Text

Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements
	ML20151G871
Person / Time
Site:	Seabrook
Issue date:	07/22/1988
From:	; PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	;
Shared Package
ML20151G869	List: ML20151G866; ML20151G871;
References
	NYN-88100, NUDOCS 8807290291
	Download: ML20151G871 (55)
	v • d • e

_ _ _ _ _ _ _ _ _ _ _ _ _

t e ENCLOSURE 1 TO NYN-88100 PROPOSED TECHNICAL SPECIFICATION CHANGES I

8807290291 880722 PDR ADOCK 03000443 P PDC .

I 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS 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 MODES or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements. shall be . net.

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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months action shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in:

a. At least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , 4

b. At least HOT SHUTOOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and

c. At least COLD SHUT 00WN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Where corrective measures are completed that permit operation under the ACTION requirements, the action may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation. Exceptions.to these requirements are stated in the individual specifications.

This specification is not applicable in MODE 5 or 6.

3.0.' Entry i-te an CPERATION^,L "005 r :ther ;p;;ified candition ; hen not be d: un!::: the condition: fer the Li-iting C nditi:n f r Operation ace met withnut en14 m ni a on_pgguie49ne cgnt3 4 ngd 4a th; A[T!gu 7;q j7;;;g;;, 73j; ecovision--sha e4-40t-pr. event-passage-through er t OPERATIONAL "00:5 as requiced-Ao-comply-wi-th-AGTION - r e qu i r ements . - .. Exceptions-to-the:: requir;;;nt; ;r:

Etated 'a th individual pecific: tion:.

fusee r n SEABROOK - UNIT 1 3/4 0-1

f f ki INSERT A 3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made when the conditions for the Limiting Conditions for Operation are not met and the associated ACTION requires a shutdown if they are not met within a specified time. interval. Entry into an OPERATIONAL MODE or specified condition may be made in accordance with AC' TION requirements.when conformance to them permits continued operation of the facility for an unlimited period of time. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual specifications.

i l

i i

e

.,~ ,

APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL HODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Reor:rement.

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

a. A saximum allowable extension not to exceed 25% of the surveillance interval, but

b. The combined time interval for any three consecutive. surveillance intervals shall not exceed 3.25 times the specified surveillance interval.

.rswrz r3

0. 3 "ailure to-peefore-a-Sur-vef!!ance Requir:::nt "ithia the spec 4fied time inter-val-sha14-constitute-a-f-atlure-te :::t the OPER^3ILIT requir:::nt:

'fer e Limiting Conditier for Operatier Eyceptiens te there requirement:

.are-stated-in-the-indtwidual-spec 44tcations _ Surve411=nca Daq"4ramen" de

.not-have-to-be-performed ca inoperable-eqttipment---

-4ror4-Entry-4nto-an-OPERAT-IONAl-H00E-or-other-specified-condit4cn shall not be

'=ede unless-the-Surve441ancs Requirement (s_) associated with +he limiting

. Condition-for Operation has been-performodyithin the stated surveillance inte rval-or-as-othewise-spe c i r i a+

4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, and 3 components shall be applicable as follows:

a. Inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in a.ccordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR Part 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR Part 50, Section 50.55a(g)(6)(i);

SEABROOK - UNIT 1 3/4 0-2

e~ :. i INSERT B 4 . 0 .' 3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a LLaiting Condition for Operation. -The time limits of.the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been

_ performed.' The ACTION requirements may be delayed for up to 24-hours to permit the completion of the surveillance when the allowable outage time limits of the ACTION requ3:ements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Surveillance Requirements do not have to be performed on inoperable equipment.

4.0.4 Entry-into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Requirement (s) associated with a Limiting Condition of Operation has been performed within the stated surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.

o i

0

TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION

o 8

MINIMUM i.

TOTAL NO. CilANNELS CilANNELS APPLICABLE FUNCTIONAL UNIT OF CilANNELS TO TRIP OPERABLE MODES ACTION

[

z U 1. Hanual Reactor Trip 2 1 2 I 2 1

- 2 1 2 .

3g, 4*, S* 10

2. Power Range, Neutron Flux -

' y

a. liigh Setpoint 4 2 3 1, 2 2r/

b. Low Setpoint 4 2 3 1###, 2 2#'

3. Power Range, Neutron Flux 4 2 3 1, 2 2 liigh Positive Rate

4. Power Rar.ge, Neutron Flux, 4 2 3 1, 2 2 liigh Negative Rate S. Intermediate Range, Neutron Flux 2 1 2 1###, 2 3

6. Source Range, Neutron Flux

a. Startup 2 1 2 2## 4

b. Shutdown 2 0 1 3 4, 5 5

c. Shutdown 2 1 2 3 I, 4*, S* 10

7. Overtemperature AT 4 2 3 1, 2 6

8. Overpower AT 4 2 3 1,2! 6

9. Pressurizer Pressure--Low 4 2 3 1** 1)

10. Pressurizer Pressure--liigh 4 2 3 1, 2 6 1)

11. Pressurizer Water Level--liigh 3 2 2 1** 7#

.~..

TABLE 3.3-1 (Continueo) .

REACTOR TRIP SYSTEM INSTRUMENTATION

o 8

^

MINIMUM TOTAL NO. CilANNELS CllANNELS APPLICABLE TUNCTIONAL UNIT OF CllANNELS TO TRIP 4)PERABLE H0 DES ACTION.

d Z 12. Reactor Coolant flow--Low e a. Single Loop (Above P-8) 3/ loop 2/ loop in 2/ loop in 1 7#

any oper- each oper-ating loop ating loop

b. Two Loops (Above P-7 and .3/ loop 2/ loop in 2/ loop 1 7#

below P-8) two oper- each oper-ating loops ating loop

13. Steam Generator Water 4/sta. gen. 2/sta. gen. 3/sta. gen. 1, 2 6 )

Level--Low-Low in any oper- each oper-

!:* ating stm. ating sta.

gen. gen.

14. Undervoltage--Reactor Coolant 4-2/ bus 2-1/ bus 2 on one bus 1** 6 Pumps a/

15. Underfrequency--Reactor Coolant 4-2/ bus 2-1/ bus 2 on one bus 1** 6#'-

Pumps

16. Turbine Trip

a. Low Fluid Oil Pressure 3 2 2 1*** 7#

b. Turbine Stop Valve Closure 4 4 4 1*** 11#

17. Safety Injection Input from ESF 2 1 2 1, 2 9

18. Reactor Trip System Interlocks

a. Intermediate Range Neutron Flux, P-6 2 1 2 2## 8

. TABLE 3.3-3 l ENGINEERED SAFETY FEATURES ACTUATION SYSTEM _ INSTRUMENTATION i

=

0 MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE E FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION M

e 1. Safety Injer. tion (Reactor Trip, Feedwater Isolation, Start Diesel Generators, Phase "A" Isolation, Containmant Ventilation Isolation, Emergency feedwater, Service Water to Secondary Component Cooling Water Isolation, CBA Emergency Fan / Filter R Actuation, and Latching

[. Relay).

