ML20057B973

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Provides Second Group of Completed Defueling Monitored Storage Requirements & Commitments
ML20057B973
Person / Time
Site: Crane Constellation icon.png
Issue date: 09/15/1993
From: Long R
GENERAL PUBLIC UTILITIES CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C-93-2205, C000-93-2205, C312-93-2062, NUDOCS 9309240225
Download: ML20057B973 (15)
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GPU Nuclear Corporation

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Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Nurnber:

(717) 948-8400 September 15, 1993 C312-93-2062 C000-93-2205 US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Three Mile Island Nuclear Station Unit 2 (TMI-2)

Operating License No. DPR-73 Docket No. 50-320 Completed PDMS Requirements and Commitments

Dear Sir:

The NRC letter, " Review of the May 28, 1993, Request to Revise the TMI-2 PDMS Requirements and Commitments," dated August 5,1993, provides a revised list of Post-Defueling Monitored Storage (PDMS) Requirements and Commitments. GPU Nuclear letter C312-93-2023, dated June 1,1993, initiated the NRC review and approval process by providing a list of completed PDMS Requirements and Commitments. The purpose of this letter is to provide a second group of completed PDMS Requirements and Commitments. Enclosum I includes a table of all PDMS Requirements and Commitments, along with the GPU Nuclear letter number that pmvides closeout documentation and the NRC cormspondence that provides NRC approval of each closed-out requirement. provides a refemnce to the documentation for each requirement in this second gmup which has been closed-out. The close-out documentation is available for your review in the TMI-2 Licensing office in the TMI South Office Building.

Jincemly,

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R. L. Long Director, Servi Division /TMI-2 EDS/dlb Enclosures 23{}(j G3 cc: See Page 2 9309240225 930915 hi l

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UPU Nuciear Corporation is a subsid ary of General Pubhc UtMes Corporation l

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Document Control Desk September 15, 1993 C312-93-2062 i

C000-93-2205 Page 2 cc:

M.- Evans - Senior Resident Inspector, TMI T. T. Manin - Regional Administrator, Region I-M. T. Masnik - Project Manager, PDNP Dimetorate L. II. Thonus - Project Manager, TMI 4

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ENCLOSURE 1 t

PDMS ENTRY REOUIREMENTS TAC f or IR #

GPU Nuclear Letter Signifying p

License Conditions Documentina Closure Date NRC ADoroval 2.D. Special AFHB Ventilation Study i

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 d.

Fire Protection Program Evaluation N/A e.

Radiological Environmental Monitoring Plan C312-92-2091 1/4/93 N/A f.

. Plant Radiation and Contamination Surveys 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 5/28/93 10 gallons (38 liters) of water.

(SAR 6.2.27.2; TER 5-9) 1

- Reactor Building Fuel' Transfer Canal.

C312-93-2023 5/28/93 r

(TER 5-9) 2.

Isolate the fuel transfer tubes.

C312-93-2023 5/28/93 (SAR 1.1.2.1).

i 3.

Drill holes in canal. seal plate to prevent C312-93-2023 5/28/93 L

refueling canal from filling.

(TER 5-9) 4.

Cover the Reactor Vessel to minimize water C312-93-2023 5/28/93 entry. (SAR 6.2.27.2) 1 5.

Drain the Submerged Demineralizer System to C312-92-2023 5/28/93 I

the extent reasonably achievable.

(SAR 6.2.36.2)

September 1993 r

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PDMS ENTRY REOUIREMENTS TAC 4 or IR #

GPU Nuclear Letter Signifying Additional Recuirements/ Licensee Commitments Documentinc Closure Date NRC Annroval 6.

Drain.and cover the "B"

spent fuel pool C312-93-2062 to the' extent reasonably achievable.

(SAR 6.2.36.2) 7.- Drain and cover the "A" spent fuel pool to C312-93-2062 the extent reasonably achievable.

(SAR 6.2.3.2)

B.

Radiation Safety & Reduction of Potential for Releases 1.

Ship offsite or package and stage for shipment remaining radioactive waste from the major TMI decontamination activities.

(SAR 1.1.2.1; TER xiv) 2.

Reduce radiation levels within the facility, to the extent reasonably achievable and consistent with ALARA, to allow plant monitoring, maintenance, and inspection.

