Text

Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements & RCS Operational Leakage
	ML20247R712
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	07/28/1989
From:	; CONNECTICUT YANKEE ATOMIC POWER CO.
To:	;
Shared Package
ML20247R709	List: B13295, Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements & RCS Operational Leakage; ML20247R707;
References
	B13295, NUDOCS 8908080087
	Download: ML20247R712 (85)
	v • d • e

, l Docket No. 50-213 B13295 I

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Attachment 1 j Haddam Neck Plant ;

Proposed Revision Technical Specifications

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Jr!1y 1989 1 i

- Docket No 50-213 B13291 4

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SECTIONS 3/0 AND 4.0 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS July 1989

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS 3/4.0 APPLICABILITY i 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 i Limiting Conditions for Operation, the associated ACTION requirements shall be met.

3.0.2 Noncompliance with a specification shall exist when the requirements of the 1.imiting 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 requinments, 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 ,

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

c. AT least COLD SHUTDOWN 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 frcm 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.

3.0.4 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 ACTION requirements when conformance to them permits continued operation of the facility for an l 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 )

1 specifications.

4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for ]3 Operation unless otherwise stated in an individual Surveillance Requirement.

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

HADDAM NECK 3/4 0-1

, j APPLICABILITY SURVEILLANCE RE0VIREMENTS

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

b. The combined time interval for any three consecutive surveillance I intervals shall not exceed 3,25 times the specified surveillance interval. ,

4.0.3 Failere 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 Limiting Condition for Operation. The time limits of the ACTION requirements are applicable at i, the time it is identified that a Surveillance Requirement has not been ,

performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to i permit the completion of the surveillance Men the allowable outage time limits of the ACTION requirements 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 the Limiting Condition for Operation have 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.

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

a. Inservice inspoction of ASME Code Class 1, 2, and 3 equivalent ';

components and inservice testing of ASME Code Class 1,' 2, and 3 I equivalent pumps and valves shall be performed in accordance with '

Section XI of the ASME Boiler and Pressure. Vessel Code and applicable Addenda as required by 10 CFR Part 50, Section 50.5La(g), except where specific written relief has been granted by the Commission pursuant to 10CFR Part 50, Section 50.55a (g)(6)(i).

b. Surveillance intervals specified in Sectioa XI of the ASME Boiler I and Pressure Vessel Code and applicable Addenda for the inservice !

inspection and testing activities required by the ASME Boiler aad i Pressure Vessel Code and applicable Addenda shall be applicable as j follows in these Technical Specifications:

ASME Boiler and Pressure Vessel Required frequencies for Code and applicable Addenda performing inservice

! terminolog3 for inservice inspection and testing inspection and testina ac.tlyitiqi activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days HADDAM NECK 3/4 0-2

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APPLICABILITY SURVEILLANCE RE0VIREMENTS (Continued) i

c. The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities;

d. Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements; and

e. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical i Specification.

4.0.6 The augmented inservice inspection program at each weld identified in Table 4.0-1 and 4.0-2 shall be performed as follows in accordance with the applicable requirements of the ASME Section XI Code, specified in Specification 4.0.5.

a. 4 rst lfD-Year Insoection Proaram

1. Nondestructive examination of each weld identified in Tables 4.0-1 and 4.0-2 for the first three consecutive 3-1/3 year inspections. Tnese inspections may be adjusted to coincide with the scheduled regular ASME Section XI inspections. i

2. A monthly visual examination for evidence of leakage of areas identified in Tables 4.0-1 and 4.0-2.

b. Successive Inservice Inspection Proarams

1. If no indications are detected or the indications do not exceed the allowable standards of the ASME Section XI Code during inspections specified in 4.0.6.a.1, subsequent inspections will be limited to once during each 10-year inspection interval.

2. If indications are detected that exceed the allowable standards of the ASME Section XI Code, they shall be investigated and evaluated and the frequency of examination for that weld shall revert to Specification 4.0.6.a.1.

3. Consistent with paragraph 4.0.6.b.1, visual examinations of i areas identified in Tables 4.0-1 and 4.0-2 will be performed semiannually.

c. Repairs. Re-examination and Tests Repairs, re-examination, and piping pressure tests shall be conducted in accordance with ASME Section XI.

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BASES FOR SECTIONS 3.0 AND 4.0 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS j

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H91L The BASES contained in succeeding pages summarizes the reasons for the Specifications in Sections 3.0 and 4.0, but in accordance with 10 CFR 50.36 are not part of these Technical Specifications.

.- 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS 3/4.0 APPLICABILITY BASES Specifications 3.0.1 throuah 3.0.4 establish the general requirements applicable to Limiting Conditions for Operation. These requirements are.

based on the requirements for Limiting Conditions for Operation stated in the Code of Federal Regulations,10CFR50.36(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 corcpleted 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 l include a specified time limit for the completion of a Surveillance i

Requirement when equipment is removed from service. 'In this case, the allowable outage time 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 HADDAM NECK B3/4 0-1

. i 3/4.0 APPLICABILITY l i

BASES (Con't) 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 j 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 b?en implemented within the specified time interval. The purpose of this specification is to .

clarify that (1) implementation of the ACTION requirements within the I 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 restored 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. The time limits specified to reach lower MODES of operation ptrmit 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 r.cnditions for which this specification applies.

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

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 !

I the COLD SHUTDOWN MODE when a shutdow 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 r!0DE of operation 4 applies. However, if a lower MODE of operation is reached in less time than HADDAM NECK B3/4 0-2

l 3/4.0 APPLICABILITY BASES (Con't) l allowed, the total allowable time 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 SHUTDOWN is the next II hours because ;

the total time to reach HOT SHUTDOWN 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. !

i The same principle applies with regard to the allowable 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 the new specification becomes applicable in !

less time than specified, the difference may by added to the allowable l 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 for 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 facility for an unlimited period of time provides an i acceptable level of safety for continued operation without regard to the {

status of the plant before or after a MODE change. Therefore, in this caso, j entry into an OPERATIONAL MODE or other specified condition may be made in i accordance with the provisions of the ACTION requirements. The provisions 1 of this specification should not, however, be interpreted as endorsing the 1 failure to exercise good practice in restoring systems or components to l OPERABLE status before plant startup. i 1

When a shutdown is required to comply with ACTION requirements, the l provisions 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 throuch 4.0.5 establish the general requirements applicable to Surveillance Requirements. These requirements are based on i the Surveillance Requirements stated in the Code of Federal Regulations, ;

10CFR50.36(c)(3)* i l

HADDAM NECK B3/4 0-3 i

I 3/4.0 APPLICABILITY BASES (Con't)

" Surveillance requirements are requirements relating to test, calibration, or inspection to ensure that the necessary quality of ,

systems and components is maintained, that facility operation will be i within safety limits, and that the limiting conditions of operation q will be met." {

1 Specification 4.0.1 establishes the requirement that surveillance 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 ersure that surveillance 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 othe.r 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 cf a ,

specification. l l

Specification 4.0.2 establishes the conditions under which the specified 1 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 surveillance; e.g.,

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

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 to meet the OPERABILITY requirements for a Limiting Condition for Operation.

Under the provisions of this specification, systems and components are assumed to be OPERABLE when Surveillance Requirements have been l satisfactorily performed within the specified time interval. However, l nothing in this provision is to be construed as implying that systems or 1

components are OPERABLE when they are found or known to be inoperable although still meeting the Surveillance Requirements. This specification also clarifies that the ACTION requirements are applicable when Surveillance Requirements have not been completed within the allowed HADDAM NECK B3/4 0-4

--.-_-_.-__a

l 3/_iJ APPLICABILITY BASES (Con't) surveillance interval and that the time limits of ACTION requirements apply from the point in time it is identified that a surveillance has not been performed and not at the time that the allowed surveillance interval was ;

exceeded. Completion of the Surveillance Requirement within the allowable outage time limits of the ACTION requirements restores compliance with the )

requirements of Specification 4.0.3. Huwever, this does not negate the facc i that the failure to have performed the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, was i a violation of the OPERABILITY requirements of a Limiting Condition for l Operation.

i If the allowable outage time limits of the ACTION requirements are less than i

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or a shutdown is required to com?ly with ACTION requirements, e.g.,

l Specification 3.0.3, a 24-hour allowance is provided to permit a delay in implementing the ACTION requirements. This provides an adequate time 11mit ,

to complete Surveillance Requirements that have not been performed. The I purpose of this allowance is to permit the completion of a surveillance l before a shutdown is required to comply with ACTION requirements or before l other remedial measures would be required that may preclude completion of a i 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 surveillance. 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 1 24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is term Mated. i 1

1 Surveillance Requirements do not have to be performed on inoperable ;

equipment because the ACTION requirements define the remedial measures that i apply. However, the Surveillance Requirements have to be met to demonstrate i that inoperable equipment has been restored to OPERABLE status.

Specification 4.0.4 establishes the requirement that all applicable '

surveillance must be met before entry into an OPERATIONAL MODE or other condition of operation specified in the Applicability statement. The purpose of this specification is to ensure that system and component i 0PERABILITY 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 shutdown as well as startup.

1 HADDAM NECK B3/4 0-5

~

3/4.0 APPLICABILITY BASES (Con't)

I 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 MODE of operation.

Specification 4.0.5 establishes the requirement that inservice inspection of I 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 accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure 1 Vessel Code and Addenda as required by 10CFR50.55a. These requirements ;

apply except when relief has been provided in writing by the Commission, j This specification includes a clarification of the frequencies for performing the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda. This clarification is provided to ensure consistency in surveillance intervals throughout the Technical Specifications and to remove i any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.

Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda. The requirements of j Specifications 4.0.4 to perform surveillance activities before entry into an OPERATIONAL MODE or other specified condition takes precedence over the ASME 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 gra:e period before a component, that is not capable of performing its specified function, is- J 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 before being declared inoperable.

Specification 4.0.6 Consistent with the guidance contained in NRC Mechanical' Engineering Branch Technical Position No. 4, dated March 18, 1915, an inservice inspection program is instituted at potenial high energy pipe break locations at which consequences of a postulated pipe rupture "could" affect the plant's safe shutdown capability and other methods of pipe restraint are considered to be impractical. This augmented inspection program will provide a means for timely detection of cracks propagating in the piping. Since the Haddam Neck Plant was built prior to adoption of the ASME Code for ISI, there is not complete accessibility for inspection in accordance with specific requirements of that code. Inspections will be conducted to the extent practical within the limitations of design, geometry, and materials of tLa l

components. Visual inspections will be conducted for all areas identified in Tables 4.0-1 and 4.0-2.

HADDAM NECK B3/4 0-6

.]

References:

1. CYAPC0 Special Report "High Energy Pipe Break Outside J Containment," dated February 5, 1975, as supplemented on March 13, 1975, April 4, 1975, and May 1, 1975.