M a. Manual Initiation 2 1 2 1,2,3,4 17

b. Automatic Actuation 2 1 2 1,2,3,4 13 Logic and Actuation Relays

c. Containment 3 2 2 1,2,3 14*

Pressure--Hi-1

d. Pressurizer 4 2 3 1, 2, 3# 18 Pressure--Low

e. Steam Line 3/ steam line 2/ steam line 2/ steam line 1, 2, 3# 14*

Pressure--Low any steam line

~

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION x TOTAL NO. CilANNELS MINIMUM CilANNELS APPLICABLE

FUNCTIONAL UNIT . OF CilANNELS TO TRIP OPERABLE H0 DES ACTION I C h 4. Steam Line Isolation (continued)

b. Automatic Actuation 2 1 2 1,2,3 20 Logic and Actuation Relays

c. Containment Pressure-- 3 2 2 1,2,3 14" l11-2

d. Steam Line 3/ steam line 2/ steam line 2/ steam line 1, 2, 3# 14" Pressure-Low any steam line I

~

e. Steam Generator Pressure - Negative 3/ steam line 2/ steam line 2/ steam line 3** 14" ~

[ Rate--liigh any steam u> line S. Turbine Trip

a. Automatic Actuation 2 1 2 1, 2 22 Logic and Actuation Relays

b. Steam Generator 4/sta. gen. 2/sta. gen. 3/sta. gen. 1, 2 18 Water Level--

liigh-liigh (P-14)

6. Feedwater Isolation

a. Steam Generator Water 4/sta. gen. 2/sta. gen. 3/sta. gen. 1, 2 18 Level--liigh-liigh (P-14)

b. 4 2 3 1, 2 18 Low RCS T,yg Coincident 1 with Reactor Trip

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION x TOTAL NO. CHANNELS HINIMUM CilANNELS APPLICABLE

FUNCTIONAL UNIT OF CliANNELS TO TRIP OPERABLE MODES ACTION C

h c. Safety Injection See Item 1. above for all Safety Injection initiating functions y

and requirements.

7. Emergency feedwater

a. Manual Initiation (1) Motor driven pump 1 1 1 1,2,3 21 (2) Turbine driven pump 2 1 2 1,2,3 21

b. Automatic Actuation Logic 2 1 2 1, 2, 3 20 and Actuation Relays

c. Stm. Gen. Water Level--

{ Low-tow

{ Start Motor-Driven Pump 4/stm. gen.- 2/sta. gen. 3/sta. gen. 1,2,3 18 o and Start Turbine -

Driven Pump

d. Safety Injection Start Motor-Driven Pump See Item 1. above for all Safety Injection initiating functions and and Turbine-Driven Pump requirements.

e. Loss-of-Of fsite Power Start Motor-Driven Pump and Turbine- See Item 9 for Loss-of-Of fsite Power initiating functions and Driven Pump requirements.

8. Automatic Switchover to Containment Sump

a. Automatic Actuation 2 1 2 1,2,3,4 13 togic and Actuation Relays

/

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION

o O

MINIMUM TOTAL NO. CilANNELS C!!ANNELS APPLICABLE FUNCTIONAL UNIT OF CilANNELS TO TRIP OPERABLE MODES ACTION

[

b. RWST Level--Low-Low 4 2 3 1,2,3,4 18 Coincident With:

Safety Injection See Item 1. above for all Safety Injection initiating functions and requirements.

9. Loss of Power (Start Emergency feedwater)

a. 4.16 kV Bus ES and E6- 2/ bus 2/ bus 1/ bus 1, 2, 3, 4 18* /

Loss of Voltage .

b. 4.16 kV Bus ES and E6- /

Degraded Voltage 2/ bus 2/ bus 1/ bus 1, 2, 3, 4 18*'

's Coincident with SI

[ See Item 1. above for all Safety Injection initiating functious-g, and requirements.

10. Engineered Safety features Actuation System Interlocks

a. Pressurizer Pressure, 3 2 2 1,2,3 19 P-11

b. Reactor Trip, P-4 2 2 2 1,2,3 21 :

c. Steam Generator Water 4/sta. gen. 2/stm. gen. 3/sta. gen. 1, 2, 3 18*/

Level, P-14

1 a

i INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING FOR PLANT OPERATIONS .

LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels for plant operations shown in Table 3.3-6 shall be OPERABLE with their Alarm / Trip Setpoints within the specified limits. .

APPLICABILITYi As shown in Table 3.3-6.

ACTION:

a. With a radiation monitoring channel Alarm / Trip Setpoint for plant operations exceeding the value shown in Table 3.3-6, adjust the Setpoint to within the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the channel inoperable,

b. With one or more radiation monitoring channels for plant operations inoperable, *.ake the ACTION shown in Table 3.3-6.

c. The provisions of Specifications .0.3 and- M A are not applicable.

SURVEILLANCE REOUIREMENTS

'4.3.3.1 Each radiation monitoring instrumentation channel for plant operations shall Ebe demonstrated GPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and DIGITAL CHANNEL OPERATIONAL TEST for the MODES and at the

. frequencies shown in Table 4.3-3.

l SEABROOK - UNIT 1 3/4 3-36 t

i

-TABLE 3.3-6 RA01ATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS

m. >

E$ MINIMUM c3 CilANNELS CllANNELS APPLICABLE ALARM / TRIP FUNCTIONAL UNIT SETPOINT ACTION

'l TO TRIP / ALARM OPERABLE MODES c= 1. Containment x

il a. Containment - Post LOCA - 1 2 All -< 10 R/h 27 pa Area Monitor

b. RCS teakage Detection

1) Particulate Radioactivity N.A. I 1, 2, 3, 4 N.A. 2. #

2) Gaseous Radioactivity N.A. I 12,3,4 N.A. 2'(#_,

2. Containment Ventilation Isolation

a. On Line Purge Monitor 1 2 1,2,3,4 23 .

~

b. Manipulator Crane Area Monitor 1 2 5, 6 23 ti 3. Main Steam Line 1/ steam line 1/ steam 1, 2, 3, 4 N.A. 27

line

'f 4. Fuel Storage Pool Areas w

'd

a. fuel Storage Building Exhaust Monitor N.A. 1 25

5. Control Room Isolation

a. Air Intake-Radiation Level ****

1) East Air Intake 1/ intake 2/ intake All 24

2) West Air Intake 1/ intake 2/ intake All 24 -

6. Primary Component Cooling Water

a. Loop A 1 1 All <2x '9 c

Hackground

b. Loop B 1 1 All <2x 28 Hackground TABLE NOTATIONS

Two times background; purge rate will be verified to ensure compliance with Specification 3.11.2.1 requirements.

- lwo times background or 15 mR/hr, whichever is greater.

- - With irradiated fuel in the. fuel storage pool areas.

-f **** lwo times background or 100 CPM, whichever.is greaterr

(# The provisions of Specification 3.0.4 are not-applicable. 3

~s _ _..m ..__.

INSTRUMENTATION MONITORING INSTRUMENTATON MOVABLE INCORE OETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The Movable Incore Detection System shall be OPERABLE with:

a. At least 75% of the detector thimbles,

b. A minimum of two detector thimbles per core quadrant, and

c. Sufficient movable detectors, drive, and readout equipment to map these thimbles.

APPLICABILITY: When the Movable Incore Detection System is used for: ,

a. Recalibration of the Excore Neutron Flux Detection System, or

b. Monitoring the QUADRANT POWER TILT RATIO, or N

c. Measurement of FaH, FQ(Z) and Fxy, ACTION:

With the Movable Incore Detection System inoperable, do not use the system for the above applicable monitoring or calibration functions. The provisions of Specifications"3.0.3 ar.d 3.0.' are not applicable.

SURVEILLANCE RE0VIREMENTS (Plant procedures are used to determine that the Movable Incore Detection System is OPERABLE.)

l l

SEABROOK - UNIT 1 3/4 3-40 l

l

. w ,

INSTRUMENTATION MONITORING INSTRUMENTAT*0N SEISMIC INSTRUMENTATION LIMITING CONDITION FOR OPERATION ,

3.3.3.3 The seismic monitoring instrumentation shown in Table 3.3-7 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, prepare and submit a Special Report to the Commission pursuant to Specification 6.8.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrument (s) to OPERABLE status.

