ML20247E999

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Proposed Tech Specs,Reflecting Permanently Defueled Condition of HNP
ML20247E999
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 05/07/1998
From:
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20247E995 List:
References
NUDOCS 9805190084
Download: ML20247E999 (9)
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Docket No. 50-213 CY-98-071 Attachment 1 Haddam Neck Plant Supplement To Proposed Defueled License Amendment Spent Fuel Pool Cooling - Defueled Typed Pages May 7,1998 9805190084 980507 DR ADOCK O 23

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, . l BEFUELING OPERATIO_NS 3/4.9.16 SPENT FUEL P0OL COOLING - DEFUELED LIMITING CONDITIONS FOR OPERATION 3.9.16 The spent fuel pool coolant temperature shall be maintained at less than or equal to 150 degrees F.

APPLICABILITY:

Whenever irradiated fuel assemblies are stored in the spent fuel pool.

ACTION:

With the spent fuel pool coolant temperature not within limit:

a. Immediately initiate action to restore the spent fuel pool coolant temperature to within limit, and
b. Immediately verify that a spent fuel pool makeup water source is available, and
c. Within 7 days, restore the spent fuel pool coolant temperature to within the limit.

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SURVEILLANCE REQUIREMENTS 4.9.16 At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, verify that the spent fuel pool coolant temperature is less than or equal to 150 degrees F.

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l HADDAM NECK 3/4 9 21 Amendment No.

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3/4.9 REFUELING OPERATIONS BASES 3/4.9.16 SPENT FUEL P00L COOLING - DEFUELEQ The primary basis for 150 degrees F is to limit thermal stresses on the spent fuel pool concrete structures due to the differential temperature across the internal and exterior surfaces of the walls and floor. The basis is further discussed in License Amendment No. 188.

As of May 1998, the spent fuel heat load was calculated to be less than 2.3E+06 BTU /hr. Each heat exchanger has the capability of removing this heat load. One spent fuel pool heat exchanger and one spent fuel pool cooling pump, that can be operated intermittently is sufficient to remove the decay heat load.

Assuming no forced or evaporative cooling, the calculated May 1998 heatup rate is approximately 1.2 degrees F/hr. Thus, in the event of a complete loss of forced cooling and assuming an initial spent fuel pool temperature of 150 degrees F, the time to boil, assuming no evaporative cooling, is greater than 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. Therefore, sufficient time exists to either reestablish forced cooling or to provide makeup to maintain the spent fuel pool inventory.

HADOAM NECK B 3/4 9 5 Amendment No.

6.0 ADMINISTRATIVE CONTROLS 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures and/or administrative policies shall be established, implemented, and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978;
b. The requirements and recommendations of Sections 5.1 and 5.3 of ANSI N 18.7 1976.
c. Fire Protection Program implementation.
d. Quality controls for effluent monitoring, using the guidance in Regulatory Guide 1.21 Rev.1 June 1974.
e. RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REM 00CM) implementation except for Section I.E.

Radiological Environmental Monitoring.

f. Process Control Program implementation.
g. Spent Fuel Pool Cooling and Makeup Monitoring Program I implementation. This Program requires that the primary method for spent fuel pool cooling and the primary method for spent fuel pool )

water makeup capability be monitored and maintained. This Program shall provide reasonable assurance that the equipment, components, systems and water sources used for spent fuel pool cooling and for maintaining spent fuel pool water level are capable of fulfilling their intended functions and are protected against freezing.

l HADDAM NECK 6 11 Amendment No. 424, 465, 481, 491, 492, l

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6.0 ADMINISTRATIVE CONTROLS I

6.8.2 Each procedure of Specification 6.8.1, and changes thereto, shall be reviewed by the PORC and shall be approved by the Unit Director prior to implementation and reviewed periodically as set forth in each document or in administrative procedures.

6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made provided:

1 l a. The intent of the original procedure is not altered:

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! b. The change is approved by a member of the plant management staff and a Certified Fuel Handler; and

c. The change is documented, reviewed by the PORC and approved by the Unit Director within 14 days of implementation.

6.8.4 Written procedures shall be established, implemented and maintained covering Section I.E., Radiological Environmental Monitoring, of the REM 00CM.

6.8.5 All procedures and procedure changes required for the Radiological Environmental Monitoring Program of Specification 6.8.4 above shall be reviewed by an individual (other than the author) from the Radiological Assessment Branch or the Production Operation Services Laboratory (POSL) and approved by appropriate supervision.

Temporary changes may be made provided the intent of the original procedure is not altered and the change is documented and reviewed by an individual (other than the author) from the Radiological Assessment Branch or the POSL, within 14 days of implementation.

HADDAM NECK 6-12 Amendment No. 426, M5, M8, 191, 492, i

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Docket No. 50-213 CY-98-071 l

! Attachment 2 Haddam Neck Plant Supplement To Proposed Defueled License Amendment Spent Fuel Pool Coo!ing - Defueled Description Of Changes i

i May 7,1998

U. S. Nucle:r Regulatory Commission CY-98-071/ Attachment 2/Page 1 Additions 3/4.9.16 SPENT FUEL POOL COOLING - DEFUELED I

Add the new Technical Specification provided in Attachment 1.  !

B3/4.9.16 SPENT FUEL POOL COOLING - DEFUELED l

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Add the new Basis provided Attachment 1.

