ML20059C266
| ML20059C266 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/27/1993 |
| From: | Thonus L Office of Nuclear Reactor Regulation |
| To: | Weiss S Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9401050064 | |
| Download: ML20059C266 (6) | |
Text
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December 27, 1993 MEMORANDUM FOR:
Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support Office of Nuclear Reactor Regulation THRU:
Richard F. Dudley, Chief Decommissioning Section Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support Office of Nuclear Reactor Regulation FROM:
Lee H. Thonus, Project Manager Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support Office of Nuclear Reactor Regulation
SUBJECT:
THI-2 POST-DEFUELING MONITORED STORAGE PUNCHLIST Enclosed is a list of items on the THI-2 PDMS punchlist which I have reviewed and have found that the licensee has satisfactorily completed as of December 14, 1993.
This list documents the item completed and the basis for acceptance of completion.
Original signed by:
Lee H. Thonus, Project Manager Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support Office of Nuclear Reactor Regulation
Enclosure:
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l ENCLOSURE THI-2 PUNCHLIST - COMPLETED ITEMS
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P_tjNCHLIST ITEM BASIS FOR ACCEPTANCE C.1 Verify that a surveillance Review of procedures 4210-0PS-program exists to ensure AFHB 3029.01, 4210-0PS-3030.01, 4210-SUR-ventilation and filtration 3829.01, 4210-SUR-3829.02, 4210-SUR-operability, maintenance, and 3829.03, and 4210-SUR-3830.01; which testing.
are the operations and surveillance procedures for the auxiliary and fuel handling building ventilation systems. Also reviewed were procedure change requests to modify the procedures to make them applicable to PDMS.
C.5 D0P test HEPA filter in the RB Review of Unit Work Instruction breather prior to entry into PDMS.
(UWI) 4220-3824-91-J079.0 which installed the HEPA filter using procedure 4224-PMU-3820.03 and tested the filter using procedure 4224-PMU-3916.03.
The filter passed the leakage test with a filtration efficiency of 99.998% using polydisperse dioctyl phthalate (00P).
C.6 Ensure installation, actuation Review of MMA 3824-92-9225 rev 0&l, testing and routine surveillance UWI 4220-3824-92-J155.00, and UWI testing of the isolation valve 4220-3824-92-104 (a standard between containment and HEPA filter operating procedure). Modifications in the reactor building breather (to were completed to effect valve automatically close upon receipt of closure of containment isolation a containment pressure increase of valve AH-V-52 if the containment 0.25 psi).
pressure exceeded auxiliary building pressure by 0.25 psi.
Procedure 4210-SUR-3824.05 tests the trip setpoint alarm, and valve closure bi-annually.
C.8 Develop and implement a Procedure 4210-SUR-3824.02 requires reactor procedure for maintaining an operational check of the RB purge HEPA filter banks for the reactor HEPA filter system every 31 days.
building purge system.
Procedure 4210-SUR-3824.01 performs a flow test and DOP filter efficiency test every 18 months.
y C.9 Develop and implement Procedure 4210-0PS-3824.02 requires procedurer for monitoring the that HPR-225 or 226, the reactor reactor building vent during reactor building purge monitors and one of building purge.
the vent stack monitors (HPR-219 or 219A) be operable while purging the reactor building.
D.1 Licensee will meet established The licensee submitted a letter with contamination goals for entrance attached evaluations to the NRC into PDMS for each area of the AFHB.
(C312-93-2078) dated November 12, If the decontamination goals cannot 1993. The NRC staff reviewed the be met because of the unique licensee evaluations and situation at TMI-2 or ALARA justifications including factors considerations, the licensee will such as need for access to the area provide an evaluation of the during PDMS, and estimated spe:ific situation to the NRC.
additional personnel exposure to achieve the decontamination goal.
The NRC staff finds the licensee exceptions and evaluations acceptable.
D.2 Update information in the The staff has verified that the following tables as final tables have been updated in decontamination results become amendments 18 and 19 to the PDMS SAR avail able, dated October 24, 1993 and
-Table 5.3-2 PDMS Radiological November 12, 1993 respectively.
Conditions AFHB
-Table 5.3-4 Surface Contamination -
-Table 5.3-5 Surface Contamination -
AFHB
-Table 5.3-6 Surface Contamination -
Other Bldgs.
