View source for B11712, Forwards Response to 850826 Request for Addl Info Re Util 850724 Proposed Change to Tech Spec Mods for Spent Fuel Storage Pool Capacity

{{Adams
| number = ML20135H947
| issue date = 09/16/1985
| title = Forwards Response to 850826 Request for Addl Info Re Util 850724 Proposed Change to Tech Spec Mods for Spent Fuel Storage Pool Capacity
| author name = Opeka J, Sears C
| author affiliation = NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
| addressee name = Butcher E
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000336
| license number = 
| contact person = 
| document report number = B11712, TAC-59294, NUDOCS 8509250046
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 41
| project = TAC:59294
| stage = Request
}}

=Text=
{{#Wiki_filter:C. ~    'O N tlTILITIES                                                   o.nor.i Ore.c.. . s.io.n str .t. s.riin. Connecticut
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(203) ses-5000 September 16,1985 Docket No. 50-336 Bil712 Director of Nuclear Reactor Regulation Attn: Mr. Edward J. Butcher, Chief Operating Reactors Branch No. 3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:
Millstone Nuclear Power Station, Unit No. 2 Repiy to Request for Additional Information on Spent Fuel Storage Capacity in August, 1985(l) the Staff requested additional jqformation concerning a Northeast Nuclear Energy Company (NNECO) requestt21 to modify the Technical Specifications concerning the spent fuel storage capacity at Millstone Unit No.2.
Attachment No. I to this letter provides the response, in a question and answer format, to the four questions contained in the Staff's request for additional information.
(1)     E. 3. Butcher letter to 3. F. Opeka, " Request for Additional Information on Spent Fuel Storage Capacity Expansion for Millstone Unit No. 2", dated August 26,1985.
(2)     3. F. Opeka letter to E. 3. Butcher, " Millstone Nuclear Power Station, Unit No. 2, Proposed Change to Technical Specification Modifications to Spent Fuel Storage Pool", dated July 24,1985.
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      . We trust that the information provided is sufficient, and we remain ready to    ;
address any further questions as they arise to support expeditious processing of l our pending amendment request.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY d.S.O J. F. Opeka Senior Vice President By: C. F. Sears Vice President t.

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Attachment No. I i                                              Millstone Nuclear Power Station, Unit No. 2 Response to Request for Additional Information on
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September,1985

Ouestion 1:
The submittal refers to using the two spent fuel pool cooling systems in addition to using one shutdown cooling system to remove the decay heat associated with a core off-load and the remaining capacity filled with normal refuelings. The FSAR does not discuss the potential for using the shutdown cooling system to cool spent fuel. FSAR Figure 9.5-1 does show a " temporary" connection to
          " shutdown heat exchanger". Verify that this is the connection to the shutdown cooling system and that this temporary connection is still available. Provide a discussion of this temporary connection in terms of the existence of a' spool piece, manual or remote manual valving, and operating procedures.

===Response===
The discussion of the potential for using the Shutdown Cooling System for cooling the spent fuel pool may be found in Section 9.5.3.2 of the Millstone Unit No. 2 FSAR titled Abnormal Operation (Spent Fuel Pcol Cooling System). The section reads as follows:
i "In the event that an emergency full core offload is placed in the spent fuel pool, a combination of spent fuel pool cooling and shutdown cooling system components will be used to remove decay heat. One low pressure safety injection pump will take suction from the spent fuel pool and pump the cooling water through one of the shutdown heat exchangers. The shutdown cooling system is placed into service by manual initiation."
The Shutdown Cooling System has been used for cooling fuel during the last two refuel outages.
The connection between the spent feel pool outlet and the shutdown cooling system inlet is a spool piece located between valves 2-SI-442 and 2-RW-il. The connection between the shutdown cooling system outlet and the spent fuel pool inlet is a spool piece between valves 2-51-458 and 2-RW-15.
Valves 2-51-442 and 2-S1-458 are manually operated while valves 2-RW-il and 2-RW-15 are remote manually operated from the Control Room Panel CO-1. The procedure for performing the spent fuel pool cooling function is contained in Operating Procedure OP 2310, Shutdown Cooling System.
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_ . - .                                                             ,            _.  -_ y ,

  . O,       t Question 2:
The heat load calculations provided in the submittal indicate that the total normal heat load would be in excess of the combined capacity of both spent fuel pool cooling trains. In conformance with the Standard Review Plan (NUREG-0800), provide a discussion of the method of maintaining the spent fuel pool water temperature less than 140 degrees F with the normal heat load and the single failure of one spent fuel pool cooling system train. If the shutdown cooling system is relied upon, provide a commitment to have the reactor in cold shutdown prior to aligning the shutdown cooling system to cool the spent fuel pool and to maintain the reactor in the cold shutdown condition until the shutdown cooling system can be realigned to the reactor system.