(SAR 1.1.2.1; TER xiv) 3.

Apply shielding in critical locations after C312-93-2023 5/28/93 reactor vessel draindown to reduce dose rates.

(TER 5-23) 4.

Define and establish an overall surveillance program plan for PDMS environmental protection systems to e..sure public health and safety.

(TER xiv) i C.

Ventilation 1.

Verify that a surveillance program exists to C312-93-2923 5/28/93 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 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)

September 1993

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4 PDMS ENTRY REOUIREMENTS TAC i or IR I

  • GPU Nuclear Letter Signifying Additional Recuirements/ Licensee Commitments Documentina Closure Date NRC Accroval 3.

Ensure that penetration R-626 has been C312-93-2062 upgraded to 5 psi. (SAR Supp.

3, Item B.2; TER 6-17) 4.

Ensure that the reactor building breather C312-93-2062 system is the predominant pathway for effluent i

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 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 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 5/28/93 procedure that_ requires an evaluation of the reactor building atmospheric conditions prior to personnel entry.

(SAR 7.2.1.3) 6.

Develop and implement procedures for maintaining C312-93-2023 5/28/93 HEPA filtar banks for the Reactor Building Purge i

System.(SAR 7.2.1.3) 9.

Develop and implement procedures for monitoring C312-93-2023 5/28/93 the Reactor Building vent during reactor building purge. (SAR 7.2.1.3)

D.

' Plant Contamination Survey I

1.

Licensee will meet established contamination l

level goals for entrance into PDMS for each I

area of the AFHB. -If the decontamination l

goals cannot be met because of the unique situation at TMI-2 or ALARA considerations,-

September 1993 l

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PDMS ENTRY REOUIREMENTS TAC i or IR 4 -

GPU Nuclear Letter Signifying Additional Recuirements/ Licensee Commitments Documentina Closure Date NRC 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 the SAR as final decontamination results become available. (SAR 5.3.2)

- Table 5.3-2 (SAR) *PDMS Radiological

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Conditions - AFHB"

- Table 5.3-4 " Surface Contamination - Reactor Building" 1

- Table 5.3-5 " Surface Contamination - AFHB"

- Table 5.3-6 " Surface Contamination - Other Buildings" 3.

Perform survey of the service building, elevation 305 ft.; the turbine building, elevation 281 ft. and the containment air 4

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) i 4.

Ensure that a program exists for periodic 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 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 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)

September 1993

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PDMS ENTRY REQUIREMENTS TAC i or IR 8 GPU Nuclear Letter Signifying Additional Recuirements/ Licensee Commitments Documentina Closure Date NRC Anoroval F.

Physical Maintenance in AFHB 2

1.

Create a program plan to perform monthly entries into the AFHB for at least 6 months after placing it into its PDMS condition.

(SAR 7.2.4; TER 5-23) 2.

Ensure that both fuel pool structures remain C312-93-2062 intact (SAR 7.1.3.2)

G.

Physical Maintenance in other Buildings 1.

Ensure that the Control Room Ventilation Systems (i.e., Control Room HVAC and Cable Room KVAC) 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 5/28/93 contaminated liquids.

(SAR 7.2.3.1; TER 5-14) 3.

Electrical Related 1.

In reactor containment, reactor building C312-93-2023 5/28/93 electric power circuits will be deenergized except those 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 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.

(SAR 7.1.2.2; TER 6-37) 3.

In the fuel-handling building, low voltage C312-93-2062 circuits to lighting and fire detection will be energized.' (SAR 7.1.3.2;_TER 6-37)

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PDMS ENTRY REOUIREMENTS TAC i or IR #

GPU Nuclear Letter Signifying

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Additional Recuirements/ Licensee Commitments Documentina Closure Date NRC Acoroval 4.

In the control and Service Buildings, verify C312-93-2062 that the electrical distribution will remain configured to power low voltage lighting loads and fire detectors. (SAR 7.1.7.2) 5.

Portions of the THI-2 electrical. distribution C312-93-2062 system will be operational and energized to F

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 support PDMS activities. (SAR 7.2.5.1.1; TER 6-37) 6.