2. E. J, Mroczka letter to C. I. Grimes, dated December 5, i 1986,

Subject:

Environmental Qualification of Equipment i Outside Containment and High Energy Line Breaks. '

i

3. F. J. Miraglia le;ter to E. J. Mroczka, dated January )

27, 1987,

Subject:

Augmented Inservice Inspection and l Resolution of Environmental Qualification and High i Energy Line Break Issues. {

i i

l1 0

l I

I HADDAM NECK B3/4 0-7

Docket No. 50-213 Elll21 Section 3.4.6.2 Reactor Coolant System - Operational Leakage 1

1 1

July 1989

REACTOR COOLANT SYSTEM OPERATIONAL _ LEAKAGE LIMITING CONDITION _f0R OPERATION ,

I 3.4.6.2 Reartor Coolant S.vstem leakage shall be limited to:

a. No PRESSURE B0UNDARY LEAKAGE,

b. 1 gpm UNIDENTIFIED LEAKAGE,

c. 0.4 gpm total primary-to-secondary leakage through all steam generators not isolated from the Reactor Coolant System and 150 gallons per day through any one steam generator not isolated from the Reactor Coolant System,

d. 10 gpm IDENTIFIED LEAKAGE from the Reactor Coolant System,

e. 2 liters per hour from the mechanical seal of any Residud Heat Removal pump.

f. 0.8 gallons per hour (3 liters per hour) combined leakage outside containment from Residual Heat Removal System,* the makeup, i seal injection / return and fill portions of the Charging System, and those portions of the HPSI system outside of containment used for recirculation,

g. I gpm through each of the following ECCS valves : SI-CV-862 A, B, i C, and D, and SI-CV-872 A and B.

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

a. With any PRESSURE B0UNDARY LEAKAGE, be in at least HOT STANDBY i within 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 , j 1

b. With any Reactor Coolant System leakage greater than any one of !

the above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT j 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 .

1

c. If primary-to-secondary tube leakage (not including leaks originating from tube to tube sheet welds) in excess of Specification 3.4.6.2c., above, results in COLD SHUTDOWN, ,

inservice inspections shall be performed in accorcance with First '

Sample Inspection requirements in Table 4d-2 during that COLD !

SHUTDOWN. ,

a As determined from the last time the RHR leakage was measured at 145 psig.

HADDAM NECK 3/4 4-31

LIM? TING CONDITION FOR OPERATION Rontinued)

REACT 0k COOLANT SYSTEM I

d. If Residual Heat Removal Pump Seal leakage exceeds its allowable limit, monitor this leakage for at least 36 continuous operating-hours. If the leak rate does not decrease or stabilize prior to reaching three liters per hour, the provisions of action statement l

b. are applicable. i SJRVEllLANCER50VIREMENTS 4.4.6.2.1 Refetor Coolant System leakages shall be demonstrated to be within each of the nbove limits by: i

a. Monitoring the containment atmosphere gaseous radioactivity monitor at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; j

b. Menitoring the containment sump inventory at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ;

c. Monitoring the Volume Control Tank level at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ;

.l

d. Performance of a Reactor Coolant System water inventory balance at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ;

e. Monitoring the Reactor Head Flange Leakoff System at least once i per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ;

f. Monitr1 ring the RHR Pit, HI'SI, and charging pump cubicles for indications of leakage at seals, flanges, and valves at least once per 1-2 hours.

g. Performance of an operational leak rate test, for those portions of the HPSI, charging and RHR system outside containment used for recirculation, at least once per month. The test shall be conducted at a hydrostatic pressure corresponding to the operating pressure under accident conditions.

h. Monitoring leakage through each of the following ECCS valves (SI-CV-862 A, B, C, and D and SI-CV-872 A and B):

1) At least once per 18 months,

2) Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or more and if leakage testing has not been performcd in the previous 9 months,

3) Prior to returning the valve to service following maintenance, repair, or replacement work on the valve', and

4) Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months fol lowing valve actuation due to flow through the valve.

The provisions of Specification 4.0.4 are not applicable for. entry into MODE 3 or 4.

HADDAM NECK 3/4 4-32

q

. REACTOR COOLANT SYSTEM BASES

)

capability to reliably detect degradation that _has penetrated 20% of the l original tube wall thickness and to axially locate the degradation in the 4 rolled region .with an accuracy of 10.1 inch. ]

The plugging or sleeving limit defined in Specification 4.4.5A.a.6 is based ,

on the requirements set forth in-Regulatory Guide 1.121. These requirements J are also the bases for demonstrating that a tube imperfection is acceptable regardless_ of its depth provided it is located below one inch of sound roll.

An imperfection within this 1" region due to manufacturing or repair activities is acceptable and considered insignificant. An indication which developed in service within this 1" region may be considered significant. -

I Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be reported to the Commission in a Special Report oursuant to Specification 6.9.2 within 30 days and prior to resumption of plant operation. Such cases will be considered by the ,

Commission on a case-by-case basis and may result in a requirement for j analysis, laboratory examinations, tests, additional eddy-current I inspection, and revision of the Technical Specifications, if necessary.

3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE ,

3/4.4.6.1 LEAKAGE DETECTION SYSTEMS The RCS Leakage Detection Systems required by this specification are l provided to monitor and detect leakage from the reactor coolant pressure i boundary.

This technical specification ensures a reliable means of detecting 1 unidentified leakage in the reactor coolant system which potentially could ;

be due to a circumferential through-wall flaw in primary system piping. The {

required instrument sensitivity is I gallon per minute in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months as stated 1 in Condition (2) of Generic Letter 84-04. Because the Volume Control Tank Level Monitoring System and the Containment Main Sump Level (Narrow Range) ;

Monitoring System are not seismically qualified, surveillance requirements . ;

for a seismic event greater than one half the Safe Shutdown Earthquake (SSE) ;

are imposed.

The RCS Leakage Detection Systems required by this specification are previded to monitor and detect leakage from the reactor coolant pressure boundary. These Detection Systems are consistent with the recommendations of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage i Detection Systems," May 1973. ;

l l

HADDAM NECK- 83/4 4-5

- _ _ _ _ _ _ - _ _ _ _ _ _ _ -. _ a

1 REACTOR COOLANT SYSTEM BASES l

3/4.4.6.2 OPERATIONAL LEAKAGE PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary. l Therefore, the presence of any PRESSURE BOUNDARY LEAKAGE requires the unit j to be promptly placed in COLD SHUfDOWN. j Industry experience has shown that while a limited amount of leakage is expected from the RCS, the unidentified portion of this leakage can be reduced to a threshold value of less than 1 gpm. This threshold value is sufficiently low to ensure early detection of additional leakage.

The total steam generator tube leakage limit of 0.4 gpm for all steam generators not isolated from the RCS ensures that the dosage contribution from the tube leakage will be limited to a small fraction of 10 CFR Part 100 dose guideline values in the event of either a steam generator tube rupture or steam line break. The 0.4 gpm limit is consistent with the assumptions used in the analysis of these accidents. The 150 gpd leakage limit per steam generator ensures that steam generator tube integrity is maintained in {

the event of a main steam line rupture or under LOCA conditions.

The 10 gpm IDENTIFIED LEAKAGE limitation provides allowance for a limited amount of leakage from known sources whose presence will not interfere with the detection of UNIDENTIFIED LEAKASE by the Leaka~ge Detection Systems.

The 12-hour surveillance requirement for leakage monitoring for RHR, HPSI, and charging systems involves general inspection of the RHR pit, HPSI, and charging pump cubicles for any obvious signs of leakage.

The limitation on the combined leakaga from the kHO. System, HPSI, and charging systems provides an indication of impending seal failures. The radiological consequences associated with the combined leakage is acceptable. This leakage will be considered as a portion of the IDENTIFIED LEAKAGE.

fhe specified allowable leakage from the listed ECCS valves is sufficiently low to ensure early detection of possible check valve failure. It is apparent that when pressure isolati.on is provided by two in-series valves and when failure of one valve in the pair can go undetected for a substantial length of time, verification of valve integrity is required.

Since these valves are important in preventing overpressurization and rupture of the ECCS low pressure piping which could result in a LOCA that l bypasses containment, the e valves should be tested periodically to ensure j low probability of gross failure. l The Surveillance Requirements for these ECCS valves provide added assurance of valve integrity thereby reducing the probability of gross valve failure l and consequent fntersystem LOCA. Leakage from these ECCS valves is .

IDENTIFIED LEAKAGE and will be considered as a portion of the allowed limit.

4 HADDAM NECK B3/4 4-6 l l

. REACTOR COOLANT SYSTEM BASES i

3/4.4.7 CHEMISTRY !

The limitations on Reactor Coolant System chemistry ensure that corrosion of the Reactor Coolant System is miniinized and reduces the potential for Reactor Coolant System leakage or failure due to stress corrosion. )

Maintaining the chemistry within the Steady-State Limits provides adequate i corrosion protection to ensure the structural integrity of.the Reactor 1 Coolant System over the life of the plant. The associated effects of J exceeding the oxygen, chloride, and fluoride limits are time and temperature {

dependent. Corrosion studies show that operation may be continued with

.cntaminant concentration levels in excess of the Steady-State Limits, up to the Transient Limits, for the specified limited time intervals without having a significant effect on the structural integrity of the Reactor Coolant System. The time interval permitting continued operation within the restrictions of the Transient Limits provides time for taking corrective actions to restore the contaminant concentrations to within the Steady-State ,

limits. 1 l

The Surveillance Requirements provide adequate assurance that concentrations in excess of the limits will be detected in sufficient time to take corrective action.

3/4.4.8 SPECIFIC ACTIVITY The limitations on the specific activity of the reactor coolant ensure that the resulting 2-hour doses at the SITE B0UNDARY will not exceed an appropriately s,nall fraction of 10 CFR Part 100 dose guideline values following a steam generator tube rupture accident.

The ACTION statement permitting POWER OPERATION to continue for limited time periods with the reactor coolant's specific activity greater than 1 micrcCurie/ gram DOSE EQUIVALENT I-131, but within the allowable limit shown on Figure 3.4-2, accommodates possible iodine spiking phenomenon which may occur following changes in THERMAL POWER. Operation with specific activity levels exceeding 1 microcurie / gram DOSE EQUlVALENT I-131 but within the limits shown on Figure 3.4-2 must be restricted to no more than 800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months per year (approximately 10% of the unit's yearly operating time) since the activity levels allowed by Figure 3.4-2 increase the 2-hour thyroid dose at the SITE B0UNDARY by a factor of up to 20 following a postulated steam generator tube rupture.

)

l l4 HADDAM NECK B3/4 4-7 1

I __________.___ _ U

.l 1 Docket No. 50-213

. B13295 ,

i

.4 i

4 3

l 1

l Attachment IA j Haddam Neck Plant !

Revision to the previously submitted Technical Specification Sections J

d l

i l

i i

1 July 1989

' Attachment IA 1

,. B13295/Page 1 3.3.1 Reactor Trip System Instrumentation (Table 3.3-1) )

3.3.2 Engineered Safety Feature Actuation System Instrumentation (Table 3.3-2) 3.3.3.1 Radiation Monitoring for Flant Operations (Action Statement b.) ,

i 3.3.3.2 Movable Incore Detectors (Action Stateeent b.) !

l 3.3.3.3 Seismic Instrumentation (Action Statement b.) l 3.3.3.4 Meteorological Instrumentation (Action Statement b.) 'l 3.3.3.5 Accident Monitoring Instrumentation (Action Statement b.) j 3.3.3.6 Fire Detection Instrumentation (Action Statement c.)

