (e. g., filter .sludges, spent resins, evaporator bottoms, bo id solutiohs, and sodium sulfate solutions) shall be verified in accor with the PROCESS CONTROL PROGRAM.

a. If any test specimen fails to verify SOLIDIFICATION; the SOLIDIFICATION of the batch under test shall be suspended until such time as addi-tional test specimens can be obtained, alternative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION. SOLIDIFI-CATION of the batch may then be resumed using the alternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM.

b. If the initial test specimen from a batch'of waste, fails to verify .

~

SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each consecutive batch of the same'type of wet waste until at least three consecutive initial test specimens demonstrate SOLIDIFICATION.

The PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.13, to assure SOLIDIFICATION of subsequent batches of waste.

C. With the installed equipment incapable of mee ing Specification 3.11.3 or declared inoperable, restore the equipment to OPERABLE status or, provide for contract capability to process wastes as necessary to satisfy all applicable transporation and disposal requirements.

WASHINGTON NUCLEAR - UNIT 2 3/4 11"19

RADIOACTIVE EFFLUENTS 3/4. 11. 4 TOTAL. DOSE LIMITING CONDITION FOR OPERATION

3. 11.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and'adiation, fr'om'uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

APPLICABILITY: At all times.

ACTION:

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifica-tion 3. 11. 1. 2. a, 3. 11. l. 2.b, 3. 11. 2. 2. a, 3. 11.2. 2. b, 3. 11.2. 3. a, or

3. 11.2.3.b, calculations shall be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits of Specification 3. 11.4 have been exceeded. If such is the case, in l Report, prepare and submit to the Commg5h

~ of a Licensee Event within 30 days, pursuant to Specification 6.9.2, a Special Reg~Khat defines the corrective action to be taken to reduce subsegegnnn'releases to prevent recurrence of exceeding the above'imits and~ides the schedule for achieving conformance with the above limi~~his Special Report, as defined in 10 CFR 20.405c, shall inclu radiation exposure (dose) to

~n analysis that estimates the MBER OF THE PUBLIC from uranium fuel cycle sources, includin 1 effluent pathways and direct radiation, for the calends~ear that includes the release(s) covered by this report. ~C%hall also describe levels 'of radiation and concentrations of ~aeactive material involved, and the cause of the, exposure levels + concentrations. If the estimated dose(s) exceeds the above limits, and if-the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall'nclude a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

b. The provisions of Specification 3.0.3mnch8=fh4-are not applicable.

SURVEILLANCE RE UIREMENTS

4. 11,.4. 1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 4. 11.1.2, 4. 11.2.2, and

4. 11.2.3, and in accordance with. the methodology and parameters in the ODCM.

4. 11. 4. 2 Cumulative dose contributions from direct radiation from unit opera" tion shall be determined in accordance with the methodology and parameters in the ODCM.

WASHINGTON NUCLEAR - UNIT 2 3/4 11-20

RADIOLOGICAL ENVIRONMENTAL MONITORING LIMITING CONDITION FOR OPERATION Continued)

ACTION: (Continued) locations from which samples were unavailable may then be deleted from the monitoring program. In lieu of a Licensee Event Report and pursuant to Specification 6.9.1.11, identify the'cause of the unavail-ability of samples and identify the new location(s) for obtaining replacement samples in the next Semiannual Radioactive Effluent

'Release Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

d. The provisions of Specification 3.0.3~cd=~are not-applicable.

. SURVEILLANCE RE UIREMENTS 4.12.1 'he radiological environmental monitoring samples shall be collected pursuant to Table 3.12-,1 from the s ecific locations given in the table and figure(s) in .the ODCM, and shall nalyzed pursuant to the requirements of Table 3. 12-1 and the detection ca ities required by Table '4.12-1.

Cp O~

. WASHINGTON NUCLEAR - UNIT 2 3/4 12-2

,EA RAOIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LANG USE CENSUS LIMITING CONOITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16" of the nearest milk animal, the 'nearest residence and the nearest meteorological'ectors garden" of greater than 50 m~ (500 ft2) producing broad leaf vegetation.

APPLICABILITY: At al 1 times.

ACTION:

'a e With a land use census identifying a location(s) that yields a "

calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, in lieu of a Licensee Event Report, identify the new location(s) in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9. l. 11.

b. With a land use census identifying a location(s) that yields a calculated d or dose commitment (via the same exposure pathway) 20K greater t a location from which samples are currently being obtained cordance with Specification 3. 12. 1, add the new location( t the radiological environmental monitoring program within 30 d ' . The sampling location(s), excluding the control station loca having the lowest calculated dose or dose

~

commitment{s), via the this monitoring program

& exposure pathway, may be deleted from October 31 of the year in which this land use census .was conduc . In lieu of a Licensee Event Report and pursuant to Specificati+ . 1. 1 identify the new locationis) in the next Semiannual Radioa Eff/uent Release Report and also include in the report a revise re(s) and table for the OOCM reflecting the new location(s).

c., The provi si ons of Speci f i cation 3.0.3 mach%~ are not applicable.