/

b. The provisions of Specifications'3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.3.1 Each of the above required seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALI-BRATION, and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-4.

4.3.3.3.2 Each of the above required seismic monfiaring 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and a CHANNEL CALIBRATION performed within 30 days following the seismic event. Data shall be retrieved from actuated instruments and analyzed to determine the magnitude of the vibratory ground motion. A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.8.2 within 14 days describing the magnitude, frequency spectrum, and resultant effect upon facility features important to safety.

SEABROOK - UNIT 1 3/4 3-41

.., . . ~

INSTRUMENTATION HONITORING INSTRUMENTATION METEOROLOGICAL INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.4 The meteorological monitoring instrumentation channels shown in Table 3.3-8 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

a. With one or more required meteorological monitoring channels inoperable for more than 7 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.8.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status,

b. The provisions of Specificationr#3.0.3 :nd 2.0.^ are not applicable.

SURVEILLANCE RE0VIREMENTS 4.3.3.4 Each of the meteorological monitoring instrumentation channels shown in Table 3.3-8 shall be demonstrated OPERABLE by the performance of:

a. A Oaily CHANNEL CHECK, and

b. A Semiannual CHANNEL CALIBRATION i

4 SEABROOK - UNIT 1 3/4 3-44 .

- - - - --- - -w. - m.- - e- y m.-, rm -

i

. .- l INSTRUMENTATION MIITORINGINSTRUMENTATION REMOTE SHUTOOWN SYSTEM LIMITING CONDITION FOR OPERATION 3.3.3.5 The Remote Shutdown System transfer switches, power, controis and monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

With the number of OPERABLE remote shutdown monitoring channels less

. than the Minimum Channels OPERABLE as required by Table 3.3-9, restore the inoperable channel (s) to OPERABLE status within 7 days, or be in HOT SHUT 00WN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. With the number of OPERABLE remote shutdown monitoring channels less than the Total Number of Channels as required by Table 3.3-9, within 60 days restore the inoperable channel (s) to OPERABLE status or, pursuant to Specification 6.8.2, submit a Special Report that defines the corrective action to be taken.

With one or more Remote Shutdot1 System transfer switches, power, or control circuits inoperable, restore the inoperable switch (s)/

circuit (s) to OPERABLE status within 7 days, or be in HOT STAN0BY within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

d. TM provision: Of Spe:ffication 3.0.t cre not applic 21e.

SURVEILLANCE REOUIREMENTS 4.3.3.5.1 Each remote shutdown monitoring instrumentation channel in Table 3.3-9 shall be demonstrated OPERABLE:

a. Every 31 days by performance of a CHANNEL CHECK, and

b. Every 18 months by performance of a CHANNEL CALIBRATION.

4.3.3.5.2 Each Remote Shutdown System transfer switch, power and control circuit listed in Table 3.3-9, including the actuated components, shall be demonstrated OPERABLE at least once per 18 months.

~

~ _ _ __

The provisions of Specification 3.0.4 are not applicable.

~- _ _ _ ..

SEABROOK - UNIT 1 3/4 3-46 I

i INSTRUMENTATION MONITORING INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 The accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a. With the number of OPERABLE accident monitoring instrumentation channels less than the Total Number of Channels shown in Table 3.3-10, restore the inoperable channel (s) to OPERABLE status within 7 days, or be in at least HOT STAN0BY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTOOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.* With the number of OPERABLE accident monitoring instrumentation channels except the containment atmosphere-high range radiation monitor, less than the Minimum Channels OPERABLE requirements of Table 3.3-10, restore the inoperable chanael(s) to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTCOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

c. With the number of OPERABLE channels for the containment Post-LOCA high range area monitor less than required by the Minimum Channels OPERABLE requirements, initiate an alternate method of monitoring the appropriate parameter (s), within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and either restore the inoperable channel (s) to OPERABLE status within 7 days or prepare and submit a Special Report to the Commission, pursuant to Specifi-cation 6.8.2, within 14 days that provides actions taken, cause of the inoperability, and the plans and schedule for restoring the channels to OPERABLE status.

d. The-provisions-of-Spec 4f-icat-forr3.0. 4 ers---r.ct applicabis.

SURVEILLANCE RE0VIREMENTS 4.3.3.6 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE:

a. Every 31 days by performance of a CHANNEL CHECK, and

b. Every 18 months by performance of a CHANNEL CALIBRATION.

~ _

The provisions of Specification 3.0.4 are not applicable SEABROOK - UNIT 1 3/4 3-49 1

INSTRUMENTATION MONITORING INSTRUMENTATION RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 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 paranters in the OFFSITE DOSE CALCULATION MANUAL (00CM). .

ADPLICABILITY: 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 by the affected channel, or declare the channel inoperable.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12. Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semi-annual Radioactive Effluent Release Report pursuant to Specifica-tion 6.8.1.4 why this inoperability was not corrected in a timely manner.

c. The provisions .of Specifications 3.0.3 and 3.0.1, are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-5.

SEABROOK - UNIT 1 3/4 3-55

o . .

INSTRUMENTATION HONITORING INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUEN'T MONITORING INSTRUMEN7ATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specifications 3.11.2.1 and 3.11.2.5 are not exceeded.

The Alarm / Trip Setpoints of these channels meeting Specification 3.11.2.1 shall be determined and adjusted in accordance with the methodology and parameters in the 00CN.

APPLICABILITY: As shown in Table 3.3-13.

ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable.

b. With the number of OPERABLE radioactive gaseous effluent monitoring instrumentation channels less than the Minimum Channels OPERABLE, take the ACTION shown in Table 3.3-13. Restore the inoperable instrumentation to OPERABLE status within 30 days or, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report pursuant to Specification 6.8.1.4 why this inoperability was not corrected in a timely manner.

c. The provisions of Specifications T.0.3 d 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.10 Eacn radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-6.

SEABROOK - UNIT 1 3/4 3-60

REACTOR COOLANT SYSTEM PRESSURE / TEMPERATURE LIMITS OVERPRESSURE PROTEC',* ION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.9.3 At least one of the following Overpressure Protection Systems shall be OPERABLE:

a. Two residual heat removal (RHR) suction relief valver each with a setpoint of 450 psig t 3%, or

b. Two power-operated relief valves (PORVs) with lift setpoints that vary with RCS temperature which do not exceet the limit established in Figure 3.4-4, or

c. The Reactor Coolant System (RCS) depressurized with an RCS vent of greater than or equal to 1.58 square inches.

APPLICABILITY: MODE 4 when the temperature of any RCS cold leg is less than or equal to 329*F; HODE 5 and MODE 6 with the reactor vessel head on.

ACTION:

a. With one PORV and one RHR suction relief valve inoperable, either restore two PORVs or two RHR suction relief valves to OPERABLE status within 7 days or depressurize and vent the RCS through at least a 1.58-square-inch vent within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ,

b. With both PORVs and both RHR suction relief valves inoperable, depressurize and vent the RCS through at least a 1.58-square-inch vent within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

c. In the event the PORVs, or the RHR suction relief valves, or the RCS vent (s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.8.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs, or the RHR suction relief valves, or RCS vent (s) on the transient, and any corrective action necessary to prevent recurrence.

<. The prcvf:fon: ef Specification 3.0.' are-net applic M e.

SEABROCK - UNIT 1 3/4 4-34

j REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.4.10 The structural integrity of ASME Code Class 1, 2, and 3 components

-shall be maintained in accordance with Specification 4.4.10.

APPLICABILITY: All MODES.

