ML20155G006

Proposed Tech Specs Correcting Amend Number on Pages Not Changed by Amend 193

ML20155G006
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	10/30/1998
From:	CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20155G001	List: CY-98-183, Forwards Revised License Amend 193 TS Pages to Correct Amend Number on Pages Not Changed by Amend 193.No Commitments Contained within Ltr ML20155G006
References
NUDOCS 9811060179
Download: ML20155G006 (34)

Text

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A April 26, 1990 IABLE 4.3 4 SEISMIC HONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG CHANNEL CHANNEL CHANNEL OPERATIONAL INSTRUMENTS AND SENSOR LOCATIONS QiECK CALIBRATION TEST l.

Triaxial Servo Accelerometer M

R SA (SSA 302) Basemat Cable Vault 2.

Digital Cassette Accelerograph H

R SA 1

(DCA 300)**

3.

Response Spectrum Analyzer M

R SA (RSA 50)**

4.

Playback System M

R SA (SMR 102)**

5.

Seismic Warning Panel M

R SA (SWP 300)**

• • All located in the Control Room

$kIOIooN UMN13 W

PDR HADDAM NECK 3/4 3 29 Amendment No.125 T5353.00C

- - -. ~ - - - -

April 26, 1990 TABLE 3.3 6 HETEOR0 LOGICAL MONITORING INSTRUMEMTATION MINIMUM INSTRUMENT / LOCATION OPERABLE 1.

Wind Speed a.

Baseline Elev. 33' 1

I b.

Nominal Elev. 200' 1

. 2.

Wind Direction a.

Baseline Elev. 33' 1

b.

Nominal Elev. 196' 1

3.

Air Temperature a.

Baseline Elev. 33' 1

4.

Delta T*

-a.

Nominal Elev.120' 1

b.

Nominal Elev. 200' 1

Delta T is the air temperature of the nominal elevation minus the air temperature at the 33' baseline elevation.

i HADOAM NECK

.3/4 3 31 Amendment No.125 TS353.00C v

I TABLE 4.3 5 METEOROLOGICAL HONITORING INSTRUMENTATION SURVEILLANCE REQUIREtiEt[IS INSTRUMENT / LOCATION CHANNEL CHECK CHANNEL CALIBRATION 1.

Wind Speed a.

Baseline Elev. 33' D

SA b.

Nominal Elev, 200' D

SA 2.

Wind Direction a.

Baseline Elev. 33' D

SA b.

Nominal Elev.196' D

SA 3.

Air Temperature a.

Baseline Elev. 33' D

SA 4.

Delta T*

a.

Nominal Elev.120' D

SA b.

Nominal Elev. 200' D

SA Delta T is the air temperature of the nominal elevation minus the air temperature at the 33' baseline elevation.

t 2

HADOAM NECK 3/4 3 32 Amendment No.125 TS3S3.00C

April 26, 1990 TABLE 3.3 10 (Continued)

ACTION STATEMENTS ACTION 50 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, releases via the Waste Gas Holdup System may continue provided that best efforts are made to repair the instrument and that prior to initiating the release:

(a)

For the tank to be discharged, at least two independent samples of the tank's contents are analyzed: and, (b) The release rate calculations and discharge valve lineups are independently verified by a second individual.

Otherwise, suspend releases from the Waste Gas Holdup System.

Releases from all pathways other than the Waste Gas Holdup System may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for gross radioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 51 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that best efforts are made to repair the instrument and that samples are continuously collected with auxiliary sampling equipment for periods of seven (7) days and analyzed for principal gamma emitters with half lives greater than 8 days within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after the end of the sampling period. Auxiliary sampling shall be established within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of declaring the channel INOPERABLE.

With the number of channels OPERABLE less than required by ACTION 52 the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that the best efforts are made to repair the instrument and that the flow rate is estimated once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

HADDAM NECK 3/4 3 51 Amendment No.125 TS353.00C

3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.1 The boron concentration of all filled unisolated portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure a K.fr of 0.94 or less.

~ APPLICABILITY:

MODE 6*.

ACTION:

With the requirements of the above specification not satisfied immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at greater than or equal to 30 gpm of a solution containing a minimum of 14000 ppm boron or its equivalent until K,rr is reduced to less than or equal to 0.94.

SURVEILLANCE REQUIREMENTS 4.9.1.1 The above reactivity condition shall be determined prior to:

i a.