SURVEILLANCE RE UIREMENTS 4.12.2 The land use census shall be conducted during the growing season at least once per calendar year using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.10 ~

"Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNOARY in each of two different direction sectors with the highest predicted 0/qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 3. 12-1 shall be followed, including analysis of control samples.

WASHINGTON NUCLEAR - UNIT 2 3/4 12-13

~ '

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4. 12. 3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission, that correspond to samples required by Table 3. 12-1.

APPLICABILITY: At al 1 times.

ACTION:

a ~ With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.10.

I

b. The provisions of Specification 3:0.3 amd~~ are not applicable.

SURVEILLANCE RE UIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in the ODCM.

A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1. 10.

WASHINGTON4 NUCLEAR -,UNIT 2 3/4 12-14

BASES REVISION SECTIONS 3.0 AND 4.0

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3/4 LIMITIHG CONDITIONS FOR OPERATION AND SURVEILLANCE RFOUIREMEHTS 3 .0 PPL B BASES S ecifications 3.0. 1 throu h 3.0.4 establ'ish the general requirements applicable to Lsmiting on it ons for peration. These requirements are based on the requirements for Limitinc Conditions for Operation stated in the Code of Federal Regulations, 10 CFR 50.36(c)(2}:

"Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility. Vhen a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specification until the condition can be met."

S ecification 3.0.1 establishes the Applicability statement within each 1n vs ua spec >cation as the requirement for when (i.e., in which OPERATIONAL CONDITIONS or other specified conditions) conformance to the Limitino Conaitions for Operation is required for safe operation of the facility. The ACTION requirements establish those remedial measures that must be taken within specified time limits when the requirements of a Limiting Condition for Operation ar'e not met. It fs not intended that the shutdown ACTION requirements be used as an operational convenience which permits (routine) voluntary removal of a system(s) or component(s) from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.

There are two basic types of ACTION requirements. The first specifies the remedial measures that permit continued operation of the facility which is not further restricted by the time limits of the ACTION requirements. In this case, conformance to the ACTION requirements provides an acceptable level of safety for unlimited continued operation as long as the ACTION requirements continue .o be me". The second type of ACTION requirement specifies a time limit in which conformance to the conditions of the Limiting Condition for Operation must be met. This time limit is the allowable outage time to restore an inoperable system or component to OPERABLE status or for restoring parameters within specified limits. If these actions are not completed within the allowable outage time limits, a shutdown is reauired to place the facility in an OPERATIONAL CONDITIOH or other specified condition in which the specification no longer applies.

The specified time limits of the ACTION requirements are applicable from the point in time it is identified that a Limiting Condition for Operation is not met. The time limits of the ACTION requirements are also applicable when a system or component is removed from service for surveillance testing or investigation of operational problems. Individual specifications may include a specified time limit for the completion of a Surveillance Requirement when B 3/4.0-1

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3 4.0 APPLICABILITY BASES (Con't equipment is removed from service. In this case, the allowable outaae time limits of the ACTION requirements are applicable when this limit expires the surveillance has not been completed. Mhen a shutdown is required tq if comply with ACTION requirements, the plant may have entered an OPERATIONAL CONDITION in which a new specification becomes applicable. In this case, the time limits of the ACTION requirements'ould apply from the point in time that the new specification becomes applicable Condition for Operation are not met.

if the requirements of the Limiting S ecffication 3.0.2 establishes that noncompliance with a specification exists w en the requ rements of the Limiting Condition for Operation are not met and the associated ACTION requirements have not been implemented within the specified time interval. The purpose of this specification is to clarify that (I) implementation of the ACTION requirements within the specified time

~

interval. constitutes compliance with a specification and (2) completion of the remedial measures of the ACTION requirements is not reouired when compliance with a Limiting Condition of Operation is restored within the time interval specified in the associated ACTION requirements.

S ecification 3.0.3 establishes the shutdown ACTION requirements that must be mp emente w en a Limiting Condition for Operation is not met aHd the condition is not specifically addressed by the associated ACTION "requirements.