3.3.3.7 Radioactive Liquid Effluent Monitoring Instrumentation (Action-Statement C.)

3.3.3.8 P.adioactive Gaseous 'ffluent Monitoring Instruinentation (Action .{

Statement c.) l 3.3.4 Internal Flood Protection (Action 5 tat?: ant b.)

3.4.1.4.P. Cold Shutdown - Loops Not Filled (Action Statement d.'added) 3.4.1.7 Isolated Loop Startup (Action *catement b.)

3.4.1.10 Idled Loop Startup (Action Statement b.)

3.4.2.1 Safety Valves - Shutdown-(Action Statement b. added) 3.4.9.3 Low Temperature Overpressure - Protection Systems (Action . Statement d.)

3.4.10 Structural Integrity (Action Statement d.)

~

3.6.1.3 Containment Air Locks (Action Statement'a.4)-

3.7.1.1 Safety Valves (Action Statement c.)

3.7.5 Sealed Source Contamir.ation (Action Statement b.)

3.7.6.1 fire Water Supply / Distribution System (Action Statement c.) _j

~

l 3.7.6.2 Spray and/or Sprinkler Systems (Action Statument D.)

3.7.6.3 C02 Systems (Action Statement b.)

! 3.7.6.4 Halon Systems (Action Statement b.)

1 Attachment IA L' 013295/Page 2 ;

3.7.6.5 Fire Hose Station, (Action. Statement b.) )

. 4 3.7.6.6 Yard Fim Hydrants and Associated Hydrant Hose li6uses (Action j

'Statementb.) ,

i 3.7.7 Fire Rated Assemblies (Action Statement b.)

3.7.8 Flammable Liquids Control- (Acti0n Statement b.)

3.7.11 PAB Air Cleanup Systeo (Action Statement c.)

3.9.7 Crane Travel ' Spent Fuel Storage Pool Building . (Action Statement' b.)

3.9.9 Containment Purge and Exhaust Isolation System (Action Statement'O.)'

3.9.11 Water Letel - Storage Pool (Action Stetement b.)

3.9.12 Fuel Storage Building Air Cteanup System (Action Statemeni. b.)'

3.11.1.2 kadicactive Effluents, Liquid Dose (Action Statement b.) j i

3.11.2.2 Radioactive Effluents, Nchle Gases - Dose-(Action Statement b.)

i 3.11.F.3 Dose, Radioiodines, Radioap.tive Material in Paticulate Form and -j Radionuclides Mher thae Noble Gases (Ac' ion Statement b.)

3.11.3 Total Dose (Action Statement b.)

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TABLE 3.3-2 (Continued)

TABLE NOTATIONS j 1

Trip function may be bypassed in this MODE when RCS pressure is less than _;

~

1800 psig.

- The channel (s) associated with the protective functions derived from the ;

out-of-service reactor coolant loop shall be placed in the tripped mode. ~

(a) THERMAL POWER above 10% of RATED THERMAL POWER. t 1

(b) For Surveillance Testing purposes, the train being tested will be l placed in " Defeat" function. J 1

l 1

ACTION STATEMENTS ACTION 20 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 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 .

ACTION 21 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, startup and/or power operation may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST provided the inoperable-channel is placed in the tripped condition within I hour.

i ACTION 22 - With a channel associated with an operating loop inoperable, 1 restore the inoperable channel to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT STANDBY within the next 'S hours and in at least HOT SHUTDOMN within the fellowing 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 23 -

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

i i

1 HADDAM NECK 3/4 3-16 l

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 3.3-4 shall be OPERABLE.

APPLICABILITY: As shown in Table 3.3-4.

ACTION:

a. 'With no radiation monitoring channels for plant operations OPERABLE, take the ACTION shown in Table 3.3-4.

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE Rf0VIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel for plant operations shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST-for the MODES and at the frequencies shown in Table 4.3-3.

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I HADDAM NECK 3/4 3-23

INSTRUMENTATION MOVABLE INCORE DETECTORS tIMITIN9 CONDITION FOR OPERATION 3.3.3.2 The Movable Incore Detector System shall be OPEPABLE with:

a. At least 11 of 13 northwest quadrant detector thimbles or at least 10 of 13 northwest quadrant detector thimbles if the inoperable locations are M8, MI2, and N8.

b. At least one set of four. quadrant symmetric thimbles, and

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

these thimbles.

APPi.ICABILITY: When the Movable Incore Detector System is used for:

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

b. Monitoring the QUADRANT POWER TILT RATIO, or

c. MeasurementofFfH and the LINEAR HEAT GENERATION RATE.

ACTION:

a. With the Moveable Incore Detector. System inoperable due to less ihan the minimum required number of detector thimbles as required in p 3.3.3.2a or b, penalty factors shall be applied when measuring F '

LINEARHEATGENERATIONRATEorQUADRANTPOWERTILTRATIO;ordurNg.

recalibration of the Movable Incore Detector System, as appropriate.

b. With the Movable Incore Detector System inoperable, due to insufficient movable detectors, drives or readout equipment, do not use the system for the above applicable monitoring or calibration functions. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.3.3.2 The Movable Incore Detector System shall be demonstrated OPERABLE by verifying an acceptable voltage plateau for the incore detector (s) at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when used as required by the above Applicability requirements.

l HADDaM NECK 3/4 3-26

s l

INSTRUMENTATION !

SEISMIC INSTRUMENTATION LIMITING CONDITION FOR OPERATION ;

l 3.3.3.3 The seismic monitoring system instrumentation shown in Table 3.3 5

.shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

a. With the seismic monitoring system inoperable for more than 30 days, prepare and submit a Special Report to the. Commission ,

pursuant to Specification 6.9.2 within the ne::t .10 days outlining 1 the cause of the malfunction and the pir.ns for restoring the system to OPERABLE status. '

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.3.3.3.1 The above seismic monitoring system shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-4.

l 4.3.3.3.2 The above required seismic monitoring system actuated during a seismic event 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 10 days following the scismic event.

Data shall be retrieved from actuated instruments and analyzed to determine the magnitude of the vibratory ground motion. If it is determined that the .,

magnitude of the event exceeded the Operating Basis Earthquake, then a ;

Special Report shall be prepared and submitted to the Commission pursuant to i Specification 6.9.2 within 14 days describing the magnitude, frec,uency ;

spectrum, and resultant effect upon facility features important to safety. J 1

1 1

1 i

l HADDAM NECK 3/4 3-27 l

INSTRUMENTATION METEOROLOGICAL INSTRUMENTATION LIMITING CONQITION FOR OPERATION 3.3.3.4 The meteorological monitoring instrumentation channels shown in Table 3.3-6 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 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status,

b. The provirions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.3.3.4 Each of the above meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CflANNEL CHECK and CHANNEL CALIBRATION at the frequencies showw, in Table 4.3-5.

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i HADDAM NECK 3/4 3-30

i 4

INSTRUMENTATION 4 ACCIDENT MONITORING INSTRUMENTATION l i

LIMITING CONDITION FOR OPERATION 3.3.3.5 The accident monitoring instrumentation channels shown in Table ;

3.3-7 shall be OPERABLE. !

APPLICABILITY: As shown in Table 3.3-7. i ACTION:

As shown in Table 3.3-7. I SURVEILLANCE REQUIREMENTS 4.3.3.5 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION at the frequencies shown in Table 4.3-6.

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HADDAM NECK 3/4 3-33

INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION __

3.3.3.6 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-8 shall be OPERACLE.

APPLICABILITY: Whenever systems, structures, components, or equipment protected by the fire detection instrumentation are required to be OPERABLE.

ACTION:

a. With any, but no less than the minimum required fire detection instruments shown in Table 3.3-8 inoperable, restore the inoperable instrument (s) to OPERABLE status within 14 days or within the next 1 Four establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least or.ce per hour, unless the instrument (s) is located inside the containment, then inspect that containment zone at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (or monitor the containment sir temperature at least once per hour at the locations listed in Specification 4.6.1.6).

b. With less than the minimum required fire detection instruments in any fire zone shown in Table 3.3-8 operable, within I hour 1 establish a continuous fire watch to inspect the zone (s) with the inoperable instrument (s), unless io instrument (s) is located inside the containment, then inspet, that containment zone at least once p r 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (or monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.6).

c. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.3.3.6.1 Each of the above required fire detection instruments which are accessible during plant operation shall be demonstrated OPERABLE at least once per 6 months by performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST. Fire detectors which are not accessible during plant operation shall be demonstrated OPERABLE by the performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the previous 6 months. Detectors which cannot be reset are not required to be demonstrated OPERABLE by performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST.

HADCAM NECK 3/4 3-40 1

INSTRUMENTATION RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.7 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE with applicable Alarm / Trip Setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The Alarm / Trip Setpoints shall be determined in accordance with methodology and parameters described in the OFFSITE DOSE CALCULATION MANUAL (00CM).

APPLICABILITY: At all times *.

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, without delay suspend the release of-radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the Alarm / Trip Setpoint i so it is acceptably conservative.

b. With the number of channels less than the minimum channels operable requirement, take the ACTION shown in Table 3.3-9. Exert best efforts to restore the inoperable monitor to OPERABLE status within 30 days, and, if unsuccessful, explain in the next Semi-annual Effluent Report way the inoperability was not corrected in a timely manner. Releases need not be terminated after 30 days provided the specified actions are continued.

c. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.3.3.7.I Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and ANALOG CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 4.3-7. i l '

At all times means that channel shall be OPERABLE and in service on a '

continuous, uninterrupted basis, except that outages are permitted for a maximum of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months each time for the purpose of maintenance and 1' performance of required tests, checks, calibrations or sampling. ,

HADDAM NECK 3/4 3-44

.1 l

j INSTRUMENTATION RADI0ACTLYLMSE0VS EFFLUENT MONITORING INSTRUMENTATION l I

LIMITING CONDITION FOR OPERATION 3.3.3.8 The radioactive gaseous effluent monitoring instrumentation channels shewn in Table 3.3-10 shall be OPERABLE with applicable Alarm / Trip Setpoints set to ensure that the limits of Specification 3.11.2.1 are not l exceeded. The setpoints shall be determined in accordance with *% l methodology and parameters as described in the ODCM.

APPLICABILITY: At all times *.

I ACTION:

a. With a radioactive gaseous effluent taonitoring instrumentation channel Alarm / Trip setpoint less conservative than required by the i above Specification, without delay suspend the release of .l radioactive gaseous effluents monitored by the affected channel, j or declare the channel inoperable, or change the Alarm / Trip Setpoint 30 it is acceptably conservative.

a

b. With the numoer of channels less than tha minimum channels ]

operable requirement, take the ACTION shown in Table 3.3-10. ~j Exert best efforts to restore the inoperable monitor to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semi-annual Effluent Report why the inoperability was not l corrected in a timely manner. Releases need not be terminated i after 30 days provided the specified actions are continued. I

c. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS !

4.3.3.8.1 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance f the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and ANALOG CHANNEL PERATIONAL TEST operations at the frequencies shown in Table 4.3-8. j i

At all times means that the channel shall be OPERABLE and in service on a continuous basis, except that outages are permitted for a maximum of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months each time for the purpose of maintenance and performance of i required tests, checks, calibrations.

I I

HADDAM NECK 3/4 3-49

4 INSTRUMENTATION 3/4.3.4 INTERNAL FLOOD PROTECTION LIMITING CONDITION FOR OPERATION 3.3.4 The liquid level instrumentation channels for flooding protection shown in Table 3.311 shall be OPERABLE.

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

ELL 9B:

a. With less than the Minimum Channels OPERABLE for any liquid level instrumentation Functional Unit, take the ACTION shown in Table 3.3-11.

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS __

4.3.4 Each liquid level instrumentation channel for flood protection shall be demonstrated OPERAELE:

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by performance of the CHANNEL CHECK,

b. At least once per 6 months by performance of an ANALOG CHANNEL OPERATIONAL TEST and visually verifying no obstruction.

HADDAM NECK 3/4 3-54

____ _ A

. REACTOR C00Lt.NT SYSTEM COLD SHUTDOWN - LOOPS NOT FILQQ LIMITING CONDITION FOR OPERATION 3.4.1.4.2 Two RHR LOOPS shall be OPERABLE

with at least one RHR LOOP in operation ** and either the Reactor Trip System breakers shall be open or the control rod drive lift coil:: shall be de-energized.

A_ APPLICABILITY: MODE 5 with reactor coolant loops not filled.

ACTION:

a. With less than the above required RHR LOOPS OPERABLE, immediately initiate corrective action to return the required RHR LOOPS to OPERABLE status as soon as possible.

b. With no RHR LOOP in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR LOOP to operation.

c. With the Reactor Trip System breakers closed and the control rod drive lift coils energized, within I hour either open the Reactor Trip Syr. tem breakers or de-energize the control rod drive lift coils,

d. Entry into MODE 5 while subject to any of the above ACTION requirements is not permitted.

SURVEILLANCE RE0VIREMENTS 4.4.1.4.2.1 At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , a RHR LOOP shall be determined to be in operation and circulating reactor coolant.

4.4.1.4.2.2 At least once per 7 days the RHR LOOP not in operation shall be determined OPERABLE by verifying breaker alignments and indicated power availability.

4.4.1.4.2.3 At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months verify that either the Reactor Trip System breakers are open or the control rod drive lift coils are de-energized.

One RHR loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided the other RHR loop is OPERABLE and in operation.

The RHR pump may be de-energized for up to I hour provided: (1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature is maintained at least 10*F below saturation temperature.

I HADDAN NECK 3/4 4-8

_.--_____._-_-_._._-_,e._,__ _ _ , . _ _ _ _ .

REACTOR COOLANT SYSTEM

' ISOLATED LOOP STARTUP LIMITING CONDFTION FOR OPERATION 3.4.1.7 A reactor codlant loop shall remain isolated until:

a. The temperature at the cold leg of the isolated loop is within 20'F of,the highest cold leg temperature of the operating loop (s) ,

b. The boron concentration of the isolated loop is greater than or equal to the boron concentration required to meet SHUTDOWN MARGIN requirements of specification 3.1.1.2 or 3.1.1.3 or the refueling boron concentration of Specification 3.9.1.

APPLICABILITY: MODES 3, 4, 5 and 6.

ACTION:

With the requirements of the above specification not satisfied, do not open the isolated loop stop valve::.

SURVEILLANCE REQUIREMENTS 4.4.1.7.1 The isolated loop cold leg temperature shall be determined to be.

within 20*F of the highest cold leg temperature of the operating loops within 30 minutes prior to opening the cold leg stop valve.

4.4.1.7.2 At least once per refueling outage the stop valve / temperature interlock shall be determined operable by verifying that the cold leg stop valve does not open if the cold leg temperature in the loop is more than 20*F cooler than the highest temperature of the remaining operating loops. j i

4.4.1.7.3 Within 30 minutes prior to opening the loop stop valves, the i isolated loop shall be determined to have a boron concentration greater than )

or equal to the boron concentration required to meet the SHUTDOWN MARGIN l requirements of Specification 3.1.1.2. or 3.1.1.3 or the refueling boron !

concentration of Specification 3.9.1. .l 4.4.1.7.4 At least once per refueling outage the reactor coolant pump, l loop stop and bypass valve interlock operability shall be demonstrated. a An operating loop (s) may be a Reactor Coolant loop (s) or'a Residual Heat Removal loop (s).

- The above requirements do not apply when a hot leg stop valve is opened to create an idled loop.

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HADDAM NECK 3/4 4-11

_ _____ L

. REACTOR COOLANT SYSTEM l' IDLED LOOP STARTUP LIMITING CONDITION FOR OPERATION ,

3.4.1.10 A reactor coolant loop shall remain idled until:

a. The n =perature at the cold leg of the: idled loop is within 20*F of the highest cold leg temperature of the operating loops,

b. The boron concentration of the idled loop is greater than or equal-to the boron concentration of the operating loops, 6

c. The reactor is no greater than 60% RATED THERMAL POWR.

APPLICABILITY: MODES I and 2.

1 ACTION:

With the requirements of the above' specification not satisfied,; do not open the idled loop cold leg stop valve.

SURVEILLANCE RE0UIREMENTS l

4.4.1.10.1 The idled loop cold leg temperature shall be determined to.be within 20*F of tha highest cold leg temperature of the operating. loops within 30 minutes prior to opening the idled loop cold leg stop valve.

4.4.1.10.2 Within 30 minutes prior to opening the idled loop cold leg stop valve, the reactor shall be determined to be-less than 60% RATED THERMAL POWER.

l l 4.4.1.10.3 Within 30 minutes prior to opening the idled loop. cold leg stop l- valve, the idled loop shall be determined to I: ave a boron concentration-

! greater than or equal to the boron concentration of the operating loops.

l l

HADDAM NECK 3/44-14

'l

. )

,. REACTOR COOLANT SYSTEM .l 3/4.4.2 SAFETY VALVES SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.2.1 A minimum of one pressurizer Code safety valve shall be OPERABLE with the lift setting associated with the OPERABLE Code safety valve within 11% of its design Setpoint*.

APPLICABILITY: MODE 4 except when Specification 3.4.9.3 is applicable.

ACTION: 1 i

a. With no pressurizer Code safety valve OPERABLE, immediately suspend all' operations involving positive reactivity changes and place an OPERABLE RHR loop into operation in the shutdown cooling mode. ,

i

b. Entry into MODE 4 is not permitted. 1 i

SURVEILLANCE RE0VIREMENTS )

4.4.2.1 In addition to the requirements of specification 4.0.5, each pressurizer Code safety valve shall be demonstrated OPERABLE by checking its ,

setpoint each refueling. i

)

i 1

The lift setting pressure shall correspond to ambient conditions of the. '

valve at nominal operating temperature and pressure. i i

HADDAM NECK 3/4 4-16

. 'j 1

REACTOR COOLANT SYSTEM LOW TEMPERATURE OVERPRESSURE PROTECTION' SYSTEMS LIMITING CONDITION FOR OPERATION l

3.4.9.3 At least one of the following Low Temperature Overpressure Protection (LTOP) Systems shall be OPERABLE: )

a. Two LTOP spring-loaded relief valves (SLRV) with a lift' l setting of 380 (13%) psig with their respective )

l motor-operated isolation valves in the open position, or

b. The Reactor Coolant System (RCS).depressurized with an RCS vent of greater than or equal to 7 square inches. (3 inches nominal .inside diameter).

APPLICABILITY:

MODE 4 when the temperature of any RCS cold leg of an unisolated loop is less 1 than or equal to 315'F.. MODE 5 and MODE 6 with the reactor vessel head on.

The above overpressure protection system shall be placed in service prior. to placing the RHR systeci into service and shall remain in service unless the requirements of Specification 3.4.9.3.b are satisfied. f ACTION: !

a. With one LTOP SLRV inoperable, restore the inoperable LTOP l SLRV to OPERABLE status within 7 days, or depressurize and' vent the RCS through at least a 7 square _ inch vent within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

b. With both LTOP SLRVs inoperable, depressurize and vent the RCS through at least a 7. square inch vent within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

c. In the event either the LTOP SLRVs.or the RCS vent (s) of Specification 3.4.9.3b are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30.

days. The report shall describe the circumstances initiating the transient, the effect of the LTOP SLRVs or the above RCS. vent (s) on the transient, and any corrective action necessary to prevent recurrence.

HADDAM NECK 3/4 4-46

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 n,aintained in accordance with Specification 4.4.10. j APPLICABILITY: All MODES. ,

i ACTION:

a. With the structural integrity of any ASME Code Class I 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 bactor Coolant System temperature more than 50*F above the minimum temperature required by NDTT 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 witt,in 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.

SURVEILLANCE RE0UIREMENTS 4.4.10 In addition 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.

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HADDAM NECK 3/4 4-48

_ _ _A

i CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION _

3.6.1.3 The 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 the containment, then at least on air lock door shall be closed, and

b. An overall air lock leakage rate of less than or equal to 0.05 La at Pa, 39.6 psig.

APPLICABILITY: MODES 1, 1, 3, AND 4.

ACTION:

I

a. With one containment air lock door inoperable: 1

1. Maintain at least one OPERABLE air lock door closed and I either restore the incperable 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 j c1Med; ;

1

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 STANDBY within the ner.t 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months I and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; and

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 STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN withi.i the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

i i

1 i

HADDAM NECK 3/4 6-4

3L4.7 PLANT SYSTEMS E4.7.1 TURBINE CYCLE SAFErf VALVES LIMITING CONDITION FOR OPPMION 3.7.1.1 All main steam line Code safety valves associated with each steam generator of an unisolated reactor coolant loop shall be OPERABLE with lift settings as specified in Table 3.7-1.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a. With four reactor coolant 1 % ps and associated steam generators in operation and one or more main steam line Code safety valves inoperabie, operation in MODES 1, 2, and 3 niay proceed provided that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the inoperable valve is restored to OPERABLE status; otherwise, be in 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 three reactor coolant loops and associated steam generators in operation and one or more main steam line Code safety valves associated with an operating loop 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 the inoperable valve is restored to OPERABLE status; otherwise, be in H0T STANDRY 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 .

SURVEILLANCE Rf0VIREMENTS 4.7.1.1 In addition to the requirements of Specification 4.0.5, each main steam line code safety valve associated with each steam generator shall be demonstrated OPERABLE by checking its setpoint each refueling.

1 HADDAM NECK 3/4 7-1 l

L_ -- -- --

i fj. ANT SYSTEMS j 3/4.7.5 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.5 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emittir.g material shall be free of greater than or equal to 0.005 microcurie of removable contamination.

AP11 JCABILITY: At all times.