Emergency lighting (8-hr portable emergency lights)'is staged with emergency response crew equipment. (SAR-7.2.5.2.1; TER 6-37) 7.

Verify'that exit signs are powered from the i

normal lighting system and'from a locally mounted battery during emergency conditions.

(SAR 7.2.5.2.2) 8.

DC power during PDMS will'be available.

Loads have been consolidated where practicable to reduce the number of energized circuits.

(SAR 7.2.5.1.3;'TER 6-38) 9.

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Fire Protection 1.

Have procedures in place to ensure that C312-93-2062 l

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 PDMSuto minimize the potential for introduction of water into the reactor vessel. (SAR 7.2.2.2k.;

TER 6-2)

September 1993 1

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PDMS ENTRY REOUIREMENTS TAC # or IR 4 GPU Nuclear Letter Signifying Additional Recuirements/ Licensee Commitments Documentino Closure Date NRC Accroval 2.

Ensure that automatic fire suppression is provided and maintained to areas of the facility and systems which contain significant amounts of combustibles and possible ignition sources.

(SAR 7.2.2.1) 3.

Ensure that either the THI-2. control room 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 in which a fire in the.

TMI-2 facility is located. Ensure'that procedural control exists to delineate the location of the monitoring activity.

(TER 6-29; SAR 7.2.2.2b.}

4.

Demonstrate that TMI-1 Operations has 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 building and the control building.

(SAR 7.2.2.3; TER 6-29) 6.

Ensure that all Halon systems have been deactivated by disconnecting the cylinders and either emptying or removing them.

(SAR 7.2.2.2d.)

7.

Verify that portable fire extinguishers are located in the areas specified in Figures 7.2-6 and 7.2-7 of the SAR. (SAR.7.2.2.2e.)

8.

Verify that self-contained breathing apparatus are available for fire fighting purposes in the areas shown on Figures 7.2-6 and 7.2-7 of the SAR. (SAR 7.2.2.2f.)

September 1993

PDMS ENTRY REQUIREMENTS TAC 4 or IR 4 GPU Nuclear Letter Signifying Additional Reauirements/ Licensee Commitments Documentina Closure Date NRC Annroval 9.

Ensure that the fire detection system C312-93-2023 5/28/93 remains operational in the Air Intake Tunnel and the relay room.

(SAR 7.2.2.2d.)

10. Deleted N/A N/A N/A
11. To the extent that fire protection is not 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 7.2.2.2k.; TER 6-32)
12. Ensure that'the fire system line is cut C312-93-2023 5/28/93 and blanked off at the fuel-handling building, r

where the fire system line runs from the diesel generator building. (SAR 7.2.2.2k.;

TER 6-32)

13. Deactivate river water pump house.

-(SAR 6.1.10; TER 6-33) 14.. Deactivate the fire-pump house.

(SAR 6.1.10 and Supp.

1, Item 14; TER 6-33)

15. Ensure that transient combustibles have been removed from inside the containment and the AFHB to the extent practicable.

(SAR 7.2.2.2g.; TER 6-33)

This includes most plant items installed after the accident.

Fire loading must be less than

'1 a 1-hour loading of 80,000 BTU / square. foot.

(SAR Supp.

1, Item'17)

16. Drain oil to the extent reasonably achievable C312-93-2062 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.

(SAR 7.2.2.2h.; TER 6-34)

September 1993

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PDMS ENTRY REQUIREMENTS TAC l'or.IR 4.-

GPU Nuclear Letter Signifying

- g Additional Recuirements/ Licensee Commitments Documentino Closure pate NRC Acoroval i

17. Taken as an aggregate, demonstrate that no-C312-93-2023 5/28/93 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.

(SAR Supp. 1, Item 33; TER 6-34)

18. Charcoal filters have been removed from all C312-93-2062 HVAC systems in TMI-2. (SAR 7.2.2.21.; TER 6-34)
19. Train and familiarize station fire brigade with the TMI-2 system configurations, plant layout and procedures for TMI-2.

