ML20059M207
| ML20059M207 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/12/1993 |
| From: | Long R GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C-93-2265, C000-93-2265, C312-93-2072, NUDOCS 9311180275 | |
| Download: ML20059M207 (12) | |
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GPU Nuclear Corporation 1 U Nuclear m',ers:r8o o
Middletown. Pennsylvania 17057-0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
(717) 948-8400 November 12, l'993 C312-93-2072 C000-93-2265 US Nuclear Regulatory Commission I
Attn: Document Contml Desk Washington, DC 20555 Three Mile Island Nuclear Station Unit 2 (TMI-2)
Operating License DPR-73 Docket No. 50-320 Transition to PDMS
Dear Sir:
The purpose of this letter is to provide notice that GPU Nuclear will satisfy the requirements for TM1-2 transition to Post-Defueling Monitored Storage (PDMS) within the next 30 days. The requirements for transition to PDMS are contained in the TMI-2 Possession Only License (POL) and the NRC List of Requirements and Commitments (Ref. NRC letter dated May 19,1993 and revised via NRC letter dated August 5,1993). Enclosure 1 includes a table of all PDMS entry requirements along with reference to the GPU Nuclear letters that provided closeout documentation. TMI-2 is essentially in the condition described in the PDMS Safety Analysis Report (SAR). The ongoing electrical modification and associated supporting ftmetions as discussed with Messrs. M. Masnik and L. Thonus, NRR, and Ms. M. Evans, Senior Resident Inspector, TMI, is schedoled for completion in early 1994.
POL License Condition 2.D., "Special AFHB Ventilation Study," requires one year of data prior to entry into PDMS and one year of data after entry into PDMS. The pre-PDMS data collection will be completed on December 10,1993; the data indicates that the AFHB airborne particulate generation rate has remained at less than 5% of the acceptance criterion of License Condition 2.D. for the entire data collection period. The final few weeks of data are expected to be consistent with the prior data.
EE"n8s Main E
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PDR E.
GPU Nuclear Corporation is a subsidiary of General Pubitc Utibties Corporation
l Document'Contml Desk November 12,1993 C312-93-2072 i
C000-93-2265 Page 2 i
Therefore, GPU Nuclear is pmpared to transition to PDMS on' December 13,1993 (30 days from the date of this letter). Please issue the TMI-2 PDMS Technical Specifications'to be effective on that date.
Sincerely,
'j
/
R L. Long Director, Services Division /TMI-2 l
r EDS/dlb Enclosure
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cc:
M. G. Evans - Senior Resident Inspector, TMI l
T. T. Martin - Regional Administrator, Region I M. T. Masnik - Project Manager, PDNP Directorate L. H. Thonus - Project Manager, TMI 3
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ENCLOSURE 1 PDMS ENTRY REOUIREMENTS TAC 5 or IR f GPU Nuclear Letter Signifying License Conditions Documentino Closure Date
'NRC Approval 2.D. Special AFHB Ventilation Study To Be Completed 12/10/93 F
2.E. Unfiltered Leak Rate Test C312-93-2001 1/18/93 2.F. Additional Submittals a.
Site Flood Protection Plan C312-92-2091 1/4/93-N/A b.
Site Radiation Protection Plan C312-92-2091 1/4/93 N/A c.
Offsite Dose Calculation Manual C312-93-2077 11/12/93 N/A d.
Fire Protection Program Evaluation C312-93-2064 10/14/93 N/A' e.
Radiological Environmental Monitoring Plan C312-92-2091 1/4/93 N/A f.
Plant Radiation and Contamination Surveys C312-93-2079 11/12/93 N/A Additional Recuirements/ Licensee Commitments A.
Removal of Water from Reactor Coolant System and Fuel Transfer Canal 1.
Remove water to the extent reasonably achievable.
Reactor Vessel; drained to less than C312-93-2023 6/1/93 10 gallons (38 liters) of water.
- Reactor Building Fuel Transfer Canal.
C312-93-2023 6/1/93 (TER 5-9) 2.
Isolate the' fuel transfer tubes.