ACTION:

a. With the structural integrity of any ASME 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 any ASME Code Class 2 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 above 200*F.

c. With the structural integrity of any ASME Code Class 3 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) from service.

d. T h e- p ro v i s4 o n s-o f--S p e c444c a tio n-3r0,4-a re-not-app 44 ca ble .

SURVEILLANCE REQUIREMENTS 4.4.10 In addf tion to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.

SEABROOK - UNIT 1 3/4 4-37

1 EMERGENCY CORE COOLING SYSTEMS ACCUMULATORS SHUT 00WN LIMITING CONDITION FOR OPERATION 3.5.1.2 Each reactor coolant system accumulator isolation valve shall be shut with power removed from the valve operator.

APPLICABILITY: H0 DES 4* and S.

ACTION:

,Fr With one or more accumulator isolation valve (s) open and/or power available to the valve operator (s), immediately close the accumulator isolation valves and/or remove power from the valve operator (s).

-b. khe-prods 4cns-of-Spedf4catien 3.0.' are net applic3Me-fer :ntry into-NOCE ' f ree *)DE-3.

SURVEILLANCE REQUIREMENTS 4.5.1.2 Each accumulator isolation valve will be verified shut with power removed from the valve operator at least once per 31 days.

Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to entry into MODE 3 from MODE 4 and if pressurizer pressure is greater than 1000 psig, each accumulator isolation valve shall be open as required by Specification 3.5.1.1.a.

SEABROOK - UNIT 1 3/4 5-3 ,

4

--. , -- g _

CONTAINHENT SYSTEMS PRIMARY CONTAINMENT CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION ,_ ,,

. . : s_.

3.6.1.3 Each containment air lock shall be OPERABLE with:

a. Both doors closed except when the air lock is being used for normal transit entry and exit through tne containment, then at least one air lock door shall be closed, and

b. An overall air lock leakage rate of less than or equal to 0.05 L a at P,, 49.6 psig.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a. With one 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 at least once per 31 days,

3. Otherwise, be in at least HOT STANOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months /'end.

4--The-prowMons-of-Spec 4f4eation 3ror4-are-not-4pp44 cable.

b. With the containment air lock inoperable, except as the result of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANOBY within the riext 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Except during entry to repair an inoperable inner door, for a cumulative timt not to exceed I hour per year.

SEABROOK - UNIT 1 3/4 6-7

y ,

3/4.7 PLANT SYSTEMS <

3/4.7.1 TURBINE CYCLE SAFE.TY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line Code safety valves associated with each steam generator shall be OPERABLE with lift settings,as specified in Table 3.7-2.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

af With four reactor coolant loops and associated steam generators in operation and with one or more main steam line Code safety valves inoperable, operation in MODES 1, 2, and 3 may proceed, provided that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either the inoperable valve is restored to OPERABLE status or the Power Range Neutron Flux High Trip Setpoint is reduced per Table 3.7-1; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

t. The-prov4'Aons-of-Spec 4f4eation-3.O.' :r: not appl!: 210.

j'IRVEILLANCE REQUIREMENTS 4.7.1.1 No additional requirements other than those required by Speci-fication 4.0.5.

l l

l i

i SEABROOK - UNIT 1 3/4 7-1

.. p ,

PLANT SYSTEMS 3/4.7.8 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION ._.

3.7.8 Each sealed source containing radioactise material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 microcurie of removable contamination.

APPLICA8ILITY: At all times.

ACTION:

a. With a sealed soue.e having removable contamination in excess of the above -limits, irsediately 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 Specifications #3.0.3 .ad 3.0.4 are not applicable.

SURVEILLANCE REQUIRLMENTS 4.7.8.1 Test Requirements - 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 Agreecant State.

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

4.7.8.2 Tes'. Frequencies - Each cater 1ry of sealed sources (excluding l startup sources and fission detectors ya eviously subjected to core flux) shall be tested at the frequency described bePw.

a. Sources in use - At least once per 6 months for all sealed sources L containing radioactive materials:

l l

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

end

2. In any form other than gas.

e SEABROOK - UNIT 1 3/4 7-19 I

e PLANT SYSTEMS 3/4.7.10 AREA TEMPERATURE MONITORING LIMITING CONDITION FOR OPERATION 3.7.10 The temperature of each area shown in Table 3.7-3 shall not be exceeded for more than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or by more than 30'F.

APPLICABILITY: Whenever the equipment in an affected area is required to be OPERABLE.

ACTION:

a. With one or more areas exceeding the temperature limit (s) shown in Table 3.7-3 for more than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , prepare and submit to the Commission within 30 days, pursuant to Specification 6.8.2, a Special Report that provides a record of the cumulative time ano the amount by which the temperature in the affected area (s) exceeded the limit (s) and an analysis to demonstrate the continued OPERABILITY of the affected equipment. The provisions of Specifi-cationt*3.0.3 :nd 2.0.* are not applicable.

With one or more areas exceeding the temperature limit (s) shown in i

b.

Table 3.7-3 by more than 30*F, prepare and submit a Special Report as required by ACTION a. above and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either restore the area (s) to within the temperature limit (s) or declare the equip-l ment in the affected area (s) inoperable.

SURVEILLANCE REQr!REMENTS 4.7.10 The temperature in each of the areas shown in Table 3.7-3 shall be determined to be within its limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SEABROOK - UNIT 1 3/4 7-22

9 ELECTRICAL POWER SYSTEMS ELECTRICAL EQUIPMENT PROTECTIVE DEVICES CONTAINMENT PENETRATION CCN00CTOR OVERCURRENT PROTECTIVE DEVICES AND PROTECTIVE DEVICES FOR CLASS IE POWER SOURCES CONNECTED TO NON-CLASS IE CIRCUITS LIMITING CONDITION FOR OPERATION 3.8.4.2 Each containment penetration conductor overcurrent protective device and each protective device for Class IE power sources connected to non-class IE circuits shall be OPERABLE.

APPLICABILITf: MODES 1, 2, 3, 4, 5,* and 6.*

ACTION:

a. With one or more of the containment penetration conductor overcurrent pro-tective device (s) inoperable:

1) Restore the protective device (s) to OPERABLE status or deenergize the circuit (s) by tripping the associated circuit breaker or racking out or removing the inoperable protective device within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , declare the affected system or component inoperable, and verify the circuit breaker to be tripped or the inoperable protective device to be racked out or removed at least once per 7 days thereafter; Se g r a v i s i ons-o f-Spee#icet4cn-3r0r4-a re-no t-ap p44 c able-to-ove r t u r r e nt devices in circuits-which-have-their-circult-breakers-tripped,-or their-inoperatrie-protect 49e-devices ~ racked-outr-or-removed; or

2) Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With one or more of the Class IE power source protective device (s) inoper- -

able, restore a protective device (s) to OPERABLE status or deenergize the circuit (s) oy tripping the ciri.uit breaker or racking out or removing the inoperable protective device within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , deleare the affected com-

' ponent inoperable, and verify the circuit breaker to be tripped or the inoperable protective device to be racked out or removed at least once per l

7 days thereafter(,the-prov4s4ons-of-SpecWication-3ror4-are-not-applicat>1e

-to-overcurrent--devices-4n-circuits-which-have-their-circuit breakers t 4pped,-or-their-inoperable-protective-dev4ces-racked-outar-removed.

SURVEILLANCE REQUIREMENTS 4.8.4.2 Each containment penetration conductor overcurrent and Class IE power i source protective device shall be demonstrated OPERABLE:

a. At least once per 18 months:

! 1) By verifying that the medium voltage 13.8-kV and 4.16-kV circuit I breakers are OPERABLE by selecting, on a rotating basis, at least one of the circuit breakers, and performing the following:

1

0nly for Class IE power source protective devices.