Removing or unbolting the reactor vessel head, and b.

Withdrawal of any control rod in excess of 3 feet from its fully inserted position within the reactor vessel except when control rod drag testing is being performed, at which time the reactivity condition shall be determined prior to the first control rod withdrawn in excess of 3 feet and every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereafter until completion of the testing.

4.9.1.2 The boron concentration of the Reactor Coolant System and the refueling canal shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

The reactor shall be maintained in H0DE 6 whenever fuel is in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

HADDAM NECK 3/4 9 1 Amendment No.125 TS359,00C

s May 27, 1993 REFUELING OPERATIONS 3/4 9.2 INSTRUMENTATION l

LIBII1NG CONDITION FOR OPERATION 3.9.2.a As a minimum, two Source Range Neutron Flux Monitors shall be OPERABLE and operating, each with continuous visual indication in the control room and one with audible indication in the containment and control room when CORE ALTERATIONS or positive reactivity changes are taking place.

When CORE ALTERATIONS or positive reactivity changes are not taking place.

at least one Soun.e Range Neutron Flux Monitor shall be OPERABLE and i

operating with a visual indication in the control room and audible indication in the containment.

3.9.2.b As a minimum, two Source Range High Neutron Level Alarms (Containment Evacuation) shall be OPERABLE and operating with a minimum i

logic to audibly alarm in both the control room and containment of one (1) of two (2).

i AEELICABILITY:

MODE 6.

l ACTION:

a.

With one of the above required monitors inoperable or not operating, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

b.

With both of the required monitors inoperable or not operating, determine the boron concentration of the Reactor Coolant System at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

, SURVEILLANCE REQUIREMENTS 4.9.2 Each Source Range Neutron Flux Monitor shall be demonstrated OPERABLE by performance of:

a.

A CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.

An ANALOG CHANNEL OPERATIONAL TEST within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the initial start of CORE ALTERATIONS, and c.

An ANALOG CHANNEL OPERATIONAL TEST at least once per 7 days.

HADDAM NECK 3/4 9 2 Amendment No.42644h158 T5359.00C 1

s REFUELING OPERATIONS January 22. 1996 j

3/4.9.3 DECAY TIME LIMITING CONDITION FOR OPERATION 3.9.3.a The reactor shall be subcritical for at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.

l 3.9.3.b Irradiated fuel shall remain in the reactor vessel for at least the time required in Figure 3.91 prior to movement to the spent fuel pool.

APPLICABILITY: During movement of irradiated fuel in the reactor vessel.*

l ACTION:

With the reactor subcritical for less than 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, suspend all a.

operations involving movement of irradiated fuel in the reactor vessel, b.

With the combination of reactor hold time and cooling water temperature in the unacceptable region of Figure 3.91. suspend all operations involving movement of irradiated fuel from the reactor vessel to the spent fuel pool until the combination of reactor hold time and cooling water temperature return to the acceptable region of Figure 3.91.

SURVEILLANCE REQUIREMENTS 4.9.3.1 The reactor shall be determined to have been subcritical for at l

least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> by verification of the date and time of subcriticality prior to movement of irradiated fuel in the reactor vessel.

4.9.3.2 Verify that the combination of reactor hold time and cooling water temperature are in the acceptable region of Figure 3.91 prior to and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during transfer of irradiated fuel from the reactor vessel to the spent fuel pool.

• • Specification 3.9.3.b does not apply if less than 53 fuel assemblies are transferred to the spent fuel pool.

HADOAM NECK 3/4 9 3 Amendment No.1Mr188 TS359.00C

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January 22, 1996

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140 164 183 212 236 260 284.308 '332 356 380 REQUIRED IN-CORE DECAY TIME (HOURS) l l

l FIGURE 3,9 1 REQUIRED REACTOR HOLD TIME FOR A FULL CORE OFFLOAD HADOAM NECK 3/4 9 3a Amendment No.188 T53S9.00C

s REFUELING OPERATIONS April 26, 1990 3/4.9.4'CONTAI'NMENT BUILDING PENETRATIONS l

LIMITING CONDITION FOR OPERATION l

i 3.9.4 The containment building penetrations shall be in the following status:

a.

The equipment hatch installed and secured in place, j

b.

A minimum of one door in the airlock is closed, and f

c.

Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be, either:

1)

Closed by an isolation valve, blind flange, manual valve, or special device, or 2)

Be capable of being closed by an OPERABLE containment purge supply, purge exhaust, or purge exhaust bypass isolation 1

valve.

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

4 ACTION:

j 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.

SURVEILLANCE _REQlllREMENTS 4.9.4 Each of the above required containment building penetrations shall i

be determined to be either in its closed / isolated condition or capable of being closed by an OPERABLE containment purge supply, purge exhaust, or purge exhaust bypass isolation valve or capable of being closed by an OPERABLE airlock door within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS or movement of irradiated fuel in 1

the containment building by:

a.

Verifying the penetrations referred to in Specification 3.9.4c are in their closed / isolated condition, b.

Testing the containment purge supply, purge exhaust, and purge exhaust bypass isolation valves in accordance with Specification 4.9.9, and c.

Verifying that at least one of the doors in the airlock is capable of being closed.

HADOAM NECK 3/4 9 4 mendment No.125 T5359.00C

~.

April 26, 1990 REFUELING OPERATIONS 3/4.9.5 C0HHUNICATIONS LIMIIING_COND H IDH_EQR OPERATION 3.9.5 Direct communications shall be maintained between the control room and personnel at the refueling cavity manipulator crane area.

APPLICABILITY: During CORE ALTERATIONS.

ACTION:

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.

SURVEILt.ANCE_REQU18EMENTS 4.9.5 Direct communications between the control room and personnel at the refueling cavity manipulator crane area shall be demonstrated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> prior to the start of and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during CORE ALTERATIONS.

HADDAM NECK 3/4 9 5 Amendment No.125 TS359 00C

~.

REFUELING OPERATIONS April 26, 1990 3/4.9.6 MANIPULATOR CRANE LIMITING 10NDITION FOR OPERATION 3.9.6 The manipulator crane and auxiliary hoist shall be used for movement of control rod drive shafts

• or fuel assemblies and shall be OPERABLE with:

a.

The manipulator crane used for movement of fuel assemblies having:

1)

A minimum capacity of 1650 pounds, and 2)

An overload cut off limit less than or equal to 175 pounds above the indicated weight for wet conditions for a stainless steel clad fuel assembly with a full length RCCA inserted.

b.

The auxiliary hoist used for latching and unlatching control rod drive shafts having a minimum capacity of 1500 pounds.

APPLICABILITY: During movement of control rod drive shafts or fuel assemblies within the reactor vessel.

ACTION:

With the requirements for crane and/or hoist OPERABILITY not satisfied, place any fuel assembly or control rod in transit into a safe storage location and suspend use of the inoperable manipulator crane and/or auxiliary hoist from operations involving the movement of control rod drive shafts or fuel assemblies within the reactor vessel.

SURVEILLANCE REQUIREMENTS 4.9.6.1 Each manipulator crane used for movement of fuel assemblies within the reactor vessel shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of such operations by performing a load test of at least 2063 pounds and demonstrating an automatic load cut off when the crane load exceeds 175 pounds above the indicated weight for wet conditions for a stainless steel clad fuel assembly with a full length RCCA inserted.

4.9.6.2 Each auxiliary hoist used for movement of control rod drive shafts within the reactor vessel shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of such operations.

If loads greater than the weight of a stainless steel clad fuel assembly with an RCCA inserted are to be lifted within the reactor vessel with the auxiliary hoist then a load test will be performed for 125% of the weight of the load to be lifted.

The RCCA's may be attached to the control rod drive shafts during some refueling evolutions.

HADDAM NECK 3/4 9 6 Amendment No.125 T53S9.00C

May 27, 1993 4

REFUELING OPERATIONS 3/4.9.7 CRANE TRAVEL SPENT FUEL STORAGE BUILDING l

LitilIING CONDITION FOR OPERATION 3.9.7 Loads in excess of 1650 pounds shall be prohibited from travel over fuel assemblies in the storage pool.

APPLICABILITY: With fuel assemblies in the storage pool.

ACTION:

a.

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

The provisions of Specification 3.0.3 are not applicable.

SLEVEILLANCE REQUIREMENTS 4.9.7 Administrative controls that prevent the travel of loads in excess of 1650 pounds over fuel assemblies shall be in place prior to lifting a load in excess of 1650 pounds.