C312-93-2023 6/1/93 (SAR 1.1.2.1).
3.
Drill holes in canal seal plate to-prevent C312-93-2023 6/1/93 refueling canal from filling.
(TER 5-9) 4.
Cover the Reactor Vessel to minimize water-C312-93-2023 6/1/93 i
entry. (SAR 6.2.27.2) 5.
Drain the Submerged Demineralizer System to C312-92-2023 6/1/93 the extent reasonably achievable (SAR 6.2.36.2)'
November 1993 a,_-.--....
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PDMS ENTRY REOUIREMENTS TAC i or 1R I 1-GPU Nuclear Letter Signifying.
's Additional Recuirements/ Licensee Commitments Documentina Clcsure Date NRC Anproval 6.
Drain and cover the "B" spent fuel pool C312-93-2062 9/15/93 to the extent reasonably achievable.
(SAR 6.2.36.2) 7.
Drain and cover the "A" spent fuel pool to C312-93-2062 9/15/93 the extent reasonably achievable.
(SAR 6.2.3.2)
.. i B.
Radiation Safety & Reduction of Potential for Releases 1.
Ship offsite or package and stage for C312-93-2073 11/12/93 shipment remaining radioactive waste from the major TMI decontamination activities.
Reduce radiation levels.within the facility, C312-93-2073 11/12/93 to the extent reasonably achievable and consistent with ALARA, to allow plant monitoring, maintenance, and inspection.
Apply shielding in critical locations after C312-93-2023 6/1/93 reactor vessel draindown to reduce dose rates.
(TER.5-23) 4.
Define and establish an overall surveillance C312-93-2073 11/12/93 program plan for PDMS environmental protection systems to ensure public health and safety.
(TER xiv)
C.
Ventilation 1.
Verify that a surveillance program exists to C312-93-2023 6/1/93 ensure AFHB ventilation and filtration operability, maintenance and testing.
(SAR 7.1.2 and 7.1.3; TER 6-26) 2.
Verify that the licensee has procedures in C312-93-2062 9/15/93 place'to continue to operate the AFHB ventilation. system.until-the. Accident Generated Water is no longer being processed or transferred in the AFHB. (TER 6-28).
November.1993 a.
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PDMS ENTRY REOUIREMENTS TAC i or IR $
GPU Nuclear Letter Signifying Additional Reauirements/ Licensee Commitments Documentino Closure Date NRC ADDroval.
3.
Ensure that penetration R-626 has been C312-93-2062 9/15/93
. upgraded to 5 psi. (SAR Supp.
3, Item B.2; TER 6-17) 4.
Ensure that the reactor building breather C312-93-2062 9/15/93
. system is the predominant pathway for effluent
.and influent to the building during those times that the reactor building ventilation system.is not being operated; and that the effluent is filtered and monitored.
(SAR-7.2.1.2; TER 6-25).
5.
DOP' test the HEPA filter in breather prior C312-93-2062 9/15/93 to entry into PDMS.
(SAR-7.2.1.2.2 and Supp. 3, Item B.3; TER 6-25) 6.
Ensure installation, actuation setting, and C312-93-2069 11/2/93 routine surveillance testing of the isolation valve'between containment and HEPA filter in the reactor building breather (to automatically close upon receipt of a containment pressure increase of 0.25 psi). (SAR 7.2.1.2; TER 5-10, 5-11, and 6-24) 7.
Develop and implement a reactor building entry C312-93-2023 6/1/93 procedure that requires an eva'.uation of the reactor building atmospheric conditions prior to personnel entry.
(SAR~7.2.1.3) 8.
Develop and implement procedures.foi maintaining C312-93-2023 6/1/93 HEPA filter banks for the Reactor Building Purge
' System.(SAR 7.2.1.3) 9.
Develop and implement procedures for monitoring C312-93-2023 6/1/93 the Reactor' Building vent during reactor
. building purge. (SAR 7.2.1.3)
D.
Plant Contamination Survey 1.
Licensee will meet established contamination.