SEABROOK - UNIT 1 3/4 8-21

REFUELING OPERATIONS 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE AREAS '

LIMITING CONDITION FOR OPERATION 3.9.7 Loads in excess of 2100 pounds shall be prohibited from travel over fuel assemblies in the storage pool.

APPLICABILITY: With fuel assemblies in the storage pool.

ACTION:

a. With the requirements of the above specification not satisfied, place the crane load in a safe condition.

b. The provisions of SpecificationsIO.3 and-3r0:4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.7 Crane interlocks that prevent crane travel with loads in excess of 2100 pounds over fuel assemblies shall be demonstrated OPERABLE within 7 days prior to crane use and at least once per 7 days thereafter during crane operation.

SEABROOK - UN'IT 1 3/4 9-7

s REFUELING OPERATIONS 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM

. LIMITING CONDITION FOR OPERATION 3.9.9 The Containment Purge and Exhaust Isolation System shall be OPERABLE.

APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within the containment.

ACTION:

a. With the Containment Purge and Exhaust Isolatfor. System inoperable, close each of the purge and exhaust penetrations providing direct access from the containment atmosphere to the outside atmosphere.

b. The provisions of Specifications #3 IO.3 :nd 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.9 The Containment Purge and Exhaust Isolation System shall-be demonstrated OPERABLE within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to the start of and at least once per 7 days during CORE ALTERATIONS by verifying that containment purge and exhaust isolation occurs on manual initiation and on a High Radiation test signal from each of the manipulator crane area radiation monitoring instrumentation channels.

e i

f I

SEABROOK - UNIT 1 3/4 9-10

l li; REFUELING OPERATIONS 3/4.9.11 WATER LEVEL - STORAGE POOL LIMITING CONDITION FOR OPERATION 3.9.11 At least 23 feet of water shall be maintained over the top of irradiated fuel assemblies seated in the storage racks.

APPLICABILITY: Whenever irradiated fuel assemblies are in the storage pool.

ACTION:

a. With the requirements of the above specification not satisfied, suspend all movement of fuel assemblies and crane operations with' loads in the fuel storage i.reas and restore the water level to within its limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b. The provisions of Specifications #3.0.3 and-3ror4-are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.11 The water level in the storage pool shall be determined to be at least its minimum required depth at least once per 7 days when irradiated fuel assemblies are in the fuel storage pool.

SEABROOK - UNIT 1 3/4 9-12

REFUELING OPERATIONS 3/4.9.12 FUEL STORAGE BUILDING EMERGENCY AIR CLEANING SYSTEM LIMITING CONDITION FOR OPERATION 3.9.12 Two independent trains of the Fuel Storage Building Emergency Air Cleaning System shall be OPERABLE whenever irradiated fuel is in the storage pool and shall be OPERA 8LE with one train operating during fuel movement.

APPLICABILITY: Whenever irradiated fuel is in the storage pool.

ACTION:

a. With one train of the Fuel Storage Building Emergency Air Cleaning System inoperable, fuel movement within the storage pool or crane operation with loads over the storage pool may proceed provided the OPERABLE train of the Fuel Storage Building Emergency Air System is capable of being powered from an OPERABLE emergency power source and is in operation and discharging through at least one train of HEPA filters and charcoal adsorbers,

b. With no trains of the Fuel Storage Building Emergency Air Cleaning System OPERABLE, suspend all operations involving movement of fuel within the storage pool or crane operation with loads over the storage pool until at least one train of the Fuel Storage Building Emergency Air Cleaning System is restored to OPERABLE status and is in operation.

c. The provisions of Specifications #3.0.3 = d 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.12 The above required trains of the fuel Storage Building Emergency Air Cleaning System shall be demonstrated OPERABLE:

a. 'At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 continuous hours with the heaters operating;

b. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone communicating with the system by:

SEABROOK - UNIT 1 3/4 9-13

m RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each 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 arems to the whole 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 whole body and to less than or equal to 10 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.8.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b. The provisions.of Specifications [.0.3 and-ar0r4-are not applicable.

SURVEILLANCE REQUIREMENTS l

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 l with the methodology and parameters in the 00CM at least once per 31 days.

l l

SEABROOK - UNIT 1 3/4 11-2

'e e RADI0 ACTIVE EFFLUENTS LIQUID EFFLUENTS LIQUID RA0 WASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.1.3 The Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be used to "educe releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see Figure 5.1-3) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period.

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 which could reduce the radioactive liquid waste dis-charged not in operation, prepare and submit to the Commission within 30 days, pursuant to Specification 6.8.2, a Special Report that includes the following information:

1. Explanation of why liquid radwaste was being discharged without treatment, idantification of any inoperable equipment or subsystems, and the reason for the inoperability,

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

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

b. TheprovisionsofSpecifications'$'.0.3.and-3r0r4arenotapplicable.

S')RVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall oe projected at least once per 31 days in accordance with the methodology and parameters in the 00CM when Liquid Radwaste Treatment Systems are not being fully utilized.

4. 11.1.3.2 The installed Liquid Radwaste Treatment System shall be considered OPERABLE by meeting Specifications 3.11.1.1 and 3.11.1.2.

SEABROOK - UNIT 1 :/4 11-3

RADIOACTIVE EFFLUENTS LIQUID EFFLUENIS LIQUID N0 LOUP TANK 5*

LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radios:.;tive material contained in each temporary unprotected outdoor tank shall be limited to less than or equal te 10 Curies, excluding tritium and dissolved or entrained noble gases:

APPLICABILITY: At all times.

ACTION:

a. With the. quantity of radioactive material in any temporary unprotected-outdoor tank exceeding the above limit, immediately suspend all addi-tions of radioactive material to the tank, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Re-port, pursuant to Specification 6.8.1.4.

b. The provisions of Specificationsi.0.3 and-3r0 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each temporary unprotected outdoor tank shall be determined to be within the above limit by analyzing a representative sample of the tank's contents,at least once per 7 days when radioactive materials are being added to the tank.

"Tanks included in this specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the Liquid R:dwaste Treatment System.

f f

SEABROOK - UNIT 1 3/4 11-4 f

1 1

r A o RADIOACTIVE EFFLUENTS GASEOUS 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 unit, to areas at and beyor.d the SITE BOUNDARY (see Figure 5.1-1) shall be limited to the following:

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

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

APPLICABILITY: At all times.

ACTION

, a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.8.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b. The provisions of Specifications # 3'.0.3 and-6 Or4- are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dosc contributions for the current calendar quarter and current calendar year for noble sses shall be determined in accordance with the methodology and parameters in the 00CM at least once per 31 days. .

SEABR00X - UNIT 1 3/4 11-6

a RADIOACTIVE EFFLUENTS GASEOUS EFFLUENTS DOSE - IODINE-131, IODINE-133, TRITIUM, AND RADI0 ACTIVE MATERIAL IN PARTICULATE FORM LIMITING CONDITION FOR OPERATION ,,,

3.11.2.3 The dose to a HEMBER 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 unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) shall be limited to the following:

a. During 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 15 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit the the Commission within 30 days, pursuant to Specification 6.8.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b. The provisions of Specificationd0.3 -and-3r0A are not applicable.

SURVEILLANCE REQUIREMENTS 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 00CM at least once per 31 days.

SEABROOK - UNIT 1 3/4 11-7

~.

w .

l RADIOACTIVE EFFLUENTS GASEOUS EFFLUENTS GASEOUS RA0 WASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.2.4 The VENTILATION EXHAUST TREATMENT SYSTEM and the GASEOUS RA0 WASTE TREATMENT SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at and be-yond the SITE BOUNDARY (see Figure 5.1-1) would exceed:

a. 0.2 mrad to air from gamma radiation, or

b. 0.4 mrad to air from beta radiation, or

c. 0.3 r.3, to any organ of a MEMBER OF THE PUBLIC.