't HADDAM NECK 3/4 9 7 Amendment No. L % 158 TS359,0CC

~

s April 26, 1990 REFUELING OPERATIONS 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION HIGH WATER LEVEL LIMITING CONDITION F0[LOPERATION 3.9.8.1 At least one RHR LOOP shall be OPERABLE and in operation.*

APPLICABILITY: H0DE 6, when the water level is greater than or equal to 23 feet above the top of the reactor vessel flange.

ACTION:

With no RHR LOOP OPERABLE and in operation, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR LOOP to OPERABLE and operating status as soon as possible. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCLREQUlREBENTS 4.9.8.1 At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> verify at least one RHR LOOP is in operation and circulating reactor coolant at a flow rate of greater than or equal to 2000 gpm.

The RHR LOOP may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of CORE ALTERATIONS in the vicinity of the reactor vessel hot legs.

HADDAM NECK 3/4 9 8 Amendment No.125 TS3S9.00C

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April 26, 1990 REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.2 Two independent RHR LOOPS shall be OPERABLE. and at least one RHR

. LOOP shall be in operation.

APPLICABILITY: H00E 6 when the water level is less than 23 feet above the top of the reactor vessel flange.

ACTION:

a.

With less than the required RllR LOOPS OPERABLE, immediately initiate corrective action to return the required RHR LOOPS to OPERABLE status, or establish greater than or equal to 23 feet of water above the reactor vessel flange, 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. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE REQUIREMENTS e

4.9.8.2.1 At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> verify at least one RHR LOOP is in l

- operation and circulating reactor coolant at a flow rate of greater than or equal to 2000 gpm.

\\

4.9.8.2.2 The RHR LOOP not in operation shall be determined OPERABLE at least'once per 7 days by verifying correct breaker alignments and indicated power availability.

4 HADOAM NECK 3/4 9 9 Amendment No.125 TS359.00C

P i

April 26, 1990 REFUELING OPERATIONS 3/4.9.9 CONTAINMENT PURGE SUPPLY. PURGE EXHAUST. AND PURGE EXHAUST BYPASS ISOLATION SYSTEM r

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

APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within 1

the containment.

ACTION:

I a.

With the requirements of the above specification not satisfied, i

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.-

SURVEILLANCE REQUIREMENTS 4.9.9 The containment purge supply, purge exhaust, and purge exhaust bypass isolation valves shall be verified OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS and prior to movement of irradiated fuel within containment by verifying that containment purge, bypass or exhaust isolation valves are accessible for manual operation or verifying that the associated penetrations are blind flanged.

I HADDAM NECK 3/4 9 10 Amendment No.125 TS359.00C

l W

REFUELING OPERATI0 tis 3/4.9.10 WATER LEVEL REACTOR VESSEL LIMITING CONDITION FOR OPERATION l

3.9.10 At least 23 feet of water shall be maintained over the top of the l

reactor vessel f1ange.

APPLICABILITY: During movement of fuel assemblies or control rods within the containment while in MODE 6.

ACTION:

With the requirements of the above specification not satisfied, place any fuel assembly or control rod in transit into a safe storage location and suspend all further operations involving movement of fuel assemblies or control rods within the reactor vessel.

. SURVEILLANCE REQUIREMENTS 4.9.10 The water level shall be determined to be at least its minimum required depth within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to the start of and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter during movement or fuel assemblies or control rods.

HADDAM NECK 3/4 9 11 Amendment No.125 l

l-T5359. DOC

~.

April 26, 1990 REFUELING OPERATIONS 3/4.9.11 WATER LEVEL STORAGE P0OL LIMITING CONDITION FOR OPERATION 3.9.11-At least 20 feet of water shall be maintained over the top of irradiated fuel assemblies seated in the storage racks.

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

ACTION:

a.

With the requirements of the above specification not satisfied, suspend all movements of fuel assemblies and crane operations with loads in the fuel storage areas and restore the water level to within its limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, b.

The provisions of Specification 3.0.3 are not applicable.

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

r HADDAM NECK 3/4 9 12 Amendment No.125 TS359.00C

REFUELING OPERATIONS January 17, 1996 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.

APPLICABILITY: During operations involving movement of fuel within the pool.ge pool or crane operation with loads over the storage l

stora ACTION:

a.

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

l b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.12 The Fuel Storage Building 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 (2) 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.S.c, and C.S.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 laboratory 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 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 10% at test conditions of 86*F, 95% relative humidity atmospheric pressure, and 40 feet / min face velocity in accordance with ASTH D3803: and 3)

Verifying a system flow rate of 4000 cfm 10% during system operation when tested in accordance with ANSI N5101980.