C312-93-2073 11/12/93 level goals for entrance'into PDMS for each.
area of the AFHB.
If the decontamination goals cannot be met because of the unique
- situation at TMI-2 or ALARA, considerations,'
No'rember 1993'
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e PDMS ENTRY REOUIREMENTS TAC # or IR f*
GPU Nuclear Letter Signifying Additional Recuirements/ Licensee Commitments Documentino Closure Date NEC Anoroval the licensee will provide an evaluation of the specific situation to the NRC. (SAR 5.3.1 and Supp.
3,. Item A.11; TER p. 4-2) 2.
Update information in the following tables from C312-93-2073 11/12/93 the SAR as final decontamination results become available. (SAR 5.3.2)
- Table 5.3-2 (SAR) "PDMS. Radiological Conditions - AFHB"
- Table 5.3-4 " Surface Contmmination - Reactor Building"
- Table 5.3-5 " Surface Contamination - AFHB"
- Table 5.3-6 " Surface Contamination - Other Buildings" 3.
Perform survey of the' service building, C312-93-2073 11/12/93 elevation 305 ft.; the turbine building, elevation 281 ft. and the containment air control' envelope building and provide information in the PDMS SAR before entry.
into PDMS in order to establish a radiological baseline for the facility.-(SAR 5.3.2; TER 4-2) 4.
Ensure that a program exists for periodic C312-93-2073 11/12/93 measurement of radiation and contamination levels-to verify radiological conditions.
(SAR 7.2.4.1 and.7.2.4.2; TER.6-42 and 6-43).
E.
Physical Maintenance in Reactor Building'and Vessel 1.
Have the capability of inserting a video C312-93-2062 9/15/93 camera into the reactor vessel to verify fuel location if it.is determined at a later time that such an examination is required.
(TER 6-3).
2.
Create a program plan;to perform' monthly C312-93-2062 9/15/93 entries into the reactor. building'for at' least_6 months after placing it,into its PDMS condition. (PDMS SAR 7.2.4; TER 5-23)
November 1993-2..
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L PDMS ENTRY REOUIREMENTS TAC # or IR 4 '
GPU Nuclear Letter Signifying i
Additional Recuirements/ Licensee Commitments Documentine Closure Date NRC Aporoval F.
Physical Maintenance in AFHB 1.
Create a program plan to perform monthly C312-93-2073 11/12/93 entries.into the AFHB for at least 6 months after placing it-into its PDMS condition.
. Ensure that both fuel pool structures remain C312-93-2062 9/15/93 intact (SAR 7.1.3.2)
C.
Physical Maintenance in other Buildings 1.
- Ensure that the Control Room Ventilation C312-93-2069 11/2/93 Systems (i.e., Control Room HVAC and Cable Room HVAC) and the Service Building Ventilation System are maintained in an operational condition and will be operated as required.
(SAR 7.2.6.8,9,10) 2.
Maintain the capability to process potentially C312-93-2023 6/1/93 contaminated liquids.
H.
Electrical Related 1.
In reactor containment, reactor building C312-93-2023 6/1/93 electric power. circuits will be deenergized t
^
except tnose necessary for PDMS monitoring, inspection,.and surveillance equipment and other PDMS support requirements.
(SAR 7.1.1.4; Supp.
1, Item 17; TER 6-34 and 6-38) 2.
In the auxiliary building, the power to C312-93-2062 9/15/93 lighting, fire detectors, and sump level indication circuits will be energized and will remain operational. The auxiliary sump, auxiliary sump tank and associated level indication will also remain operational.
3.
In the fuel-handling building, low voltage C312-93-2062 9/15/93 circuits to lighting and fire detection will be energized. (SAR 7.1 3 2;-TER 6-37)
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GPU Nuclear Letter Signifying Additional Recuirements/ Licensee Commitments Docurentina Closure Date NRC Approval
.r 4.
In the control and Service Buildings, verify C312-93-2062 9/15/93 that the electrical distribution will remain N-configured to power low voltage lighting loads and fire detectors. (SAR 7.1.7.2) 5.