APPLICABILITY: At all times.

ACTION:

a. With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.8.2, a Special Report that includes the following information:

1. Identification of any inoperable equipment or subsystems, and the reason for the inoperability,

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

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

b. The provisions of Specificationsh.0.3 and-Sr0-4-are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in l

accordance with the methodology and parameters in the 00CM when Gaseous Radwaste Treatment Systems are not being fully utilized.

4.11.2.4.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM and GASEOUS I RA0 WASTE TREATMENT SYSTEM shall be considered OPERABLE by meeting Specifica-j tions 3.11.2.1 and 3.11.2.2 or 3.11.2.3.

l l

SEABROOK - UNIT 1 3/4 11-8

RADI0 ACTIVE EFFLUENTS GASEOUS EFFLUENTS EXPLOSIVE GAS MIXTURE - SYSTEM LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the GASEOUS RADWASTE . TREATMENT SYSTEM shall be limited to less .than or equal to 2% by volume.

APPLICABILITY: At all times.

ACTION:

a. With the concentration of oxygen in the GASEOUS RADWASTE TREATMENT SYSTEM greater than 2% by volume, reduce the oxygen concentration to the above limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months unless the hydrogen concentration is verified to be less than 4% by volume.

b. The provisions of SpecificationsIO.3.and-3-0-4 are not ' applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5 The concentration of hydrogen or oxygen in the GASEOUS RA0 WASTE TREAT-MENT SYSTEM shall be determined to be within the above limit by continuously monitoring the waste gases in the GASEOUS RADWASTE TREATHENT SYSTEM with the hydrogen or oxygen monitors required OPERABLE by Table 3.3-13 of Specificatian 3.3.10.

t l

l i SEABROOk - UNIT 1 3/4 11-9 f

l

., y . l RADI0 ACTIVE EFFLUENTS 3/4.11.3 SOLIO RADIOACTIVE WASTES LIMITING CONDITION FOR OPERATION 3.11.3 Radioactive wastes shall be SOLIDIFIED or dewatered in accordance with the PROCESS CONTROL PROGPAM 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 prevent recurrence,

b. With SOLIDIFICATION or dewatering not performed in accordance with the PROCESS CONTROL PROGRAM, test the improperly processed waste in each container to ensure that it meets burial ground and shipping requirements and sake appropriate administrative action to prevent recurrence.

c. The provisions of Specifications v3.0.3 4r4 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.3 For cement SOLIDIFICATION of at least one representative test speci-men from at least every tenth batch of each type of wet radioactive wastes (e.g., filter sludges, spent resins, evaporator bottoms, beric acid solutions, and sodium sulfate solutions) shall be verified in accordance 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 additional test specimens can be obtained, alternative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION. SOLIDIFICATION 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 6.12, to assure SOLIDIFICATION of subsequent batches of waste; and SEABROOK - UNIT 1 3/4 11-10

.. , +

RA0!0 ACTIVE 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 to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limitad to less than or equal to 75 areas.

1 APPLICABILITY: At all tit?s.

ACTION:

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifi-cation 3.11.1.2a., 3.11.1.2b., 3.11.2.2a., 3.11.2.2b., 3.11.2.3a., or

3.11.2.3b., calculations shall be made including direct radiation contributions from the units and from outside storage tanks to deter-mine whether the above limits of Specification 3.11.4 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Specification 6.8.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits.

This Special Report, as defined in 10 CFR 20.405(c), shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes ,

the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition result- ,

ing in violation'of 40 CFA Part 190 has not already been corrected, '

the Special Report shall include a request for a variance in accor-dance with the provisions of 40 CFR Part 190. Submittal of the report

,it considered a timely request, and a variance is granted until staff action on the request is complete.

b. The provisions of Specificationr#3.0.3 and-3ror4 are not applicable.

I

! SURVEILLANCE REQUIREMENTS I

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 00CM.

4.11.4.2 Cumulative dose contributions from direct radiation from the units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in the 00CM. This requirement is applicable only under conditions set 'forth in ACTION a. of Specification 3.11.4.

SEABROOK - UNIT 1 3/4 11-12 i

RA0!0 LOGICAL ENVIRONMENTAL MONITORING MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 (Continued)

ACTION:

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by the Radiological Environ-mental Monitoring Program (REMP), identify specific locations for obtaining replacement samples and add them within 30 days to the REMP given in the 00CM. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Specification 6.13, submit in the next Semiannual Radioactive Ef-fluent Release Report documentation for a change in the 00CM including a revised figure (s) and table for the 00CM reflecting the new loca-tion (s) with supporting information identifying the cause of the un-availability of samples and justifying the selection of the new loca-tion (s) for obtaining samples.

//

d. The provisions of Specificationr' 3.0.3 e-d 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to the REMP from the specific locations given in the table and figure (s) in the 00CM, and shall be analyzed pursuant to the requirements of and the detection capabilities required by the REMP.

SEABROOK - UNIT 1 3/4 12-2

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LANO USE CENSUS LIMITING CONDITION 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 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden

of greater than 50 m 2 (500 ft 2) producing broad leaf vegetation.

APPLICABILITY: At all times.

ACTION:

a. 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, pursuant to Specifica-tion 6.8.1.4, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report,

b. With a Land Use Census identifying a location (s) that yields a calcu-lated dose or dose commitment (via the same exposure pathway) 20%

greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the new location (s) within 30 days to the Radiological Environmental Moni-toring Program given in the 00CM, if permission from the owner to collect samples can be obtained and sufficient sample volume is available. The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s),

via the same exposure pathsay, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Pursuant to Specification 6.13, submit in the next Semiannual Radioactive Effluent Release Report documentation for a change in the-00CM including a revised figure (s) and table (s) for the 00CM reflecting the new location (s) with information supporting the change in sampling locations,

c. The provisions of Specifications .0.3 and-3r0 M are not applicable.

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sec-tors with the highest predicted relative deposition values (0/Qs) in lieu of the garden census. Specifications for broad leaf vegetation sampling in the REMP, shall be followed, including analysis of control samples.

SEABROOK - UNIT 1 3/4 12-3

. ~. ,

RAOIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on all r dioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission, that correspond to samples required by the REMP, APPLICABILITY: At all 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 6.8.1.3.

/

b. The provisions of Specification (g ,3.0.3.aww 3.0.-4are not applicable.

SURVEILLANCE REQUIREMENTS , 4.12.3 The Interlaboratory Comparison Program shall be identified in the 00CM.

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 6.8.1.3.

4 SEABROOK - UNIT 1 3/4 12-5

g

_gp_ _ . -_ _ - e, aa-, -.-- s. - _ -r -

.a ma -.~- ~ , _. . .a >

. o l

l 1

i ENCLOSURE 2 TO NYN-88100 ;

REVISED BASES P

1

)

i a

i 1

I t

?

I i

I e

d

--y.. m - - , , , , - ,- ,.,,~_ _ .___ , . _. ,_ . , - - -- - --w,,-

- ,-v--, - , , -*-

--rw-,---- r- ,-,,,,, _ . _ ... -,- ,

~

3/4.0 APPLICABILITY BASES r A).r a r G.

The specifications of this section provide the general requirements appli-cab to each of the Limiting Conditions for Operation and Surveillance Re-quire nts within Sections 3.0 and 4.0. In the event of a disagreement betw n the re frements stated in these Technical Specifiestions and those stated n an appli ble Federal Regulation or Act, the requirements stated in the li-cable Fed 1 Regulation or Act shall take precedence and shall be met.