6.8 PROCEDURES AND PROGRAMS Add new item 6.8.1.g provided in Attachment 1.

Reasons and Bases Backaround The water temperature in the spent fuel pool is normally controlled by a forced cooling system. This system is designed to maintain the spent fuel pool temperature to

< 150 *F. In the unlikely event that forced cooling is interrupted for an extended period of time, the volume of water in the spent fuel pool provides an adequate passive heat sink for the heat generated by the Irradiated fuel. A general description of the spent fuel pool design and the cooling system is provided in the UFSAR, Sections 9.1.2 and 9.1.3. The safety analysis of a loss of forced cooling for the spent fuel pool is also referenced in UFSAR Section 9.1.3.

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U. S. Nuclerr Regulatory Commission CY-98-071/ Attachment 2/Page 2 Apolicable Safety Analysis The spent fuel pool cooling system is used to prevent heatup of the water in the spent fuel pool, which in turn could lead to a loss of coolant inventory due to evaporation and l boiling. The spent fuel cooling system is designed to maintain the water in the spent fuel pool temperature to .5150 *F. The primary basis for 150 *F is to limit thermal ,

stresses on the spent fuel pool concrete structures due to the differential temperature across the internal and exterior surfaces of the walls and floor. The basis is further discussed in License Amendment No.188.W The potential for an extended loss of forced cooling has been evaluated. Conservative calculations performed for the HNP were based on a decay time of 18 months after shutdown. Assuming no evaporative cooling, the results indicate that more that 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> would elapse before the water in the spent fuel pool rises from an initial temperature of 150 'F to boiling at 212 'F.

Boiling and evaporation at the surface of the spent fuel pool would continue to provide an adequate heat sink for the irradiated fuel assemblies stored in the spent fuel pool as long as the fuel assemblies remain covered with water. The rate of water loss due to boiling and evaporation is low; greater than 13 days would be available from the onset of boiling before the water level in the spent fuel pool drops from 20 feet above the top of the irradiated fuel to 10 feet above the fuel. Ten feet of water above the top of the irradiated fuel would continue to provide an adequate heat sink for the fuel and would protect personnel working in the area from excessive radiation. It would also provide sufficient time to establish makeup flow from a number of facility systems or to arrange for makeup using portable or temporary sources. Methods for providing cooling and makeup water to the spent fuel pool are prescribed by facility procedures.

3/4.9.16 Spent Fuel Pool Cooling - Defueled The change reflects that the reactor is permanently defueled, the heat load of the spent fuel has significantly decreased and that no more freshly irradiated spent fuel will be added to the spent fuel pool. The proposed change will not require one spent fuel pool cooling pump and the plate heat exchanger be in continuous operation. Due to the decreased decay heat load, continuous operation of either spent fuel pool cooling pump or either spent fuel pool cooling heat exchanger is no longer required. Each heat exchanger has the capability of removing the existing heat load. However, the spent fuel pool cooling system will still have available two spent fuel pool cooling pumps and two spent fuel pool cooling heat exchangers.

(1) NRC Letter from A. B. Wang to R. E. Busch, " Issuance Of Amendment (TAC No. M91976)," cated January 22,1996.

U. S. Nucle r Reguhtory Commission l CY-98-071/ Attachment 2/Page 3 l B3/4.9.16 Spent Fuel Pool Cooling - Defueled The primary basis for 150 *F is to limit thermal stresses on the spent fuel pool concrete structures due to the differential temperature across the internal and exterior surfaces of the walls and floor. The basis is further discussed in License Amendment No.188.0)

The plant was shutdown on July 22,1996 and more than 500 days have passed since t the shutdown, thus the heat load on the spent fuel pool cooling system is greatly reduced. Present cooling performance data as well as calculations provided in the i CYAPCO's letter dated May 30,1997,(2) demonstrate that either the plate or the shell and tube heat exchanger has more than adequate heat removal capacity. In addition, the performance data and the calculations also demonstrate that it is no longer necessary to continuously run a spent fuel pool cooling pump. In the event of a loss of forced cooling, calculations indicate that the spent fuel pool time to tacil, assuming no evaporative cooling, is greater than 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> based on an initial spent fuel pool temperature of 150 *F. This in contrast to the version approved by License Amendment No.188,U) in which the time to boil was approximately 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. The initial spent fuel pool temperature of 150 *F is based on Technical Specification 3/4.9.15 which has a spent fuel pool temperature limit of 150 *F. Even if the spent fuel pool were to boil, the fuel is adequately cooled. If boiling commences, the operators have in excess of 13 days to provide forced cooling and/or makeup before there is inadequate shielding provided by the water in the spent fuel pool. This allows sufficient time to provide an alternate source of forced cooling or establish makeup to the spent fuel pool.

6.8 Procedures And Programs In order to provide reasonable assurance that the equipment, components, systems and water sources used for spent fuel pool cooling and for maintaining spent fuel pool water level are capable of fulfilling their intended functions and are protected from freezing, the Spent Fuel Pool Cooling and Makeup Monitoring Program is required by Technical Specification 6.8.1.g. This Program requires that the primary method for spent fuel pool cooling and the primary method for spent fuel pool water makeup capability be monitored and maintained.

(2) CYAPCO Letter CY-97-006 from T. C. Feigenbaum to the U. S. Nuclear Regulatory Commission, " Proposed Revision To Operating License And j Technical Specifications Defueled Operating License And Technical i Specifications," dated May 30,1997.

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