Portions of the TMI-2 electrical distribution C312-93-2062 9/15/93 system will be operational and energized to
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provide power for the PDMS support systems and their associated controls and instrumentation.
Power will be available'for area lighting, receptacles, heating, and ventilation to i
support PDMS activities. (SAR 7.2.5.1.1; TER 6-37) 6.
Emergency lighting (8-hr portable emergency C312-93-2069 11/2/93 lights) is staged with emergency response crew equipment. (SAR 7.~.5.2.1; TER 6-37) 7.
Verify that exit signs are powered from the C312-93-2073 11/12/93 normal lighting system.
(SAR 7.2.5.2.2) 8.
DC power during PDMS will be available.
C312-93-2069 11/2/93 Loads have been consolidated where practicable to reduce the number of energized circuits.
Deleted N/A N/A N/A I.
Fire Protection 1.
Have procedures in place to ensure that C312-93-2062 9/15/93 the fire mains within the reactor building i
will be closed with valves drained to the-extent reasonably. achievable within 30 days following entry into PDMS to minimize the potential for introduction of water into the reactor vessel.-(SAR 7.2.2.21~.;..
-TER 6-2) t.
l November 1993 2..
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PDMS ENTRY REOUIREMENTS TAC I or IR #
- GPU Nuclear Letter Signifying Additional Recuirements/ Licensee Commitments Documentino Closure Date NRC Anoroval 2.
Deleted.
N/A N/A N/A 3.
Ensure that either the TMI-2 control room C312-93-2069 11/2/93 or some other location is continuously manned with a fully qualified person or that remote monitoring capabilities are available in TMI-1 control room to identify the specific zone panel which indicates the location of the fire in the TMI-2 facility.
Ensure that procedural control exists to delineate the location of the monitoring activity.
(T'R 6-29; SAR 7.2.2.2b.)
4.
Demonstrate that TMI-1 Operations has C312-93-2069 11/2/93 accepted responsibility for maintaining the fire service system in operable areas of the plant as required to support operations in the waste-handling and packaging facility, the respirator cleaning facility and the. administration building. (TER 6-29) 5.
Deactivate deluge systems in the auxiliary C312-93-2062 9/15/93 building and the control building.
Ensure that all Halon systems have been' C312-93-2073 11/12/93 deactivated by disconnecting the cylinders and either emptying or removing them.
(SAR 7.2.2.2d.)
7.
Verify that portable fire extinguishers are C312-93-2073 11/12/93 staged with emergency response crew equipment. -(SAR 7.2.2.2e.)
B.
Verify that self-contained breathing apparatus C312-93-2069 11/2/93 are staged with emergency' response crew-equipment.
(SAR 7.2.2.2e.)'
November 1993
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b PDMS ENTRY REOUIREMENTS TAC 4 or IR #
GPU Nuclear Letter Signifying Additional Recuirements/ Licensee Commitments Documentino Closure Date NRC Anproval 9.
Ensure that the fire detection system C312-93-2023 6/1/93 remains operational in the Air' Intake Tunnel and the relay room.
(SAR 7.2.2.2d.)
- 10. Deleted N/A N/A N/A
- 31. To the extent that fire protection is not C312-93-2073 11/12/93 required in work or storage areas, ensure isolation of the 12-inch fire service loop, which runs through the AFHB, the control building area and the turbine building (east and west). (SAR 7.2.2.2i.; TER 6-32)
- 12. Ensure that the fire system line is cut.
C312-93-2023 6/1/93
-i
-and blanked off at the fuel-handling building, where the fire system line runs from the diesel generator building. (SAR 7.2.2.2i.;
i TER 6-32) 13.. Deactivate river water pump house.
C312-93-2073 11/12/93 (SAR 6.1.10; TER 6-33)
- 14. Deactivate the fire pump house. - (SAR 6.1.10 C312-93-2073 11/12/93 and Supp.
1, Item 14; TER 6-33)
- 15. Ensure that transient combustibles have C312-93-2073 11/12/93 been removed from inside the containment and the AFHB to the extent practicable.