• The above specification does not apply during movement of fuel storage rack modules into or out of the SFP during t!a Cycle 19 rerack, provided an approved safe loading path is established with no loads over stored fuel assemblies.

HADDAM NECK 3/4 9 13 Amendment No.1 & l87 T53?M

April 26, 1990 REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued) b.

After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying, within 31 days after removal, that a laboratory 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 1.52. Revision 2. March 1978, for a methyl iodide penetration of less than 10% at test conditions of 86"F, 95% relative humidity, atmospheric pressure, and 40 feet / min. face velocity in accordance with ASHT D3803.

c.

At least once per 18 months by:

1)

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches Water Gauge while operating the system at a flow rate of 4000 cfm 10%, and 2)

Verifying that the system maintains the spent fuel storage pool area at a negative pressure of greater than 0 inch Water Gauge differential relative to the outside atmosphere during system operation, d.

After each complete or partial replacement of a HEPA filter bank, by verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than it in accordance with ANSI N5101980 for a D0P test aerosol while operating the system at a flow rate of 4000 cfm 10t: and e.

After each complete or partial replacement of a charcoal adsorber bank, by verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1% in accordance with ANSI N510 1980 for a halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of 4000 cfm 10%.

HADDAM NECK 3/4 9 14 Amendment No.125 TS359. DOC

j 1

August 16, 1994 j

REFUELING OPERATIONS 3/4.9.13 MOVEMENT OF FUEL IN SPENT FUEL POOL i

LIti1 TING CONDITION FOR OPERATION 3.9.13 Prior to movement of a fuel assembly in the spent fuel pool, the boron concentration of the pool shall be maintained uniform and sufficient to maintain a boron concentration of greater than or equal to 800 ppm.

APPLICABILITY: Whenever a fuel assembly is moved in the spent fuel pool.

l ACTION:

l With the boron concentration less than 800 ppm, suspend the movement of all l

fuel in the spent fuel pool.

l' 3URVEILLANCE REQUIREMENT l

4. 9.'.13 Verify that the boron concentration is greater than or equal to 800 ppm within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> pnor to any movement of a fuel assembly in the spent fuel pool L

and every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafter.

i s

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HADDAM NECK 3/4 9 15 Amendment No.175 i

TS359.00C

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2.

1 January 22, 1996 REFUELING OPERATIONS 3/4.9.14 SPENT FUEL P00L REACTIVITY CONDITION LIMITING ff@lIION FOR OPERATION 3.9.14 The Reactivity Condition of the spent fuel pool shall be such that K,fr is less than or equal to 0.95 at all times.

APPLICABILITY: Whenever fuel is in the spent fuel pool.

ACTION:

Immediately initiate actions to correct the loading error if the placement of i

fuel assemblies does not meet the requirements of Figure 3.9 2, Figure 3.9 3, and l

Figure 3.9 4.

SURVEILLANCE REQUIREMENT 4.9.14 Ensure that all fuel assemblies to be placed in the spent fuel pool a.e within the enrichment and burn up limits of Figure 3.9 2 (Region 2) and Figure 3.9 3 (Region 3) by checking the assembly's design and burn up documentation. Region locations Ore shown in Figure 3.9 4.

HADDAM NECK 3/4 9 16 Amendment No.4 & l88 T5359.00C

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1 January 22, 1996 REFUELING OPERATIONS 3/4.9.15 SPENT FUEL POOL COOLING LitilIING CONDITION FOR_0PERATION 3.5.15 The spent fuel pool cooling system shall be OPERABLE with:

a.

Both spent fuel pool cooling pumps OPERABLE and at least one spent fuel pool cooling pump and the plate heat exchanger in operation, and b.

Spent fuel pool temperature less than 150 degrees F.

APPLICABILITY: MODE 6, during transfer and storage of irradiated fuel from the reactor vessel to the spent fuel pool for a full core offload.*

ACTION: With less than the required equipment OPERABLE and in operation or with spent fuel pool temperature greator than 150 degrees F, suspend all operations involving the addition of irradiated fuel to the spent fuel pool and initiate corrective action to restore the spent fuel pool cooling system to OPERABLE status as soon as possible.