===Response===
As indicated, the heat load in the spent fuel pool immediately following a one-third core offloa'd would result in spent fuel pool water temperature in excess of 1400F assuming a failure of one Spent Fuel Pool cooling train. The calculated maximum temperature is 1780F following the failure of a single train of the Spent Fuel Pool cooling system. Northeast Utilities Service Company has performed independent calculations which predict a maximum temperature of 1770 F.
These results assume a one-third core effload whicn has decayed 150 hours and that no corrective action has been taken to provide additional cooling.
If the most recent offload is assumed to have decayed for 18 days, the Spent Fuel Pool cooling system in its normal alignment is sufficient to maintain the pool at'1220F. In addition, alternate means of cooling could be provided. A LPSI pump could be aligned to take suction from the Spent Fuel Pool and discharge through the shutdown cooling heat exchangers into the reactor vessel. In this arrangement, coolant would flow from the vessel, through the fuel transfer tube and back into the spent fuel pool. In the event that fuel handling operations were completed and the fuel transfer tube was closed, one train of LPSI could provide cooling to the Spent Fuel Pool while the other train cooled the fuel in
>        the reactor vessel. This equipment would be available as it is required to perform the normal shutdown cooling function.
With respect to a commitment to have the reactor in cold shutdown prior to aligning the shutdown cooling, the shutdown cooling system is part of the ECCS during power operations. Since the shutdown cooling system is composed of a cross-tie between the LPSI and containment spray systems it is required to be operable in Modes 1 and 2 rad in Mode 3 for pressurizer pressure greater than 1750 psia. Shutdown cooling is only required for cooling the Spent Fuel Pool following a full core off-load (Reactor in Mode 6). Once the fuel is reloaded into the reactor vessel, Shutdown Cooling is no longer required for the Spent Fuel Pool but will be required for reactor vessel cooling. Both trains of Shutdown Cooling must be inservice to the vessel before the reactor is taken above Mode 3 with pressurizer pressure greater than 1750 psia.           Therefore no further commitment is necessary.
_     ~ _

Question 3:
Provide the heat exchanger heat rate transfer coefficients in BTU /Hr-f2t oF for the spent fuel pool cooling system heat exchangers and the reactor building water system (RBCCWS) heat exchangers. Provide the total component     coolmg(in MBTU/Hr) on the RBCCWS heat exchangers excluding the normal heat loads spent fuel decay heat load. Provide the maximum water temperatures for the RBCCWS and the service water system which will not result in insufficient cooling to the serviced components. Provide the design flow rates in GPM for the RBCCWS water through the spent fuel pool cooling system heat exchangers and for the service water through the RBCCWS heat exchangers.

===Response===
Spent Fuel Pool Cooling System Heat Exchangers a)    Heat rate transfer coefficient 413 BTU /Hr-f t2 .op b)    Design flow rate of RBCCWS water through exchanger 1100 GPM RBCCW Heat Exchangers a)    Heat rate transfer coefficient 347 BTU /Hr-f t 2_op b)    Design flow rate of service water through exchanger 11.700 GPM c)    Total norma} heat load per exchanger (excluding spent fuel decay heat load) 26.33(11 MBTU/HR d)    Maximum RBCCW temperature 850F(I)
Maximum service water temperature 7fF(I)
(1)   Millstone Unit No. 2 FSAR Section 9.4.3.1.

Question 4:
Provide the results of analyses of dropping an existing rack and each type of the new racks from the maximum height that it will be lifted onto the spent fuel pool floor. Provide the results of an analysis of the failure of one wire rope and one lif ting lug when the rack is lif ted sufficiently high above the pool floor that the rack can rotate. These analyses should include the damage to the poolliner, adjacent racks, fuel damage, and loss of pool water (both due to splashing from the dropped racks and leakage through liner damage). When considering the damage to the pool liner, the feet of the rack should be consider.ed as hitting the weakest part of the liner, which is usually at the leakage detection system for the liner welds'. Provide a discussion of the procedure which will be used to physically verify that no damage has occurred and to recover the dropped load, should a load drop accident occur. Provide drawings which show the load paths
   . to be followed, the order in which the racks will be replaced and the location of the spent fuel during the load handling operations.