The purpose of this specification is to delineate the time limits'or placing the unit in a safe shutdown CONDITION when plant operation cannot be maintained within the limits for safe operation dPi'ned by the Limiting Conditions for Operation and its ACTION requirements. It is not intended to be used as an operational c'onvenience which permits (routine) voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or componts being inoperable. One hour is allowed to prepare for an orderly shutdown before initiating a change in plant operation. This time permits the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid. The time limits specified to reach lower CONDITIONS of operation permit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the cooldown capabilities of the facility assuming only the minimum required equipment is OPERABLE. This reduces thermal stresses on components of the primary coolant system and the potential for a plant upset that could challenge safety systems under conditions for which this specification applies.

If remedial measures permitting limited continued operation of the facility under the provisions of the ACTION requirements are completed, the shutdown may be terminated. The time limits of the ACTION requirements are applicable from the point in time there was a failure to meet a Limiting Condition for Operation. Therefore, the shutdown may be terminated if the ACTION requirements have been met or the time limits of the ACTION requirements have not expired, thus providing an allowance for the completion of the required actions.

8 3/4.0-2

3/4. 0 APPLICABILITY BASES Con't)

The time'limits of Specification 3.0.3 allow 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> 'for the plant to be in COLD SHUTDOWN when a shutdown is required during POWER operation. If the plant is in a lower CONDITION of operation when a shutdown is required, the time limit for reaching the next lower CONDITION of operation applies.

However, if a lower CONDITION of -operation is reached in less time than allowed, the total allowable time to reach COLD SHUTDOWN, or other OPERATIONAL CONDITION, is not reduced. For example, if STARTUP is reached in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the time allowed to reach HOT SHUTDOWN is the next ll hours because the total time to reach HOT SHUTDOWN is not reduced from the allowable limit of 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.

Therefore, if remedial measures are completed that would permit a return to POMER operation, a penalty is not incurred by having to reach a lower CONDITION of operation in less than the total time allowed.

The same principle applies with regard to the allowable outage time limits of if compliance the ACTION requirements, with the ACTION requirements for one specification results in entry into an OPERATIONAL CONDITION or condition of operation for another specification in which the requirements of the Limiting Condition for Operation are not met. If the new specification becomes applicable in less time than specified, the difference may be added to the allowab'le 0L'tag hillle 1;mits o. the second spec',i-ication. However, the allowable outage time limits of ACTION requirements for a higher CONDITION of operation may not be used to extend the allowable outage time that is applicable when a Limiting'ondition for Operation is not met in a'lower CONDITION of operation.

The 'shutdown requirements of Specification 3.0.3 do not apply in CONDITIONS 4 and 5, because the ACTION reouirements of individual specifications define the remedial measures to be taken.

S ecification 3.0.4 establishes limitations on a change in OPERATIONAL CONDITIONS when a Limiting Condition for Operation is not met. It precludes placing the facility in a higher CONDITION of operation when the requirements for a Limiting Condition for Operation are not met and continued noncompliance to these conditions would result in a shutdown to comply with the ACTION requirements if a change in COHDITIONS were permitted. The purpose of this specification is to ensure that facility operation is not initiated or that higher CONDITIONS of operation are not entered when corrective action is being taken to obtain compliance with a specification by restoring equipment to OPERABLE status or parameters to specified limits. Compliance with ACTION requirements that permit continued operation of the facility for an unlimited period of time provides an acceptable level of safety for continued operation without regard to the status of the plant before or after a change in OPEPATIONAL CONDITIONS. Therefore, in this case, entry'into an OPERATIONAL CONDITION or other specified condition may be made in accordance with the provisions of the ACTION requirements. The provisions of this specification should not, however, be interpreted as endorsing the failure to exercise good practice in restoring systems or components to OPERABLE status before plant startup.

8 3/4.0-3

~ ~

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5 E4

3 4.0 APPLICABILITY BASES Con't Mhen a shutdown is required to comply with ACTION requirements, the provisions of Specification 3.0.4 do not apply because they would delay placing the facility in a lower CONDITION of operation.

S ecifications" 4.0.1 throu h 4.0.5 establish the general requirements app ica e to urve ance equirements. These requirements are based on the Surveillance Requirements stated in the Code of Federal Regulations, IO CFR 50.36(c)(3):

"Surveillance requirements are requirements relating to test, calibration, or inspection to ensure that the necessary quality of systems and components is maintained, that facility operation will be within'afety limits, and that the limiting conditions of operation will be met."

S ecification 4.0.1 establishes the requirement that surveillances must be per ormed during t e OPERATIONAL CONDITIONS or other conditions for which the requirements of the Limiting Conditions for Operation apply unless otherwise stated in an individual Surveillance Requirement. The purpose of this specification is to ensure that surveillances are performed to verify the operational status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in an OPERATIONAL CONDITION or other specified condition for which the individual Limiting Conditions for Operation are applicable. Surveillance Requirements do not have to be performed when the facility is in an OPERATIONAL CONDITION for which the requirements of the associated Limiting Condition for Opera'tion do not apply unless otherwise specified. The Surveillance Reouirements associated with a Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to the requirements of a specification.