ACTION:

a. Each sealed source with removable contamination in excess es the above limits shall be immediately withdrawn from use and either:

1. Decontaminate and repair the sealed source, or

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

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

l SURVEILLANCE RE0UIREMENTS l

l l 4.7.5.1 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 Agreement State.

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

4.7.5.2 Test Frequencies - Each category of sealed sources (excluding startup sourcei and fission detectors previously subjected to core flux) ;

shall be testeo at the frequency described below,

a. Sources in use - At least once per 6 months for all sealed sources I containing radioactive materials: 1 l 1) With a half-life greater than 30 days l (excluding Hydrogen 3), and

2) In any form other than g.4s.

l l j

l

)

HADDAM NECK 3/4 7-14 I .. i

PLANT SYSTEMS I

3/4.7.6 FIRE SUPPRESSION SYSTEMS flRE WATER SUPPLY / DISTRIBUTION SYSTEM LIMITING CONDITION FOR 0PERATI0fi )

3.7.6.1 The Fire Water Supply / Distribution System shall be OPERABLE with:

l

a. At least two high pressure fire suppression pumps, each with a capacity of 2500 gpm (at Rated Pressure), automatic start capability with their discharge aligned to the fire suppression ;

header, and i

b. An OPERABLE flow path capable of taking suction from the Connecticut River and transferring the water through distribution piping with OPERABLE sectionalizing control valves and the first valve ahead of the water flow alarm device on each sprinkler, hose standpipe or Spray System riser required to be OPERABLE per Specifications 3.7.6.2, 3.7.6.5, and 3.7.6.6.

APPLICABILITY: At all times.

ACTION:

a. With one pump inoperable, restore the inoperable pump to OPERABLE status within 7 days or provide an alternate method of supplying fire water.

b. With the Fire Water Supply / Distribution System otherwise inoperable, establish an hourly Fire Watch Patrol for the affected areas, and provide a backup Fire Water Supply / Distribution System within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or the plant shall be placed in at least Hot Standby within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in Cold Shutdown with1..

the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c. The provisions of Specification 3.0.3 are not applicable.

HADDAM NECK 3/4 7-16

p ' PLANT SYSTEMS

, SPRAY AND/0R SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.6.2 The following Spray and/or Sprinkler Systems shall be OPERABLE:

a. Sprinkler Systems

1) Maintenance shop annex (old warehouse),

2) . Turbine building, El. 21'6",

3) Turbine building mezzanine,

4) Turbine building beneath the turbine floor and under the high pressure turbine,

5) Turbine building between column lines C and D and column numbers 8 and 12 under the 59' 6" elevation *

6) Lube Oil Storage room,

7) Cable Spreading area,*

8) Primary Auxiliary building,*

9) Service Building,

?O) Chemistry Lab,

11) Machine Shop,

12) Intake Structure (diesel fuel storage room)

13) Diesel Fire Pump.

14) Service Water Pumps Water Curtain *, cnd

15) Cable Spreading Hallway Water Curtain *'

b. Deluge Spray Systems

1) High pressure turbine, (manual),

2) !!ydrogen seal oil unit, (manual),

3) Turbine lube oil reservoir, (manual) and

4) Turbine Building Crane Well (automatic).

c. Preaction Systems

1) Tarbine building mezzanine under generator,

2) Diesel Generator Room A, and

3) Diesel Generator Room B.

APPLICABILITY: Whenever systems, structures, components, or equipment protected by the spray and/or sprinkler systems are required to be OPERABLE.

ACTION:

a. With one or more of the above required Spray and/or Sprinkler Systems inoperable, within I hour establish a continuous fire watch with backup' fire suppression equipment for those. areas in which redundant systams'or components could be damaged or present an exposure fire hazard to other components (these areas are asterisked (*)); for other areas, establish an hourly. fire watch patrol.

b. The provisions of Specification 3.0.3 are not applicable. l 2

Areas where redundant systems or components could be damaged.

HADDAM NECK 3/4 7-19

i PLANT SYSTEMS CO SYSTEMS 2

l LJMITING CONDITION FOR OPERATION 3.7.6.3 The following High Pressure C0 Systems shall be OPERABLE with the 1 minimum nun.ber of storage bottles shown $ach having a net weight of not less I than 90% charge weight:

a. Cable Vault'- 18 bottles, and

b. Primary Auxiliary Building Charcoal Filters - 8 bottles.

APPLICABILITY:

Whenever systems, structures, components, or equipment protected by the High .

Pressure C02 Systems are required to be OPERABLE.

ACTION:

a. .With one or more of the above required High Pressure C0 Systems inoperable,withinIhourestablishacontinuous'firew$tchwith- i backup fire suppression equipment.

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.7.6.3 Each of the above required High Pressure C0 Systems shall be I 2

demonstrated OPERABLE:

a. At least once per 6 months by verifying 'C0 storage bottle weight to be at least 90% of full charge weight, $nd ,

b. At least once per 18 months by:

1) Verifying the system alarms and associated interlocks actuate manually and automatically upon receipt of a ' simulated test signal, and

2) Performance of an air flow test through system headers and nozzles to assure no blockage.

HADDAM NECK 3/4 7-21

. -- _. _ - __ _ - D

PLANT SYSTEMS HALON SYSTEMS

_ LIMITING CONDITIONS FOR OPERATION . _ , 3 l

l 3.7.6.4 The following Halon 1301 Systems shall be OPERABLE with the minimum number of storage containers shown each having a net weight of not less than 95% and a presttire of not less than 324 psig:

a. Switchgear Room - 8 containts,

b. Control Room - 3 containers.

APPLICABILITY: Whenever systems,' structures, components, or equipment protected by the *dalon System are required to be OPERABLE.

ACTION:

a. With one or more of the alsove required Halon 1301 Systems ino>erable, within l' hour establish a continuous fire watch with bac(up fire suppression equipment.

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0UIREMENTS .

4.7.6.4 Each of the above required Halen 1301 Systems shall be demonstrated OPERABLE:

a. At least once per 6 months by verifying each Halon storage container net weight to be at least 95% of full charge weight and with a pressure of net less than 324 psig (adjusted for temp.erature),and

b. At least once per 18 months by:

1) Verifying the system valves and associated interlocks actuate manually and automatically upon receipt of a simulated test signal, and

2) Performance of an air flow test through headers and nozzles to assure no blockage.

I HADDAM NECK 3/4 7-22

PLANT, SYSTEMS l FIREHOSEi[ATIONS 1ltllllN_6_CQ@JJION FOR OPERATION l

! i

3.7.6.5 The fire hose stations given in Table 3.7-4 shall be OPERABLE. (

1 AP_PJJCABILITY: Whenever systems, structures, components, or equipment in the j area's protected by the Fire Hose Stations are required to be OPERABLE. j hCllDEL i

a. With oae or more of the fire hose stations listed in Table 3.7 a !

inoperable, J

1) Within one hour provide a hose of equivalent capacity, or

2) Establish a continuous fire watch for the area of the Lffected hose station if the f noperable hose provides primary suppression capability and provide a hose of equivalent capacity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or

3) Establish an hourly firo watch patrol if the affected hose provides backup sepp'ression capability and provide a hose of equiv.11ent capacity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

J

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE _ REQUIREMENTS l

4.7.6.5 Each of the fire hose stations given in Table 3.7-4 shall be l clemonstrated OPERABLE:

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

b. At least once per 12 months, by:

I

1) Removing the hose for inspection, conducting a hose i hydrostatic test at a pressure of at least 50 psig above ;

maximum system pressure and re-racking, and

2) Inspecting all gaskets and replacing any degraded gaskets in the couplings.

c. At least once per 3 years, by opening each hose station valve to verify valve OPERABILITY and no flow blockage.

HADDAM NECK 3/4 7-23

l' PLANT SYSTEMS l i

YARD FIRE HYD? ANTS AND ASSOCIATED HYORANT HOSE HOUSES LIMITING CONDITION FOR OPERATION _

_ s 3.7.6.6 The yard fire hydrants and associated hydrant hose houses given in 3 Table 3.7-5 shall be OPERABLE. j APPLICABIjllli Whenever systems, structures, components, or equipment in the I areas protected by the Yard Fire Hydrants are required to be OPERABLE. !

l ACTION: j i

a. With one of more of the yard fire hydrants (and associated hydrant j hose houses) given in Table 3.7-5 inoperable, 1

1) Within one hour connect sufficient additional lengths of 2 inch diameter hose on an OPERABLE hydrant to provide i service to the unprotected area (s) if the inoperable hydrant i or hydrant hose house is the primary means of fire i suppression for any safety-related areas, or

2) Establish an hourly fire watch patrol in the safety-related area (s) protected by the inoperable hydrant or hydrant hose house if fire detection is available in the safety-related area (s) and provide the additional hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or

3) Establish a continuous fire watch in the safety-related area (s) protected by the inoperable hydrant or hydrant hose house if fire detection is not available in the area and provide the additional hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or

4) Provide additional hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months if the inoperable hydrant or hydrant hose house is the backup means of fire suppression for any safety-related area (s).

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.6.6 Each of the yard fire hydrants and associated hydrant hose houses given in Table 3.7-5 shall be demonstrated OPERABLE:

a. At least once per 31 days by visual inspection of the hydrant hose house to assure all required equipment is at the hose house, and that the hydrant is accessible and unobstructed,

b. At least once per 6 months (once during March, April or May and once during September, October or November), visually inspecting each yard fire hydrant and verifying that the hydrant barrel is dry and that the hydrant is not damaged, and HADDAM NECK 3/4 7-25

r PLANT SYSTEMS 3/4.7.7 FIRE RATED ASSEMBLIES LIMITING CONDITION FOR OPERATION 3.7.7 All fire rated assemblies (walls, floor / ceiling, cable tray enclosures, and other fire barriers) separating safety-related fire areas or ;

separating portions of redundant systems required OPEPABLE for safe shutdown !

within a fire area and all sealing devices in fire rated assembly penetrations (fire dcors, fire dampers, cable, piping, and ventilation duct penetration seals) shall be OPERABLE.

APPLICABILITY: At all times unless otherwise determined that the separation of safety-related fire areas or separating portions of redundant systems important to safe shutdown within a fire area is not required based on the MODE of operation.

ACTION:

a. With one or more of the above required fire rated assemblies and/or penetration sealing devices inoperable, within I hour:

1. Determine that the fire areas / zones on both sides of the affected fire rated assembly and/or penetration sealing device are monitored by either an OPERABLE fire detection or automatic suppression system at the fire barrier and establish a fire watch patrol that inspects both areas at least once per hour, g

2. Establish a continuous fire watch on at least one side of the affected fire rated assembly and/or penetration seal, E

3. Temporarily repair the inoperable fire rated assembly and/or sealing device with a qualified temporary assembly and/or seal and classify it as temporary.

All temporary fire rated asseablies and/or sealing devices shall be permanently repaired within 30 days, c: implement ACTION 1 or 2 above.