SURVEILLANCE REQUIREMENTS 4.9.15.1 Prior to movement of irradiated fuel to the spent fuel pool, verify that both spent fuel pool cooling pumps are lined up to provide flow to the plate heat exchanger.

4.9.15.2 At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, verify that at least one spent fuel pool cooling pump is running.

4.9.15.3 At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, verify that the spent fuel pool temperature is less than 150 degrees F.

I

• Specification 3.9.15 does not apply if less than 53 fuel assemblies are transferred to the spent fuel pool.

HADDAM NECK 3/4 9 20 Amendment No.188 T5359.00C

o April 26, 1990 3/4.11.RADIQACTIVE EFFLUENTS j

3/4.11.1 LIQUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released from the site (see Figure 5.11) shall not exceed the concentrations specified in 10 CFR Part 20. Appendix B. Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.

For dissolved or entrained noble 4

gases, the concentration shall not exceed 2 x 10 microC1/mi total activity.

APPLICABILITY: At all times.

ACTION:

With the concentration of radioactive material released from the site exceeding the above limits, restore the concentration to within the above limits within 15 minutes.

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed in accordance with the sampling and analysis program specified in Section I of the REM 00CH.

4.11.1.1.2 The results of the radioactive analysis shall be used in accordance with the methods of Section II of the REMODCH to assure that the concentration of the point of release are maintained within the limits of Specification 3.11.1.1.

HADDAM NECK 3/4 11-1 Amendment No. 125 TS3511.00C

-=

1 January 22, 1996 3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that:

(1) the reactor will remain subcritical during CORE ALTERATIONS, and (2) a uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel. These limitations are consistent with che initial conditions assumed for the boron dilution incident in the accident analyses. A value of 0.94 or less for K rr is e

required for this accident.

For a core configuration of all rods in an additional 0.05 K,rr penalty is required to account for a heavy load crushing the core into a more reactive configuration.

)

l 3/4.9.2 INSTRUMENTATION 1

i The OPERABILITY of the Source Range Neutron Flux Monitors ensures that monitoring capability is available to detect changes in the reactivity condition of the core. Redundant monitoring capability is required to detect changes in the reactivity condition of the core during fuel movement, j

3/4.9.3 DECAY TIME The minimum requirement for reactor subcriticality prior to movement of irradiated assemblies in the reactor vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short lived fission products.

i The minimum requirement for reactor hold time prior to movement of irradiated fuel from the reactor vessel to the spent fuel poal ensures that sufficient decay time has elapsed for adequate spent fuel pool cooling should a failure occur to the cooling system. The reactor hold time is a function of cooling water temperature. The required decay time assumes a conservative maximum transfer rate of six assemblies per hour. These decay times are consistent with the assumptions used in the safety analysis.

3/4.9.4 CONTAINMENT BUILDING PENEIRATIONS The requirements on containment building penetration closure and OPERABILITY ensure that a release of radioactive material within containment will be restricted from leakage to the environment. The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE.

3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling cavity manipulator crane area personnel can be promptly informed of significant l

changes in the facility status or core reactivity conditions during CORE ALTERATIONS.

HADDAM NECK B3/4 9 1 Amendment No.126,188 TSB359.00C

-~

Hay 27, 1993 j

REFUELING OPERATIONS BASES 3/4.9.6 MANIPULATOR CRANE The OPERABILITY requirements for the manipulator cranes ensure that:

(1) manipulator cranes will be used for movement of control rod drive shafts and fuel assemblies, (2) each crane has sufficient load capacity to lift a drive l

shaft or fuel assembly, and (3) the core internals and reactor vessel are protected from excessive lifting forces in the event they are inadvertently engaged during lifting operations.

3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING l

The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped: (1) the activity release will be limited to that contained in single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the safety analysis.

3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirement that at least one RHR LOOP be in operation ensures that: (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor vessel below 140 F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the core to minimize the effect of a boron dilution incident and prevent boron stratification.

The requirement to have two RHR LOOPS OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a single failure of the operating RHR LOOP will not result in a complete loss of residual heat removal capability. With the reactor vessel head removed and 23 feet of water above the reactor vessel flange, a large heat sink is available for core cocling. Thus, in the event of a failure of the operating RHR LOOP, adequate time is provided to initiate emergency procedures to cool the core.

3/4.9.9 CONTAINHENT PURGE SUPPLY. PURGE EXHAUST. AND PURGE EXHAUST BYPASS ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment vent and purge penetrations can be isolated upon detection of high radiation levels within the containment. The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.