S ecification 4.0.2 establishes the conditions under which the specified time nterva or urve llance Reauirements may be extended. Item a. permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or maintenance activities. Item b.

limits the use of the provisions of item a. to ensure that it is not used repeatedly to extend the surveillance interval beyond that specified. The limits of Specification 4.0.2 are based on engineering judgment and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements. These provisions are sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.

S ecification 4.0.3 establishes the failure to perform a Surveillance equirement wit in the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure 8 3/4.0-4

3/4.0 APPLICABILITY BASES Con't to meet the OPERABILITY reouirements for a Limiting Condition for Operation.

Under the provisions of this specification, systems and components are assumed to be OPERABLE when Surveillahce Requirements have been satisfactorily performed within the specified time interval. However, nothing in this provision is to be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable although still meeting the Surveillance Requirements. This specification also clarifies that the ACTIOH requirements are applicable when Surveillance Requirements have not been completed within the allowed surveillance interval and that the time limits of the ACTION requirements apply from the point in time it is identified that a surveillance has not been performed and not at the time that the allowed surveillance interval was exceeded.

Completion of the Surveillance Requirement within the allowable outage time limits of the ACTION requirements restores compliance with the requirements of Specification 4.0.3. However, this does not negate the fact that the failure to have performed the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, was a violation of the OPERABILITY requirements of a Limiting Condition for Operation that is subject to enforcement action. Further, the failure to perform a surveillance within the provisions of Specification 4.0.2 is a violation of a Technical,:,Specification.

r quiremer,. and is, tl ere ore, a reportable event under the requirements of 10 CFR 50.73(a)(2)(i)(B) because it is a condition prohibited by the plant's Technical Specifications.

If the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or a shutdown is required to comply with ACTION requirements, e.g.,

Specification 3.0.3., a 24-hour allowance is provided to permit a delay in implementing the ACTION requirements. This provides an adequate time limit to complete Surveillance Requirements that have not been performed. The purpose of

. this allowance is to permit the completion of a surveillance before a shutdown would be required to comply with ACTION requirements or before other remedial measures would be required that may preclude the completion of a surveillance.

The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel, the time required to perform the surveillance, and the safety significance of th delay in completing the required surveillance.

This provision also provides a time limit for the completion of Surveillance Requirements that become applicable as a consequence of CONDITION changes imposed by ACTION requirements and for completing Surveillance Requirements that are applicable when an exception to the requirements of Specification 4.0.4 is allowed. If a surveillance is not completed within the 24-hour allowance, the time 1imits of the ACTION requirements are applicable at that time. When a surveillance is performed within the 24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is terminated.

Surveillance Requirements do not have to be performed on inoperable equipment because the ACTION requirements define the remedial measures that apply.

However, the Surveillance Requirements have to be met to demonstrate that inoperable equipment has been restored to OPERABLE status.

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3 4.0 APPLICABILITY BASES Con't)

S ecification 4.0.4 establishes the requirement that all applicable surve ances must be met before-entry into an OPERATIONAL COHDITIOH or other condition of operation specified in the Applicability statement. The purpose of this specification is to ensure that system and component OPERABILITY requirements or parameter limits are met before entry into an OPERATIONAL CONDITION or other specified condition for which these systems and components ensure safe operation of the facility. This provision applies to changes in OPERATIONAL CONDITIONS or other specified conditions associated with plant shutdown as well as startup.

Under the provisions of this specification, the applicable Surveillance Requirements must be performed within the syecified surveillance interval to assume that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage.

Mhen a shutdown is .required to comply with ACTION requirements, the provisions of Specification 4.0.4 do not apply because this would delay placing the facility in a lower CONDITION of operation.

S ecification 4.0.5 establishes the requirement that inservice inspection of SM o e ass I, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a. These requirements apply except when relief has been provided in writing by. the Commission.

This specification includes a clarification of the frequencies for performing

. the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda. This clarification is provided to ensure consistency in surveillance intervals throughout the Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.

Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda. The requirements of Specification 4.0.4 to perform surveillance activities before entry into an OPERATIONAL CONDITION or other specified condition takes precedence over the ASME Boiler and Pressure Vessel Code provision that allows pumps and valves to be tested up to one week after return to normal operation. The Technical Specification definition of OPERABLE does not allow a grace period before a component, which is not capable of performing its specified function, is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision that allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared inoperable.

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