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.7.7.1 At least once per 18 months, the above required fire rated assemblies and penetration sealing devices shall be verified OPERABLE by performing a visual inspection of:

a. The exposed surfaces of each fire rated assembly, HADDAM NECK 3/4 7-28

PLANT SYSTEMS 3/4.7.8 FLAMMABLE LIOVIDS CONTROL LIMITING CONDITION FOR OPERATION 3.7.8 Flammable liquids in volumes greater than 1 pint shall be restricted from the control room except under the following conditions:

a. Written permission is obtained from the Supervising Control Operator or Shift Supervisor,

b. The flammable liquid is contained in a suitable

container not to exceed one quart in volume, and

c. A dedicated fire watch is assigned to the activity.

APPLICABILITY: At all times.

ACTION:

a. Upor determination that flammable liquids in volumes greater than 1 pint are contained in the control room and do not meet the conditions stated above, the flammable liquid shall be removed immediately from the control room.

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS 1

I 4.7.8 None.

A suitable container is non-spillable and has a flame arrestor in the l nozzle. l 3

)

HADDAM NECK 3/4 7-30 ,

l

_ _ - - 1

ELMLSYSTEMS 42 3/_41_lLP.HUiMYRUiLMLMILDlBk _

_C.LLA.W_P_ESJTJJ AlH 3.7.11 . . _ _ -

and in operation,The Primary Auxiliary Building Ai_

ePELIGMlWJ1:MODES 1, 2, 3 r Cleanup System shall be OPERAB movement of fuel assemblies or, and 4.

A_QJLM:

control rods within the n.

containme t.A a.

With the Primar during MODES 1,y Auxiliary Building Air Cleanup S OPERABLE 2, within the next 6 3 and status 4 restore within 7 days the inoperabl ystem inoperable

b. fol' lowing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . hours and in COLD SHUTOOWN wit n the With the Primary Auxiliary Buildi i'

or not in operation during operati ng Air Cleanup System inoperable assembliss operations or control involving movement onse rods of f within involving containment movementth of fuel

c. within the containment. suspend all uel assemblics o,r control rods The provisions of Specificati 3810LLEGLEfE18f3fflS____ on 3.0.3 are not applicable .

4.7.11 __._.___.__ .

demonstrated OPERABLE and inThe Primary Auxiliary Buildin

a. operation:g Air Cleanup System shall be At least once per 18 months r o

! maintenance (2) following majoronpainting the HEPA any filter structuralo(1) aftc ventilation zone r charcoal adsorber housings

1) communicatingorwith

, fire, chemical the: systen

. byor in an,y release

' Verifying that the cleanup sy t penetration and bypass leakage ts em satisfies the in-p less tha:.Positions Regulatory 1% and C.5 uses pa acedure the test guidance inesting accepta Guide 1.52, Revision 2, Varc s 2) is greater than 20,000 cfm; h 1978, and the syst. . C 5 Verifying em flow rate 1'

analysis o,f a representative carbwithin 31 days after re accordance with Regulatory Positi l.52, Revision 2, March 1978 on samp,lethat a laboratory obtained in 1.52, Revision 2,, meets March the

. 1978 laboratory criteria of testingon RegulatoC a of Regulatory Guide humidity, atmospheric , for a, methyl pressurof todide less than 10% a penetration velocity in accordai.ce with e, and ASTM 40 803; and fect/03 min. faceons of 860F, 95 HADDAM NECK 3/4 7 34

i

! PLANT SYSTEMS I 3/4.7.11 PRIMARY AUXILIARY BUILDING AIR CLEANUP SYSTEM LIMITING CONDITION FOR OPERATION l !

3.7.11 The Primr y Auxiliary Building Air Cleanup System shall be OPERABLE and in operation. '

APPLICABILITY: MODES 1, 2, 3, and 4. Also, during operations involving {

movement of fuel assemblies or control rods within the containment.

ACTION:

a. With the Primary Auxiliary Building Air Cleanup System inoperable during MODES 1, 2, 3 and 4 restore the inoperable system to OPERABLE status within 7 days 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With the Primary Auxiliary Building Air Cleanup System inoperable or not in operatinn during operations involving movement of fuel assemblies or control rods within the containment, suspend all operations involvtag movement of fuel assemblies or control rods within the containment.

c. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.7.11 The Primary Auxiliary Buildii;3 Air Cleanup System shall be domanstrated OPERABLE and in operation:

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

1) Verifying %at tne cleanup system sat sfies the in-place i

penetration and bypass leakage testing ocaotance criteria of less than 1% and uses the test procedure guicace in Regulatory Positions C.S.a, C.5.c, and C.S.d oi Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is greater than 20,000 cfm;

2) Verifying, within 31 days after removal, that r. laboratory analysis of a representative carbon sample obtained in l accordance with Regulatory Position C.6.b or Regulatory Guide 1.52, Revision 2, Mard 1978, meets the lekoratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a meth 1 iodide penetration of less than 10% at test conditions of 8PF, 95% relative !

humidity, atmospheric pressure, and 40 feet / min. face velocity in accordance with ASTM D3803; and HADDAM NECK 3/4 7-34 I

h REFUEL)iiG OPERATIONS ,

3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING !

I LIMITING CONDITION FOR OPERATION 3.9.7 Loads other than fuel assemblies in excess of_1650 pounds. shall be prohibited from travel over fuel assemblies in the storage pool.

APPLICABILITY: With fuel a;semblies in the storage pool.

ACTION:

.i

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

b. The provisions of Specification 3.0.3:are not applicable.' l SURVEILLANCE RE0VIREHENTS 1

4.9.7 Administrative controls regarding the movement of. loads in the Spent Fuel Storage Pool Building shall be adhered to by all personnel involved with lifting a load in excess of 1650 pounds.

l l

I l

HADDAM NECK 3/4 9-7

j REFUELING OPERATIONS 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM i

LIMITING CONDITION FOR OPERATION 3.9.9 The containment purge bypass and exhaust isolation valves shall be OPERABLE.

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

ACTION:

a. With the requirements of the above specification not satisfied,-

immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel'in the containment building,'other than placing an irradiated fuel assembly into a safe storage location,

b. The provisions of Specification 3.0.3 are not applicable.

1 i

SURVEILLANCE RE0VIREMENTS I 4.9.9 The containment purge bypass and exhaust isolation valves shall be i verified 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 and prior to movement of irradiated fuel i within containment by verifying that containment purge, bypass or exhaust ;

isolation valves are accessible for manual operation or. verifying that the 4 associated penetrations are blind flanged. ;

l HADDAM NECK 3/4 9-10 o__-_-_---- - - - - _ _ _ - _ - - _ - _ - - - - - - _ - - - - - u

i REFUELING OPERATIONS 1 i

3/4.9.11 WATER LEVEL-STORAGE POOL LIMITING CONDITION FOR OPERATION 3.9.11 At least 21 feet of water shall be maintained over the top of i irradiated fuel assemblies seated in the storage racks. !

l i

APPLICABILITY: Whenever irradiated fuel assemblies are in the storage pool. 1 ACTION:

a. With the requirements of tne above specification r.ot satisfied, .i suspend all movements of fuel assemblies and crane operations with loads in the fuel storage areas and restore the w-ter 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 Specification 3.0.3 are not applicable.

SVRVE1LLANCE RE0VIREMENTS l

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. l 1

J i

HADDAM NECK 3/4 9-12

REFUELING OPERATIONS 3/4.9.12 FUEL STORAGE BUILDING AIR CLEANUP SYSTEM LIMITING CONDITION FOR OPERATION 3.9.12 The fuel Storage Building Air Cleanup System shall be OPERABLE and in operation. _

APfl1CABILITY: -During operation:; involving rnovement of fuel within the storage pool or crane operation with loads over the storage pool.

ACTION-

a. With the fuel Storage Building Air Clecnup System inoperable, or not operating, suspend all operations involving movements of fuel within the stcrage pool or crane operation with loads over the storage pool.

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0V!REMENTS 4.9.12 The Fuel Storage Boliding Air Cleanup System shall be demonstrated OPERABLE and in operation:

a. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or

(?) following painting, fire, or chemical release in any ventilation zone communicating with the system by:

1) Verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 1% and uses the test procedure guidance in Regulatory Positions C.S.a, C.5.c, and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 4000 cfm 10%;

2) Verifying, within 31 days after removal, that a labcratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide l 1.52, Revision 2, March 1978, for a methyl iodide penetration l of less than 4%; and

3) Verifying a system flow rate of 4000 cfm 10% during system operation when tested in accordance with ANSI N510-1975.

HADDAM NECK 3/4 9-13

{

RADIOACTIVE EFFLUENTS DOSE. LIOUIDS i LIMITING CONDITION FOR OPERATION j 3.11.1.2 The dose or dose commitment to any MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from the site (see Figure 5.1-1) shall be limited:

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

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

APPLICABILITY: At all times.

I 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 6.9.2, a Special Report wnich identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be-taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and ,

during the remainder of the calendar year so that the cumulattve dose or dose commitment to any MEMBER OF THE PUBLIC from such release during the calendar year is within 3 mren, to the total body and 10 mrem to any organ. i l

b. The provisions of Specification 3.0.3 are not applicable. I SURVEILLANCE RE0VIREMENTS 1

i 4.11.1.2.1 Cumulative dose contributions from liquid effluents shall be I I

determined in accordance with Section II of the REM 00CM..

4.11.1.2.2 Relative accuracy or conservatism of the calculations shall be l confirmed by performance of the Radiological Environmental Monitoring l Program as detailed in the REMODCM. l i

I l

HADDAM NECK 3/4 11-2 i

RADI0 ACTIVE EFFLUENTS DOSE-NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose offsite (see Figure 5.1-1) due to noble gases released in gasecus effluents shall be limited to the following:

a. During any calendar quarter, to less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta ,

radiation, and

b. During any calendar year to less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad 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 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents during the remainder of the current calendar quarter and during the remainder of the calendar year so that the cumulative dose during the calendar year is within 10 mrad for gamma radiation and 20 mrad for beta radiation,

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.11.2.2.1 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with Section II of the REM 0DCM once every 31 days.

4.11.2.2.2 Relative accuracy or conservatism of the calculations shall be confirmed by performance of the Radiological Environmental Monitoring Program as detailed in Section I of the REMODCM.

HADDAM NECK 3/4 11-4

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RADIOACTIVE EFFLUENTS DQSE. RADIOI0 DINES. RADI0 ACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES j i

LIMITING CONDITION FOR OPERATION i

l 3.11.2.3 The dose to any MEMBER OF THE PUBLIC from Iodine-131, Iodine-133,

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tritium end raoloactive materials in particulate form with half lives greater than 8 days in gaseous effluents released offsite (see Figure 5.1-1) shall be limited to the following:

a. Luring any calendar quarter to less than or equal to 7.5 mrem to any organ;

b. During any calendar year to less than or equal to 15 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radionuclides, radioactive materials in particulate form, or radionuclides other than noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases during the remainder of the current calendar quarter and during the remainder of the calendar year so that the cumulative dose or dose commitment to any MEMBER OF THE PUBLIC from such releases during the calendar year is within 15 mrem to any organ. i l

b. The provisions of Specification 3.0.3 are not applicable. l SURVEILLANCE RE0VIREMENTS 4.11.2.3.1 Cumulative dose contributions for the current calendar quarter !

and current calendar year shall be determined in accordance with Section II ;

of the REM 0DCM once every 31 days.