===Response===
An evaluation was completed in March 1983 to determine the potential consequences of drops into the Millstone Unit No. 2 spent fuel pool. .The analysis was performed as part of NUREG-0612- " Control of Heavy Loads at Nuclear Power Plants." This analysis addressed an object which weighed 67,000 pounds being water dropped     from the directly onto    a height 41elevation slab at   feet above(- the  sp)ent 2'-0". fuel The    pool floor slab through above-mentioned calculation conservatively takes no credit for any energy absorption that would occur due to deformation of the object at impact. The 67,000 pound object dropped would be expected to perforate the spent fuel pool liner. The object would penetrate into the concrete floor slab but not perforate it and therefore not jeopardize the floor slab structural integrity. Since no perforation of the concrete slab is expected, no gross leakage from the pool is expected to occur.
Assuming the dropped object hits the weakest part of the spent fuel pool, which would be the leakage detection system for the liner welds, the leak detection and monitoring system, as described in the Millstone Unit No. 2 Final Safety Analysis Report Sections 5.4.3 and 9.5.2, would be activated. The leak detection and monitoring system would be utilized if (a) a pool liner weld seam was to fail or (b) a local failure of the leak chase collection channel due to a dropped object directly hitting it was to occur. If the spent fuel pool liner is perforated, the 5'-0" thick reinforced concrete spent fuel pool floor slab will act as a water retaining barrier. The' potential exists for some leakage to occur through small cracks in the concrete but no flow path exists that will result in significant pool water inventory loss. If either a weld seam or leak chase collection channel was to locally fail due to a dropped rack, both overall leakage detection system integrity and pool structural integrity would be maintained.
The existing racks in the spent fuel pool vary in weight from a maximum of approximately 58,000 pounds for a 10x10 module to a minimum of approximately 37,000 pounds for a 7x9 module. The heaviest module to be installed as part of reracking will weigh approximately 28,000 pounds for an 8x10 module. The 67,000 pound object which was analyzed as being dropped conservatively bounds the weight of the heaviest module. Another conservatism taken in the analysis was that no credit was taken for any decrease in kinetic energy due to energy absorption at impact of the object analyzed as ' dropped.           It is therefore

concluded that the existing analysis for the 67,000 pound object is a conservatively bounding analysis for any postulated rack drop. The droppi'ng of any module will therefore not result in any gross structural damage or significant pool water inventory loss.
If a rack is dropped near the pool water surface, some splashing of water will occur. The racks will not be lif ted more than 2'-6" above the pool water surface.
Therefore, only a relatively small percentage of water could be displaced due to a dropped or rotating rack. The pool water surface is located 2'-0" below the top of the pool walls. The pool walls themselves would therefore serve to retain splashed water. The normal makeup capability to the spent fuel pool water inventory would also be available to provide makeup for any water that leaves the pool.
In the event of a dropped rack, the procecares utilized for initial rack upending and receipt inspection would be employed to recover the rack and assess any damage which might have been incurred. The inspection would consist of a complete dimensional check, including guaging of each storage cell within the rack, and a thorough visual inspection.
Additionally, any previously installed rack module in the area of the drop which is found by visual inspection to have incurred any damage would be removed from the fuel pool and reinspected in the same manner as the dropped rack.
The reracking operation at Millstone. Unit No. 2 will be conducted in accordance with strict procedures to prevent inadvertent dropping of objects into the pool during the reracking operations. Strict procedural controls, as well as technical specifications, will prohibit the movement of heavy objects over spent fuel stored in the pool.
During the reracking, no heavy loads supporting the activities ir. the spent fuel pool will have a handling path that brings the objects directly above or in the immediate vicinity of the stored spent fuel. Additionally, during the reracking transition, no fuel racks old or new will have a handling path directly over or in the immediate vicinity of stored spent fuel.
The attached drawings (32 in number) show the safe load paths that have been established for the racks, the order in which the racks will be removed and replaced, and the locations of the stored spent fuel during the load handling operation.
These drawings will demonstrate that adequate distance is always maintained between any lif ted rack and fuel stored in the pool even if some rotation of the lif ted rack was to occur due to a failure of a wire rope and lif ting lug.

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