(SAR 7.2.2.2f.; TER 6-33) This includes most plant items installed after the. _
. accident.
Fire loading must be less than a 1-hour loading of 80,000 BTU / square foot.
(SAR Supp. 1, Item 17)
- 16. Drain oil to the extent reasonably aihievable C312-93-2062 9/15/93 from the main turbine, feedwater. pump turbines, emergency feedwater pump turbine,.
main feedwater pumps, emergency feedwater' pumps, condensate pumps, condensate booster pumps, and hydrogen seal oil unit.
November 1993.
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t PDMS ENTRY REOUIREMENTS TAC 4 or-IR i '
GPU Nuclear Letter Signifying Additional Recuirements/ Licensee Commitments Documentina Closure Date NRC Annroval-t
- 17. Taken as an aggregate, demonstrate that no C312-93-2023 6/1/93 more than 57 percent of the original total volume of reactor coolant pump lubricating oil remains in the upper and lower reservoirs of the four reactor coolant pump reservoirs.
i (SAR Supp.
1, Item 33; TER 6-34) l
- 18. Charcoal filters have been removed from all C312-93-2062 9/15/93 HVAC systems in TMI-2. (SAR 7.2.2.2h.; TER 6-34)
- 19. Train and familiarize station fire brigade C312-93-2069 11/2/93 with the TMI-2 system configurations, plant-layout and procedures for TMI-2.
- 20. Procedure in place for reactivation of the C312-93-2073 11/12/93
. deactivated portions of the fire protection system if necessary. (SAR 7.2.2.2j.; TER 6-29)
- 21. Verify that the procedure for inspection of C312-93-2073 11/12/93 the fire loop drain valves during freezing weather is in place. (SAR 7.2.2.21.; TER 6-32) 1 22 Verify that the procedures and system are in C312-93-2023 6/1/93 place for testing of the operable portion of the fire detection and alarm system.
- 23. Verify that procedures for manual suppression C312-93-2062 9/15/93 of fire by the fire brigade are provided as stated in the FPPE. (TER 6-35)
J.
Flood Protection 1.
Ensure that flood panels are provided forfall C312-93-2023 6/1/93 entrances to the control building, and to the entrance of the auxiliary building (TER 6-36)
Doorstand entrances to the Control Building Area that are not. flood-protected are either watertight or are.provided-withLflood panels.
All openings that are potential leak paths (i.e.,. ducts, pipes, conduits, cable trays) are sealed. (SAR 7.1.4)
November 1993
r PDMS ENTRY REOUIREMENTS TAC 4 or IR I GPU Nuclear Letter Signifying Additional Reauirements/ Licensee Conmitments Documentinc Closure p_aB NRC Accroval 1r 2.
Verify that the containment basement and C312-93-2023 6/1/93 auxiliary building sumps level indications z
will be maintained.
(SAR 7.2.3.1.2) 3.
Verify that the auxiliary building sump C312-93-2023 6/1/93 pumps are maintained operational and placed in a manual control mode. (SAR 7.2.3.1.2) 4.
Verify-that the Miscellaneous Waste Holdup C312-93-2062 9/15/93 Tank and the Auxiliary Building. Sump Tank (ABST) have been isolated from the Radwaste Disposal Gas System and vented via HEPA filters to protect against airborne releases from these tanks. (SAR 7.2.3.1.2) 5.
Ensure that a flow path exists to drain down C312-93-2023 6/1/93 the reactor building basement floor.
(SAR 7.2.3.1.2) 6.
Deleted ~
N/A N/A N/A 7.
Deleted N/A N/A N/A 8.
Ensur9 that the active sumpo have a high C312-93-2069 11/2/93 leve'& alarm that annunciates'in the control toom and the PDMS Alarm Monitoring System.
(SAR 7.2.3.2.2)
K.
Procedures and Programs 1.
Include a surveillance program under which
. C312-93-2023 6/1/93 a limited number of rodent carcasses will be analyzed for gamma-emitting isotopes as part
. of the non-routine Radiological Environmental Monitoring Program. (SAR Supplement 3, A.16) l' n.
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