(SAR 7.2.2.2m.; TER 6-35) ra in place for reactivation of'the

20. Pr e-d4 -

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t necr sary (SAR 7.2.2.21.; TER 6-29) 21.

liy that the srocedure for inspection of the fire loop drain valves during freezing weather is in place. (SAR 7.2.2.2k.; TER 6-32)

22. Verify that the procedures and system are in C312-93-2023 5/28/93 place for testing of the operable portion of the fire detection and alarm systen (SAR 7.2.2.2b.; TER 6-34)
23. Verify that procedures for manual suppression C312-93-2062 of fire by the fire brigade are provided as stated in the FPPE. (TER 6-35)

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Flood Protection 1.

. Ensure that flood panels are provided for all C312-93-2023 5/28/93

. entrances to the control building, and to the entrance of the auxiliary building (TER 6-36)

Doors and entrances to the Control Building Area that are not flood-protected are either watertight or are provided with flood panels.

All. openings that.are potential leak paths (i.e., ducts, pipes, conduits, cable trays) are sealed. (SAR 7.1.4) i September 1993 i

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PDMS ENTRY REOUIREMENTS 3

TAC i or IR-i GPU Nuclear Letter

' Signifying Additional Reauirements/ Licensee Commitments Documentino Closure Date NRC Anoroval

- 2.

Verify that the containment basement and C312-93-2023 5/28/93 auxiliary building sumps level indications will be maintained.

(SAR 7.2.3.1.2) 3.

Verify that the auxiliary bui'ltng sump C312-93-2023 5/28/93 pumps are maintained operati

.ind placed in a manual control mode. '<3 - ' 2. 3.1. 2 )

4.

Verify that the.Miscellanet..* daste Holdup C312-93-2062 Tank and the auxiliary Builoing Sump Tank r

(ABST) have been isolated from the Radwaste Disposal Gas System and vented via HEPA filters to protect against airborne releases from these tanhs. (SAR 7.2.3.1.2)

Li 5.

Ensure that a flow path exists to drain down C312-93-2023 5/28/93 the reactor building basement floor.

(SAR 7.2.3.1.2) 1 6.

Deleted N/A N/A N/A 7.

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8.

Ensure that the active sumps have a high.

level alarm that annunciates in the control room and the PDMS Alarm Monitoring System.

= i (SAR 7.2.3.2.2)

K.

Procedures and Programs i

1.

Include a surveillance program under which C312-93-2023 5/28/93 I

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)

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l ENCLOSURE 2 CLOSEOUT DOCUMENTATION PDMS Requirements and Commitments Additional Recuirements/ Licensee Commitments Closcout Documents 8 A.

Removal of Water from Reactor Coolant System and Fuel Transfer Canal 6.

Drain and cover the "B"

spent fuel pool MMB 3160-93-0246; UWIs to the extent reasonable achievable.

4215-3232-92-090 and (SAR 6.2 36.2) 4220-3161-93-J216 7.

Drain and cover the "A" spent. fuel pool MMB 3160-90-0188 to the extent reasonable achievable.

UWI 4210-3161-92-056 (SAR 6.2.3.2)

C.

Ventilation 2.

Verify that the licensee has procedures in AGW processing has been place to continue to operate the AFHB completed, Therefore, the ventilation system until the Accident conditions of this require-Generated Water is no longer being ment have been satisfied.

processed or transferred in the AFHB, (TER 6-28) 3.

Ensure that penetration R-626 has been MMA 3244-91-0197; j

upgraded to 5 psi.

(SAR Supp. 3, Item B.2; UWI 4720-3244-91-J080 TER 6-17)

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4.

Ensure that the reactor building breather Performance of Surveillance system is the predominant pathway for procedure 4210-SUR-3824.03 effluent and influent to the building during August 13 through during those times that the reactor building 16, 1993 indicates that j

ventilation system is not being operated; flowrate through the RB and that the effluent is filtered and Breather is approximately i

monitored. (SAR 7.2.1.2; TER 6-25) 580 times greater than the RB leak rate. This exceeds the criterion of 100 established in the PDMS.

r SAR.

9 Operating procedure 4210-OPS-3824.03; Surveillance procedure i

4210-SUR-3824.04 5.

DOP test the HEPA 2ilter in breather prior UWI 4220-3824-91-J079 to entry into PDMS.

(SAR 7.2.1.2.2 and Supp. 3, Item B 3; TER 6-25)

E.

Physical Maintenance in Reactor Building and Vessel

+

1.