3.0.1 s specification defines the applicability of each spe fication in terms of de 'ned OPERATIONAL MODES or other specified condition and is pro-vided to delinea specifically when each specification is applic le.

3.0.2 This sp ification defines those conditions neces' y to constitute compliance with the rms of an individual Limiting Conditio for Operation and associated ACTION requ ement.

3.0.3 The specifica ion delineates the measures t e taken for those circumstances not directly rovided for in the ACTION atements and whose occurrence would violate the intent of a specificati . For example, Specifi-cation 3.5.2 requires two ind endent ECCS subsyst s to be OPERABLE and pro-vides explicit ACTION requireme s if one ECCS su ystem is inoperable. Under the requirements of Specific 4tio 3.0.3, if bot the required ECCS subsystems are inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months meas es must b nitiated to place the unit in at least HOT STANDBY W thin the nex 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at. least HOT SHUTOOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . As a ther example, Specification 3.6.2.1 requires two Containment Spray Systems e OPERABLE and provides explicit ACTION requirements if one Spray System inoperable. Under the requirements of Specification 3.0.3, if both the r i d Containment Spray Systems are in-operable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months measures mus be in iated to place the unit in at least HOT STANOBY within the next 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , in at I st HOT SHUTOOWN within the follow-ing 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in COLD SHUTD0h ' ithin the s sequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . It is at-ceptable to initiate and compie a reduction i OPERATIONAL MODES in a shorter time interval than required i the ACTION stateme + and to add the unused por-tion of this allowable out- service time to that rovided for operation in subsequent lower OPERATION MODE (S). Stated allowa le out-of-service times are applicable regardles of the OPERATIONAL MODE (S) which the inoperability is discovered, but the mes provided for achieving a m e reduction are not applicable if the ino rability is discovered in a mode wer than the appli-l cable mode. For ex le if the Containment Spray System w discovered to be l inoperable while i STARTUP, the ACTION Statement would all up to 156 hours0.00181 days 0.0433 hours 2.579365e-4 weeks 5.9358e-5 months l to achieve COLO UT00WN. If HOT STANDBY is attained in 16 h rs rather than the allowed 78 ours, 140 hours0.00162 days 0.0389 hours 2.314815e-4 weeks 5.327e-5 months would still be available befor the plant would l be required be in COLD SHUTOOWN However, if this system was scovered to i

be inoperab' while in HOT STANOBY, the 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided to achies HOT STAN0BY would not e additive to the time available to achieve COLO SHUT 00%, so that the tot allowable time is rJduced from 156 hours0.00181 days 0.0433 hours 2.579365e-4 weeks 5.9358e-5 months to 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months .

.0.4 This specification provides that entry into an OPERATIONAL E or ett specified applicability condition must be made with: (1) the full 'm-p ment of required systems, equipment, or components OPERABLE end (2) all l

SEABROOK - tmIT 1 B 3/4 0-1 l

l

o ,

APPLICABILITY BASES her parameters as specified in the limiting Conditions for Operation being m without regard for allowable deviations and out-of-service provisions -

tai d in the ACTION statements.

T intent of this provision is to ensure that facility operation s not initiate with either required equipment or systems inoperable or et r speci-fied limi being exceeded.

Exceptio. to this provision have been provided for a limi d number of specifications en startup with inoperable equipment would no affect plant safety. These e eptions are stated in the ACTION statement of the appropriate specifications.

4.0.1 This spec ication provides that surveillan activities necessary to ensure the Limiting onditions for Operation are me and will be performed during the OPERATIONAL ES or other conditions for nich the Limiting Condi-tions for Operation are a 'icable. Provisions for dditional survoillance activities to be performed 'thout regard to T.he plicable OPERATIONAL MODES or other conditions are provi d in the individ Surveillance Requirements.

Surveillance Requirements for . ecial Test Exe tions need only be performed when the Special Test Exception being uti zed as an exception to an individual specification.

4.0.2 This specification provi llowable tolerances for performing surveillance activities beyond those cified in the nominal surveillance in-terval. These tolerances are necess provide operational flexibility be-cause of scheduling and performane cor.si rations. The phrase "at least" as-sociated with a surveillance fre ency does at negate this allowable tolerance value and permits the performa of more fr ent surveillance activities.

The tolerance values, en either individu 'ly or consecutively over three test intervals, are fficiently restrictivt to ensure that the reli-ability associated with + e surveillance activity i not significantly degraded beyond that obtained fr the nominal specified inte 1.

4.0.3 This sp ification provides the criteria for etermination of com-pliance with the .RABILITY requirements of the Limiting nditions for Opera-tion. Under th criteria, equipment, systems, or compone s are assumed to satisfactorily be OPERABLE if ne associated surveillance activities have b performed wi+ in the specified time interval. Nothing in this revision is to be constru as defining equipment, systems, or components OPERA E when such items are ound or known to be inoperable although still meeting s e Surveil-lance R uirements. Items may be determined inoperable during use, uring surve ance tests, or in accordance with this specification. There e, ACTI statements are entered when the Surveillance Requirements shoul have be performed rather than at the time it is discovered that the tests w e not rformed.

4.0.4 This specification ensures that the surveillance activities asso-ciated with a Limiting Condition for Operation have been performed within the SEABROOK - UNIT 1 B 3/4 0-2 i

.. w. . .,

APPLICABILITY BASES cified time interval prior to entry into an OPERATIONAL MODE or other ap-pl ble condition. The intent of this provision is to ensure that survei lanc ctivities have been satisfactorily demonstrated on a current bas as requir to meet the OPERABILITY requirements of the Limiting Conditi for Operatic Under t terms of this specification, for example, during itial plant STARTUP or foi ing extended plant outages, the applicable s eillance acti-vities must be p formed within the stated surveillance inte al prior to placing or returni the system or equipment into OPERABLE tatus.

4.0.5 This speci ation ensures that inservice spection of ASME Code Class 1, 2, and 3 compon ts and inservice testing o' SME Code Class 1, 2, and 3 pumps and valves will be erformed in accordance ith a periodically updated version of Section XI of the ME Boiler and Pre ure Vessel Code and Addenda as required by 10 CFR 50.55a. elief from any f the above requirements has been provided in writing by the ission a is not a part of these Technical Specifications.

This specification includes a cla ication of the frequencies for per-forming the inservice inspection and es 'ng activities required by Section XI of the ASME Boiler and ?ressure Ve el Co and applicable Adder.da. This clarification is provided to ens consiste in surveillance intervals throughout these Technical Spe ications and remove any ambiguities re-lative to the frequencies for erforming the req red inservice inspection and testing activities.

Under the terms o# .his specification, the more r trictive requirements of the Technical Spe 'ications take precedence over the SME Boiler and Pres-l sure Vessel Code ar applicable Addenda. For example, the equirements of Specification 4. to perform surveillance activities prior o entry into an OPERATIONAL MO or other specified applicability condition ta s precedence over the ASM oiler and Pressure Vessel Code provision which a ws pumps to l

l be tested ' to 1 week after return to normal operation. And for ample, the Tech al Specification definition of OPERABLE does not grant a ace period fore a device that is not capable of performing its specifie unction is de ared inoperable and takes precedent.e over the ASME Boiler and Pre ure Ves 1 Code provision which allows a valve to be incapable of performing i s cified function for up t.1 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being declared inoperable.

SEABROOK - UNIT 1 B 3/4 0-3

INSERT C 3/4.0 APPLICABILITY BASES Specification 3.0.1 through 3.0.4 establish the general requirements applicable to Limiting Conditions for Operation. These requirements are based on the triuirements for Limiting 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. When 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.'