HADDAM NECK B3/4 9 2 Amendment No.125,158 TSB359.00C

December 11, 1997 REFUELING OPERATIONS BASgS 3/4.9.10 and 5/4.9.11 WATER LEVEL REACTOR VESSEL AND STORAGE POOL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the safety analysis.

3/4.9.12 FUEL STORAGE BUILDING AIR CLEANUP SYSTEM l

The limitations on the Fuel Storage Building Air Cleanup System ensure that l

all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere. The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the safety analysis.

l ANSI N510 1980 will be used as a procedural guide for surveillance testing.

3/4.9.13 MOVEMENT OF FUEL IN SPENT FUEL POOL The limitations of this specification ensure that, in the event of any fuel handling accident in the spent fuel pool, K,rr will remain s 0.95.

3/4.9.14 SPENT FUEL P0OL REACTIVITY CONDITION The limitations described by Figures 3.9 2, 3.9 3, and Figure 3.9 4 ensure that the reactivity of fuel assemblies introduced into the spent fuel racks, with no credit taken for soluble boron in.he pool, are conservatively within the assumptions of the safety analysis.

3/4.9.15 SPENT FUEL POOL COOLING The limitations on the Spent Fuel Pool Cooling System ensure there is sufficient capacity to remove decay heat produced by the stored.uel elements (1019 assemblies) and maintain the bulk pool temperature below 150'F with a maximum heat lo:d as shown in Fig. B3/4.9 1.

Requiring both SFP cooling pu s to be OPERABLE provides backup capability in the event the operating pump ils.

In the event of a complete loss of forced cooiing, the time to boil, excluding the effect of evaporation, is greater than !,0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> based on current heatup calculations. Only makeup would be required to maintain pool inventory.

HADDAM NECK B3/4 9 3 Amendment No.125,175,188 TS8359.00C

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May 27, 1993 3/4.11 RADI0 ACTIVE EFFLUEMTS BASES i

3/4.11.1 LIOUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This specification is provided to ensure that the concentration of i

radioactive materials released in liquid waste effluents from the site will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2.

This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within:

(1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR 20.106(e) to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe 135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

3/4.11.1.2 DOSE. LIOUIDS l

This specification is provided to implement the requirements of Sections II.A. III.A and IV.A of Appendix I,10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". The dose calculation methodology and parameters in the REMODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data, such that the actual l

exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the REMODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977, and Regulatory Guide 1.113. " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

HADDAM NECK B3/4 11 1 Amendment No. E 158 T583Sil.00C

September 26, 1995 RAD 10 ACTIVE EFFLUERTS PTSCR No. C 5 95 BASES 3/4.11.2 GASE0US EFFLUENTS 3/4.11.2.1 DOSE RATE This specification is provided to ensure that the dose rate at anytime from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for all areas offsite. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B.

Table II. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the ex30sure of an individual offsite to annual average concentrations exceeding t1e limits specified in Appendix B. Table II of 10 CFR Part 20 (10 CFR 20.106(b)).

For individuals who may at times be within the site boundary, the occupancy of that individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. The specified release rate limits restrict, at all times, the corresponding garrma and beta dose rates above background to an individual at or beyond the site boundary to less than or equal to 500 mrem / year to the total body or to less than or equal to 3000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid or other organ dose rate above background to a child to less than or equal to 1500 mrem / year from l

inhalation.

3/4.11.2.2 DOSE. N0BLE GASES This specification is provided to implement the requirements of Sections II.B., III.A and IV. A of A]pendix I,10 CFR Part 50. The Limiting Condition for Operation implements t1e guides set forth in Section II.B of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conform with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents will be consistent with the methodology provided in Regulatory Guide 1.109,

" Calculational of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light Water Cooled Reactors," Revision 1. July 1977.

TM ODCM equations provided for determining the air doses at the site boundary are based upon utilizing successively more realistic dose calculational methodologies. More realistic dose calculational methods are used whenever simplified calculations indicate a dose approaching a substantial portion of the regulatory limits. The methods used, in order are, previously determined air dose per released activity ratio, historical meteorological data and actual radionuclide mix released, or real time meteorology and actual radionuclides released.

HADDAH NECK B3/4 11 2 Amendment No. 125 TSB3511.00C

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