Have the capability of inserting a video Surveillance procedure camera into the reactor vessel to verify 4210-SUR-3221.01 fuel location if it is determined at a l'

later time that such an examination is required.

(TER 6-3) 7 i

  • UwI - Unit Work Instruction MMA/B - Mini-mod category "A" or "B"

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' Additional Recuirements/ Licensee Commitments Closeout Documents-2.

Create a program plan to perform monthly Surveillance procedure f

entrie's into the reactor building for at 4210-SUR-3824.06 least 6 months after placing it into its PDMS condition.

(SAR 7.2.4; TER 5-23)

F.

Physical' Maintenance in AFHB 1

2.

Ensure that both fuel pool structures A plant walkdown will j

remain intact (SAR 7.1.3.2) show that both. fuel pool.

structures are intact.

H.

Electrical Related i

I 2.

In the auxiliary building, the power to Operating procedures lighting, fire detectors, and sump level 4210-OPS-3570.01, 4210-indication circuits will be energized and OPS-3730.01, 4210-OPS-will remain operational. The auxiliary.

3810.01, and 4215-OPS-sump, auxiliary sump tank and associated 3232.17.

level indication will also remain operational.

(SAR 7.1.2.2; TER 6-37)

-j 3.

In the fuel-handling building, low voltage Operating procedure I

circuits to lighting and fire detection 4210-OPS-3730.01 will be energized.

(SAR 7.1.3.2; TER 6-37) 4.

In the Control and Service Buildings, Operating procedure j

verify that the electrical distribution 4210-OPS-3730.01 will remain configured to power lou voltage lighting loads and fire detectors.

(SAR 7.1.7.2)

S.

Portions of the TMI-2 electrical distri-Operating procedure bution system will be operational and 4210-OPS-3730.01 energized to provide power for the PDHS support systems and their associated controls and instrumentation.

Power will be available for area lighting, receptacles, heating, and ventilation to support PDMS activities.

(SAR 7.2.5.1.1; TER 6-37)

I.

Fire Protection f

1.

Have procedures in place to ensure that the UWI 4210-3810-92-111 fire mains within the reactor building will be closed with valves drained to the l

extent reasonably achievable within 30 days 4

following entry into PDMS to minimize the i

potential for introduction of water into the reactor vessel.

(SAR 7.2.2.2k.; TER 6-2) l I

5.

Deactivate deluge systems in the auxiliary Operating procedure i

building and the control building.

(SAR 4210-OPS-3810.01 7.2.2.3; TER 6-29) i

16. Drain oil to the extent reasonably UWIs 4210-3314-87-306, i

achievable from the main turbine, feedwater 4210-3321-86-053, 4210-i pump turbines, emergency feedwater pump 3321-88-179, 4220-3421-l turbine, main feedwater pumps, emergency 87-H324, 4220-3421-87-H354, i

icedwater pumps, condensate pumps, condon-4220-3421-87-H395, 4220-

)

sate booster pumps, and hydrogen seal oil 3424-87-H394. Condensate unit.

(SAR 7.2.2.2h.; TER 6-34) pump CO-P-1B was removed in 1979; visual verifi-j cation must be made.

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  • Additional Fecuirements/ Licensee Commitments Cloueout Documents 1 i

~18. Charcoal filters have been removed from Internal memorandum 4240-

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all HVAC systems in THI-2.93-069, dated 07/29/93.

(SAR 7.2.2.21.; TER 6-34)

UWIs 4220-3231-92-J199, 4220-3820-85-F095, 4220-3826-92-J118, 4220-3829 ;

- F096, 4220-3829-92-J112, 4220-3830-92-J111, 4220-3830-92-J132, and 4220-l 3835-92-J115; Job Ticket C5502

23. Verity that procedures for manual Operating procedures suppression of fire by the fire brigade EP 1105-22 and EP 1202-31 are provided as stated in the FPPE.

l (TER 6-25)

J.

Flood Protection 4.

Verify that the Miscellaneous Waste MMA 3231-92-0231,

[

Holdup Tank and the Auxiliary Building UWI 4220-3231-92-J199 Sump Tank (ABST) have been isolated from i

the Radwaste Disposal Gas System and i

vented via HEPA filters to protect against airborne releases from these tanks.

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