4.11.2.3.2 Relative accuracy or conservatism of the calculations shall be confirmed by performance of the Radiological Environmental Monitoring Program as detailed in the REM 0DCM.

HADDAM NECK 3/4 11-5

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RADIOACTIVE EFFLUENTS 3/4.11.3 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.3 (except the thyroidis limited to lessorthan any or or equal to 25 a period of 12 conse,cutive months.which is limited to less over than or equal to 75 m APPLICABILITY: At all times.

ACTION:

a.

With thegaseous in liquid or Specification calculated dose effluents from the exceeding twicerelease of radioac theaslimits of 3.11.1.2, 3.11.2.2, or 3.11.2.3, prepare and submit a Special Report to Commission pursuant to Specification 6 9 2 a limit the subsequent releases such that the dose or dose ..

commitment from the site to any MEMBER OF THE PUBLIC is lim less than or equal to 25 mrem to the total body or any organ (except thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months. (

This Special Report shall from the site to any MEMBER OF es uent THE PUBLIC pathways Standard. and direct radiation) are less than the 40 CFR Part 190 If the estimated doses exceed the above limits, the special report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190.

Submittal of b.

granted until staff action on the request is complet .

s The provisions of Specification 3.0.3 are not applicable .

SURVEILLANCE RE0VIREMENTS 4.11.3 4.11.2.2.1 and 4.11.2.3.1 direct radiationn sshall ...,

and be determin once per 31 days. and in accordance with Sectio 4 11 1 2 1 i :: of the REMODCM HADDAM NECK 3/4 11-6

RA_Q10 ACTIVE EFFtVENTS i

3/4.11.3 TOTAL DOSE

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i LIMITING CONDITION FOR OPERATION j i

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3.11.3 The dose 6r dose conimitment from the site to a MEMBER OF THE PUBLIC i is limited to less than or equal to 25 mrem to the total body or any organ 1 (except the thyroid, which is limited to less than or equal to 75 mrem)-over i a period of 12 consecutive months. !

APPLICABILITY: At all times.

ET.I@

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a. With the calculated dose from the release of radioactive materials- '!

in liquid or gaseous effluents exceeding twice the limits of .

Specification 3.11.1.2, 3.11.2.2, or 3.11.2.3, prepare and submit a Special Report to Commission pursuant to Specification 6.9.2 and limit the subsequent releases such that the dose or dose commitment from the site to any MEMBER OF THE PUBLIC is limited to less than or equal to 25 mrem to the total body or any organ-(except thyroid, which is limited to less than or equal'to 75 mrem) over 12 consecutive months. This Special Report shall include an analysis which demonstrates that radiation exposures from the site to any MEMBER OF THE PUBLIC (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard. If the estimated doses exceed the above limits, the special report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete..

b. The provisions of Specification 3.0.3 are not applicable. I SURVEILLANCE RE0VIREMENTS i 4.11.3 Cumulative dose contributions from liquid and gaseous effluents and l direct radiation shall be determined in Specifications 4.11.1.2.1, ,

4.11.2.2.1 and 4.11.2.3.1 and in accordance with Section II of the REM 0DCM i once per 31 days.

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I HADDAM NECK 3/4 11-6 I

- _ - - - - - - - - I

. Docket No. 50-213 813295 Attachment 2 Haddam Neck Plant Technical Specification Section 3.0/4.0 Limiting Conditions for Operation and Surveillance Requirements Section 3.4.6.2 - Reactor Coolant System -

Operational Leakage t

July 1989 1

Docket No. 50-213 B13295 1

Section 3.0/4.0 Limiting Conditions for Operation and Surveillance Requirements i,

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1 July 1989 i

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- t Attachment 2 P ?.95/Page 1

5. icn 3.0/4.0 Technical Specification Section 3.0/4.0 Limitina Conditions for Operation and Surveillance Requirements The proposed kfS Sections 3.0.1 thru 3.0.3 establish general requirements applicable to all Limiting Conditions for Operation (LCO). Section 3.0.1 requires compliance with all Section 3 LCOs during the modes in which they are applicable, or compliance with the associated ACTION requirements. Section 3.0.2 defines noncompliance with a specification as a failure to meet an LC0 and its ACTION requirements within the specified time interval. Section 3.0.3 specifies shutdown requirements and time limits which are applicable when an LC0 is not met and there are no specified ACTION requirements or the ACTION requirements are not met. All of these requirements are consistent with the intent of the existing Technical Specifications.

t The proposed RTS Section 3.0.4 would prohibii entry into an OPERATIONAL MODE or other specified condition when the requirements of an !CO are not met and the assoc' ated ACTION statement requires a shutdown if tne LC0 is not met within a specified time interval. Entry into an OPERATIONAL MODE (e.g. -

startup) may be made while still subject to ACTION requirement', (LCO not met) provided that conformance to the ACTION requirements would permit continued operation for an unlimited period of time. The intent of this specification is to ensure that startup is not allowed in a condition where essential equipment is inoperable and a shutdown may be required. However, some Tech-nical Specifications relate to systems, components, or litits which are not related to the plants' design basis, and thus do not have any impact on safe i

operation (e.g. - T.S. 3.9.7, Crane Travel - Spent Feel Storage Building).

Also, other Technical Specification ACTION requirements specify compensatory measures which provide a level of safety comparable to the LCO requirement (e.g. - T. S. 3.4.10, Structural Integrity). In all of these cases, since (

unlimited continued operation is allowed, startup while subject to these i ACTION requirements should also be allowed. The proposed RTS Section 3.0.4 '

specifically allows this. The proposed RTS Section 3.0.4 ensures that startup/ operation is only initiated when the complement of equipment required to ensure conformance with the design basis, as cpecified in the LCOs, is ;

fully operable. Alternately, if that equipment is either not necessary to 1 mitigate a design basis accident or equivalent compensatory measures are required, then startup/ operation is allowed. This is consistent with design basis requirements and there is no impact on the consequences of any accident as a result of this change.

As a result of the proposed RTS Section 3.0.4, a number of changes IAttach-ment 1A) were also required to individual LCOs/ ACTION requirements to ensure the intent of Section 3.0.4 is met. These changes are required due to the fact that those specifications had been proposed based on a version of the H Standard Technical Specifications that contain a different H Section 3.0.4.

The version of Section 3.0.4 proposed here is consistent with the changes recommended by the NRC in Generic letter 87-09. The changes to previously

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proposed Section 3 Technical Specifications (specific Technical Specification 1 Section identified in Attachment 1A) consist primarily of deleting the exist-ing requirements of Section 3.0.4 which are no longer necessary to meet the {

j intent. The other changes of the proposed Section 3.0.4 is maintained. Since -

the requirements of the proposed RTS Section 3.0.4 are consistent with

Attachment 2 '

B13295/Page 2 Section 3.0/4.0 assumptions used for the desigt basis, these changes will have no impact on the consequences of any accident.

Proposed RTS Section 4.0.1 simply requires that survei llance requirements associated with a Limiting Condition for Operation be met during the GPERA-TIONf L MODE specified for the LCO. This change has no impact on the conse- l quences of any accident.

{

It is noted that the proposed RTS Section 4.0.2 is equivalent to the existing Technical Specification Section 4.1. i Proposed RTS Section 4.0.3 defines the failure to perform a surveillance requirement within the allowed surveillance interval as noncompliance with the operability requirements of the LCO, with the ACTION requirements applicable at that time. However, the proposed RTS Section 4.0.3 would allow a delay of up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit completion of a missed surveillance when the allow-able outage time limits of the applicable ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . This delay would apply only in the event of a missed surveillance and would not apply to a failed surveillance.

The purpose of the delay in implementing the ACTION requirements is to allow a sufficient time to complete the required surveillance, recognizing tnet a missed surveillance is much less significant than a failed one. The vast majority of surveillance show equipment to me operable. Thus, it is highly likely that a missed surveillance, had it been completed, would have simply confirmed that the component was operable. Assuming that equipment is inoper-able merely because a surveillance has not been performed is overly conserva-tive. Without the proposed 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months delay, a missed surveillance would require that the applicable ACTION requirements be immediately applied and that a shutdown be initiated. Requiring a change in plant conditions, even a con-trolled plant shutdown, has the potential for resulting in a challenge to the same equipment that the surveillance was not performed on and that 'as assumed to be inoperable. Given that the majority of surveillance performed do not identify equipment problems and given the potential for causing challenges to other equipment by a forced shutdown, it is concluded that the proposed 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months delay for implementing ACTION requirements would have no impact on equipment operability and thus have no impact on the consequences of any accident- ,

The proposed RTS Section 4.0.4 requires that surveillance requirements asso-ciated with an LC0 be met prior to entry into a mode in which the LCO is applicable. The purpose of this specification is to demonstrate operability of essential systems and components prior to placing the plant in a condition (mode) for which the system or component is assumed capabb of performing its safety function. . Therefore, the proposed change ensures that essential equipaent is available to respond at assumed in the design basis, and there is no hpact on the consequences of any design basis accident.

It is noted that the proposed RTS 4.0.5 is equivalent to the existing Tech-nical Specification Sections 4.10A and 4.10B and Section 4.0.6 is equivalent to the existing Technical Specification Section 4.12.

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1 Attachment 2 BI3295/Page 3 i Section 3.0/4.0 i Significant Hazards Consideration i

In accordance with 10CFR50.92, CYAPC0 har reviewed the proposed RTS sections i and has concluded that they do not involve a significant hazards considera- .

tion. The basis for this conclusion is that the three criteria of -

10CFR50.92(a) are not compromised. The proposed RTS do not involve a signifi- )

) cant hazards consideration because the change:: would not:

1) Involve a significant increase in the probability or consequences of any accident previously evaluated. The proposed RTS Section 3.0 establish general requirements related to Limiting Conditions for Operation. These requirements provide assurance that plant operation is consistent with design basis assumptions, and therefore have no impact on probability or consequences of an accident. The proposed RTS Section 3.0.4 will allow entry into an operational mode while subject to the provisions of ACTION requirements, but only when those ACTION requirements would allow contin-ued operation for an unlimited period of time. The Technical Specifica-tions in this category consist of ones which deal with equipment or components that are not required for mitigating design basis events or ones in which the ACTION requirements specify compensatory measures which provide a level of safety equivalent to the Limiting Conditions for Operation. In these cases, entry into the ACTION requirements during power operation would not require a shutdown, and thus there is no technical basis for preventing startup in this condition.

The proposed RTS Section 4.0 establish general requirements related to surveillance performed on equipment that is subject to Limiting Condi-tions for Operation. These requirements ensure that equipment and systems that are required to mitigate design basis accidents are tested f

prior to operation and at specified intervals thereafter. This provides assurance that equipment is operable and capable of responding as assumed in the design basis. Therefore, there will be no impact on the probabil-ity or consequences of any accident.