Specification 3.0.1 establishes the Applicability statement within each individual specification as the requirement for when (i.e., in which OPERATIONAL MODES or other specified conditions) conformance to the Limiting Conditions 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 are not met.

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 to be met. 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 required to place the facility in a MODE or condition in which the specification no longer applies. It is 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.

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 equipment is removed from service. In this case, the allowable outage time SEABROOK - UNIT 1 B 3/4 0-1

o 4 .

3/4.0 A_PPLICABILITY BASES limits of the ACTION requirements are applicable when this limit expires if the surveillance has not been completed. When a shutdown is required to comply with ACTION requirements, the plant may have entered a MODE in which a new specification becomes applicable. In this case, the time limits of the ACTION requirements would apply from the point in time that the new specification becomes applicable if the requirements of the Limiting Condition for Operation are not met.

Specification 3.0.2 establishes that noncompliance with a specification exists when the requirements 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 (1) 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 required when compliance with a Limiting Condition of Operation is restered within the time interval specified in the associated ACTION requirements.

Specification 3.0.3 establishes the shutdown ACTION requirements that must be implemented when a Limiting Condition for Operation is not met and the condition is not specifically addressed by the associated ACTION requirements. The purpose of this specification is to delineate the time limits for placing the unit in a safe shutdown MODE when plant operation cannot be maintained within the limits for safe operation defined by the Limiting Conditions for Operation and its ACTION requirements. It is not intended to be used as an operational convenience 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 components 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 MODES 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 tetminated. 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 SEABROOK - UNIT 1 B 3/4 0-2

. c. .

3/4.0 APPLICABILITY BASES 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.

The time limits of Specification 3.0.3 allow 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months for the plant to be in the COLD SEUTDOWN MODE when a shutdown is required during the POWER MODE of operation. If the plant is in a lower MODE of operation when a shutdown is required, the time limit for reaching the next lower MODE of operation applies. However, if a lower MODE of operation is reached in less time than allowed, the total allowable t.ime to reach COLD SHUTDOWN, or other applicable MODE, is not reduced. For example, if HOT STANDBY is reached in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , the time allowed to reach HOT SEUTDOWN is the t. ext 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months because the total time to reach HOT SEUTDOWN is not reduced from the allowable limit of 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months .

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

The same principle applies with regard to the allowt;'. outage time limits of the ACTION requirements, if compliance with the ACTION requirements for one specification results in entry into a MODE or condition of operation for another specification in which the requirements of the Limiting Condition for operation are not met. If tha new specification becomes applicable in less time than specified, the difference may be added to the allowable outage time limits of the second specification. However, the allowable outage time limits of ACTION requirements for a higher MODE of operation may not be used to extend the allowable outage time that is applicable when a Limiting Condition fer Operation is not met in a lower MODE of operation.

The shutdown requirements of Specification 3.0.3 do not apply in MODES 5 and 6, because the ACTION requirements of individual specifications define the remedial measures to be taken.

Specification 3.0.4 establishes limitations on MODE changes when a Limiting condition for Operation is not met. It precludes placing the facility in a higher MODE 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 MODES were permitted. The purpose of this specification is to ensure that facility operation is not initiated or that higher MODES 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 f acility for an unlimited period of time provides an accept-able level of saf ety for continued operation without regard to the status of the plant before or after a MODE change. Therefore, in this case, entry into SEABROOK - UNIT 1 B 3/4 0-3 i

.- 6 .

3/4.0 APPLICABILITY BASES au OPERATIONAL MODE or other specified condition may be made in accordance with thu 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.

When a shutdown is required to comply with ACTION requirementJ, the provielons of Specification 3.0.4 do not apply because they would delay placing the facility in a lower MODE of operation.

Specifications 4.0.1 through 4.0.5 establish the general requirements applicable to Surveillance Requirem3nts. These requirements are based on the Surveillance Requirements stated in the Code of Federal Regulations, 10 CFR 50.36(c)(3):

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

Specification 4.0.1 establishes the requirement that surveillancos must be performed during the OPERATIONAL MODES 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 a MODE or other specified condition for which the associated Limiting Conditions for Operation are applicable. Surveillance Requirements do not have to be performed when the facility is in an OPERATIONAL MODE for which the requirements of the associated Limiting Condition for Operation do not apply unless otherwise specified. The Surveillance Requirements 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.

Specification 4.0.2 establishes the conditions under which the specified time interval for Surveillance Requirements 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 surveillances 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 engin( ering judgment and the reccanition that the most probable result of any particular surveillance bein; performed is the verification of conformance with the Surveillance SEABROOK - UNIT 1 B 3/4 0-4

y% ,

3/4.0 APPLICABILITY BASES 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.

Specification 4.0.3 establishes the failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by the provisions of Specification 4.0.2. as a condition that constitutes a failure l to meet the OPERABILITY requirements for a Limiting Condition for Operation.

Under the provisions of.this specification, systems and components are assur.ed to be OPERABLE when Surveillance Requirements have been satisfactorily performed within the specified. time interval. However, noir.Ang 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 el rifies that the ACTION requirements are applicable when Surveillance Requi:ements have not been completed within the allowed surveillance interval and that the time limits of the ACTION requirements apply from the point in tima iL 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 3pecification 4.0.3. However, this does not negate the fact that the failure to have performed the aurveillance 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 requirement and is, therefore, a reportaole event under the requirements of 10 CFR 50.73(a)(2)(1)(3) because it is a condition prohibited by the plant's Technical Specifications.

If the allowable outage time limits of the ACTION requirement, are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or a shutdown is required to comply with ACTION regnarements, 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 is required to comply with ACTION requirements or before other remedial measures would be required that may preclude 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 the delay in completing the required survr.;1ance. This provision also provides a time limit for the completion of Surveillance Requirements that become applicable as a consequence of MODE changes imposed by ACTION requirements and for SEABROOK - UNI" 1 B 3/4 0-5 i

yq' ,

3/4.0 APPLICABILIT,Y BASES 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 limits of the ACTION requirements are applicable at that time._ When a surveillance is performed within the 24-hour allowance and the Surveillance Requirenents 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 req '.rements 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.

Specification 4.0.4 establishes the requirement that all applicable surveillances must be met before entry into an OPERA 1IONAL MODE 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 a MODE or condition for which these systems and components ensure safe operation of the facility. This. provision applies to changes in OPERATIONAL MODES or other specified conditions associated with plant shu*.down as well.as startup.

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

When 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 HvDE of operation.

Specification 4.0.5 est.ablishes the requirement that inservice inspection of ASME Code Class 1, 2, at i 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.

1 1 This specification includes a clarification of the frequencies for performing I the inservice inspection and testing activities required by Section XI of the l

ASME Bciler and Pressure Vessel Code and applicable Addenda. This I clarification is provided to ensure consistency in surveillance intervals l throughout the Techt ;al Specifications and to remove any ambiguities relative l to the frequencies for performing the required inservice inspection and testing activities.

I SEABROOK - UNIT 1 B 3/4 0-6 l

l l

c ce L 3/4.0 APPLICABILITY BASES _

Under the terms of this specification, the more restrictive requirements of

the Technical Specifications take precedence over the ASME Boiler and Pressure L Vessel Code and applicable Addenda. The requirements of Specification 4.0.4 to' perform surveillance activities before entry into an OPERATIONAL MODE or other specified condition takes precedence over the ASHE Boiler and Pressure Vessel Code provision which 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, that is not capable of performing its specified function, is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Sefore being declared inoperable.

i l

i

[

l t

SEABROOK - UNIT 1 B 3/4 0-7

,

ML20151G871

Text

Navigation menu

Search