D.3 Perform survey of the service The staff has verified that the building, elevation 305 ft., the survey results have been included in turbine building, elevation 281 ft.,
amendment 19 to the PDMS SAR dated and the containment air control November 12, 1993.
envelope building; and provide information in the PDMS SAR before entry into PDMS in order to establish a radiological baseline for the facility.
e
- D.4 Ensure that a program exists Review of procedures 4210-SUR-for periodic measurement of 3824.07 and 4210-SUR-3824.06 which radiation and contamination levels require monthly baseline surveys for to verify radiological conditions.
6 months followed by quarterly surveillance surveys for the auxiliary and fuel handling buildings and reactor building respectively. These procedures delineate minimum survey points and require air sampling.
F.1 Create a program plan to Review of procedure 4210-SUR-3824.07 perform monthly entries into the which requires surveillance and AFHB for at least 6 months after surveys for at least 6 months after placing it into its PDMS condition.
the AFHB enters PDMS.
I.1 Have procedures in p' lace to UW1 4210-3810-92-111 (SOP) drains ensure that the fire mains within the fire system inside the reactor the reactor building will be closed building and closes FS-V-639, the with valves drained to the extent containment isolation valve for the reasonably achievable within 30 days fire mains. This UWI is scheduled following entry into PDMS to to be implemented as soon as THI-2 minimize the potential for enters PDMS.
introduction of water into the reactor vessel.
I.15 Ensure that transient Direct inspection verified the combustibles have been removed from removal of transient combustibles, inside the containment and the AFHB including plant items installed to the extent practicable. This after the accident, to the extent includes most plant items installed reasonably achievable. The licensee after the accident.
Fire loading Fire Protection Program Evaluation, must be less than a 1-hour loading submitted in a letter to the NRC z
of 80,000 btu /ft,
dated October 14, 1993 contains the fire loadings of the reactor building, control and service building and AFHB. No fire zones in any of the buildings exceeded 80,000 z
btu /ft,
k
-4 I.16 Drain oil to the extent Review of GPU Nuclear memo 4240 reasonably achievable from the main 087, Byrne to Schrull, dated turbine, feedwater pump turbines, July 30, 1993.
Review of UWIs emergency feedwater pump turbine, related to draining of oil as main feedwater pumps, emergency follows: main turbine 4210-3221.
feedwater pumps, condensate pumps, 053; feed water pump turbine / main condensate booster pumps, and feed pumps 4210-3321-88-179; EFW hydrogen seal oil unit.
pump turbines 4220-3424-87-H394; condensate booster pumps 4220-3421-87-H395; and hydrogen seal oil 4210-3314-87-306. Additionally UWIs 4220-3421-87-H324 and 4220-3421 H354 which dealt with removal of condensate booster pumps, t
I.17 Taken as an aggregate, Review of GPU Nuclear memo 4240 demonstrate that no more than 57% of 035, Byrne to Schork, dated March 5, the original total volume of reactor 1992 and UWIs 4210-3226-89-032 and coolant pump lubricating oil remains 4210-3227-89-054; which removed oil in the upper and lower reservoirs of from the upper reservoirs of RCP-1A the four reactor coolant pump and RCP-2A respectively. A net 240 reservoirs.
gallons was removed from the upper reservoirs of the 2 pumps out of a total of 552 gallons in the upper and lower reservoirs in all 4 pumps.
Thus a 56.5% of the original oil inventory remains.
I.18 Charcoal filters have been Review of UWI-4220-3829-02-Jll2 removed from all HVAC systems in (auxiliary builoing HVAC), memo TMI-2.
4220-93-069 (reactor building purge), job ticket C5502 (hydrogen purge),UWI 4220-3830-92-J111 (fuel handling building HVAC), UWI 4220-3830-92-J-132 (SDS off gas), job ticket CF 096 (condenser air ejector), job ticket CF 095 (temporary auxiliary and fuel handling building HVAC), UWI 4220-3231-92-J199 (waste gas filters),
UWI 4220-3826-92-J117 (control room i
bypass) and UWI 4220-3835-92-Jll5 (temporary nuclear sample exhaust).
3 Direct observatic.. of absence of charcoal units in auxiliary building HVAC, fuel handling building HVAC, reactor building purge, and hydrogen J
purge.
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1.20 Procedure in place for Review of THI-1 operating procedure reactivation of the deactivated 1104-450, Rev 1, "TMI-2 Fire portions of the fire protection Protection System." Section 5.4 system if necessary.
provides for restoration of the system, if necessary, after TMI-2 enters PDMS.
J.5 Ensure that a flow path exists Review of procedure 4210-0PS-to drain down the reactor building 3572.01, Rev 2-00, "RB Sump Level basement floor.
Measurement / Drain", which provides a drain pathway and a process to implement draining the RB floor and sump.
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