I The proposed RTS Section 4.0.4 will allow a delay of up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in implementing ACTION requirements in the event of a missed surveillance (due to equipment being declared inoperable) when the allowable outage time of the ACTION requirements is less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Since the vast majority of surveillance performed demonstrate equipment to be operable, assuming that equipment is inoperable simply due to a missed surveillance is overly conservative. Since this delay will apply only when a 1,urveil-lance is missed and not in the event of a failed surveillance, there is no increase in the time allowed for continued operation with equipment known to be inoperable. Further, allowing a delay of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in which I

to complete the surveillance (which will likely demonstrate the equipment or component to be, in fact, operable) avoids the potential for a forced shutdown that could possibly challenge the same equipment on which the surveillance had not been performed.

l The rest of the proposed changes to individual Technical Specifications I are necessary to ensure that the intent of the specification does not change as a result of the changes to Section 3.0.4. As such, they will have no impact on the probability or consequences of any accident.

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Attachment'2

. .B13295/Page 4

'Section 3.0/4.0 ,

2. Create the possibility of a new or different kind.of accident. None of the proposed changes affect the way the plant is operated .or alter its response, nor do they introduce any new failure modes.

3. Involve a significant reduction in a margin ' of safety. .The proposed changes do not impact-the consequences.of any. accident. Also, they have.

no adverse impact on any of the protective boundaries. Therefore, there-can be no impact' on any-margin of' safety.

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Attachment 2'

. 81329S/Page 1 Section 3.4.6.2 Technical Specification Section 2.4.6.2, Reactor Coolant System - Operation Leakage The proposed revised Technical Specification (RTS) Section 3.4.6.2 and corre-sponding bases section have been proposed by converting the existing Technical Specification Section 3.14, " Primary System Leakage" and Dection 4.4.III,

" Recirculation System" to a format consistent with the Westinghouse Standard In addition, the requirements of Adminis-Technical Specifications trative Technical (W STS()3.) Section 4.4.III.B have also been included.

Specification The proposed changes are compared to the existing Technical Specifications'and the W STS. A matrix summarizing this comparison is included in Attachment 3.

The proposed RTS section pertains restrictions on plant operation due to leakage from the following systems:

1. Reactor Coolant System (RCS)

2. Chemical and Volume Control System (CVCS)

3. Residual Heat Removal (RHR) System, and

4. High Pressure Safety Injection (HPSI) System The proposed RTS section is equivalent to the existing Technical Specifica-tions with the following exceptions:

1. Leakaoe from the portions of HPSI outside containment used for recircula-tion has been included in the limiting condition for operation (LCO) for combined leakage (RTS Section 3.4.6.2.f). This is a r.ew requirement.

2. New Surveillance Requirements have been added to the proposed RTS:

a. Monitoring containment atmosphere radioactivity (Section 4.4.6.2.1.a),

b. Mor R -ing containment sump inventory (4.4.6.2.1.b),

I

c. Haitor ing volume control tank level (4.4.6.2.1.c),

d. Performance of RCS water inventory balance (4.4.6.2.1.d), and

e. Monitoring reactor head flange Irakoff (4.4.6.2.1 e).

These new surveillance requirement are provided to ensure that the applicable LC0 specifications are properly monitored and are based on the M STS and the associated leak detection system requirements of RTS Section 3.4.6.1.

(1) Administrative Technical Specifications at the Haddam Neck Plant are I administrative procedures that were implemented as an interim measure .

prior to converting the Technical Specifications to the M STS format. I i

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Sectio' 3.4.6.2 - Reactor Coolant System Operational Leakege 1

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Attachment 2 E13295/Page 2 Section 3.4.6.2

3. A new surveillance requirement has been added (Section 4.4.6.2.1.f) to ;

monitor leakage from RPR, HPSI and portions of CVCS at least once per 12 '

hours. The existing Technical Specification (Section 4.4.III.A.2 and D) specifies this on a monthly basis. This is a new requirement and is consistent with current plant surveillance procedures.

Significant Hazards Consideration In accordance with 10CFR50.92, CYAPC0 has reviewed the proposed RTS sections and has concluded that they do not involve a significant hazards considera-tion. The basis for this conclusion is that the three criteria of IOCFR50.92(c) are not compromised. The proposed RTS do not involve a signifi-cant hazards consideration because the changes would not:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated. The- determination of whether or not a proposed change is equivalent, more restrictive _ (or a new requirement),

or less restrictive is based on the Limiting Condition fcr Operation and Applicability Requirements since it is these requirements. which will impact the design basis accidents. In general, the conversion to the W STS yields more extensive and/or restrictive Action and Surveillance Requirements. As described above, most of the changes are more restric-tive in that they are a conservative change and there are no comparable requirements in the existing Technical Specifications. This will help ensure the operability and reliability' of the systems covered under the proposed RTS. Based upon the above discussion, the proposed RTS will not increase the probability or consequences of .any accident previously analyzed.

2. Create the possibility of a new or different kind of accidant from any previously evaluated. Since there are no hardware modifications associ-ated with the proposed changes, the performance of safety-related systems remains unaffected during operations. The operability requirements are increased over the current requirements thus enhancing the performance of safety systems. Therefore, the propned RTS Will not modify the plant response to the point where it can be considered a new accident nor are any credible failure modes created.

3. Involve a significant reduction in a margin of safety. Because the changes proposed herein provide acceptable results for the design basis accident, no additional burden will be placed on the protective bounda-ries for postulated accidents. In addition, there are no plant modifica-tions associated with these changes and hence, there is.no direct-impact on the protective boundaries. The proposed RTS do not affect the safety limits of the protective boundaries and the bases of the proposed RTS have been modified to reflect the proposed changes.

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I4 Docket No. 50-213 {

B13295 )

i 1

l Attachment 3 Technical Specification Comparison Matrix July 1989 i I

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Attachment 3

,- Page 1 1

TECHNICAL SPECIFICATION COMPARISON MATRIX i

Introduction The Technical Specification Comparison Matrix (TSCM) was prepared to facilitate the revision of the existing Haddam Neck Technical Specifications (T.S.). The TSCM is set up denoting the proposed Technical Specification section numbers in the left hand column followed by a short description.

The next column lists the corresponding existing T.S. section number. The .

final two columns compare the requirements contained in the proposed section I with the existing T.S. and the Westinghouse STS, respectively. The key at the bottom of each page provides an explanation for the symbols located in i the two comparison columns. The equivalent notation "E" may either denote l that exact wording has been transposed from the existing T.S. or different j verbage conveying equivalent requirements has been used. In many cases, '

there was not a one-for-one relationship, but rather multi-section relationships, whereas the requirements in a given T.S. section may be divided between several different sections in the proposed Technical ,

Specification. The additional requirement notation "4+" denotes that the !

proposed Technical Specification is more restrictive because it is an entirely new requirement as compared to the existing T.S. or it is more restrictive in the sense that the existing T.S. requirements have been changed such that they are more restrictive. This matrix is provided in a summary fashion and highlights the more significant changes. A detailed comparison in terms of additional requirements and/or less restrictive requirements is provided in Attachment 2 of this submittal.

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Attachment 3

-' Page 2-3.0/4.0 .

LIMITING' CONDITION FOR OPERATION'AND SURVEILLANCE REQUIREMENTS TECHNICAL SPECIFICATION COMPARIS0N MATRIX Comparison ' Comparison Existing With Existing With W T.S. ' # Description ' L f_._ - T.S. # STS 3.0.1 Applicability 3.1 ++ ~E 3.0.2 Applicability -

++ E 3.0.3 Applicability -

++ E 3.0.4 Applicability _

++ . ++(1)-

4.0.1 4.1 ++ E 4.0.2 4.1 E E i 4.0.3 ~

++- ++(1) 4 4.0.4 ++ ++(1)-

i 4.0.5 4.10.A, B E~ *(2) 4.0.6 4.12 E ++

Notes .

E - Equivalent Requirements

++ - Additional Requirements .. .

(1) The proposed RTS Section is. consistent with the . recommendation of Generic Letter 87-09 whereas the W STS does not include those recommendations. >

(2) Since the Haddam Neck Plant was built prior.: to the implementation- of code classification, a word " equivalent" is added to "ASME Code. Class '

1, 2, and 3" components.

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Attachment 3'

[v Page 3 3/4,4 RNACTOR COOLANT SYSTEM 3.4.6.2 OPE .MION LEAKAGE 1 lECHNICAL SPECIFIC $ TION (QMPARIS0ri MATRIX l

t

., . Comparison Comparison Existing' With Existing With W. :)

T.S. # Description T.S. T.S. # STS -l i

3.4.6.2 Operation Leakage- j

a. No Pressure Boundary 3.14.A.4 E ,

E Leakage

b. Unidentified Leakage 3,14.A.1 E E.

c. $G Tube Leakage 3.14.A.E E ++

d. Identified teakage 3.14.A.2 E E

e. RHR Pump Seal Leakage 4.4.III.B. E D

f. Combined Leakage 3.14.A.3 E D

g. ECCS Valve Leakage 3.14.A.6 F D Applicability 3.14 E E Action a 3.14.8.1- E E Action b 3<14.B.2 E E 1

Action c 3 . ~14,. B . 3 E ++ !

Action n 4.4.III.B E D Admin. 1 I

4.4.6.2 Demonstrated Operable 1 i

Surveillance a -

++ E- l Surveillance b -

++ E -

i

. Surveillance c _

++ ++ ,

!- 3 Surveillance d ++ ++ 1 i

Surveillance e -

++ E Surveillance f 4.4.III.A ++ ++

l Surveillance g 4.4.III.A & D +<- ++ 'I Surveillance h 4.3.F E' <+ '

u i

. b

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

4 At~;a :hment 3 Paje 4 Eql.41 Y -

Equivalent Requirements

++ - Additional Requirements D - Different Requirements 4

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i Docket No. 50-213 l

.B13295 i

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Attachment 4 ,

i Haddam Neck Plant i Existing Technical Spet ifications l Cross Referents. .{

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i July 1989 i

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. 1 4 )

Existina T.S. # Description Proposed RTS

]

3.14 Primary System Leakage 3.14.A.1 Unidentified Leakage 3.4.6.2.b 3.14.A.2 Identified Leakage 3.4.6.2.d 3.14.A.3 Combined Leakage 3.4.6.2.f 3.14.A.4 No Pressure Boundary Leakage 3.4.6.2.a !

3.14.A.5 Steam Generator Tube Leakage 3.4.6.2.c 1

3.14.A.6 ECCS Valves Leakage 3.4.6.2.g 3.44.B.1 Action for Pressure Boundary 3.4.5.2 Action (a)

Leakage 3.14.B.2 Action for Other Leakage 3.4.6.2 Action (b) 3.14.B.3 Action for SG Tube Leakage 3.4.6.2 Action (c) 4.4.111 Recirculation System l 4.4.III.A Recirculation System Test 4.4.6.2.1.g )

4.4.6.2.1.f 4.4.III.B Acceptance Criteria 3.4.6.2.e 4.4.III.C Corrective Actions 3.4.6.2 Action 4.4.III.D Test Frequency 4.4.6.2.1.g Admin. 4.4.III.B Acceptance Criteria 3.4.6.2 Action d

B13295, Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements & RCS Operational Leakage

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