ML20125C417
| ML20125C417 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/07/1992 |
| From: | Masnik M Office of Nuclear Reactor Regulation |
| To: | Long R GENERAL PUBLIC UTILITIES CORP. |
| References | |
| NUDOCS 9212110180 | |
| Download: ML20125C417 (14) | |
Text
..
ock'et No. 50-320 December 7, 1992 Dr. Robert L. ' ong Director, Corporate Services /
Director, TMI-2 GPU Nuclear Corporation Post Office Box 480 Middletown, Pennsylvania 17057-0191
Dear Dr. Long:
SUBJECT:
PROPOSED LIST OF REMAINING TMI-2 RELATED REQUIREMENTS OR COMMITMENTS FOR DISCUSSION AT THE DECEMBER 8, 1992 MEETING AT THE TMI SITE The staff has completed a review of the Post-Defueling Monitored Storage (PDMS) Safety Analysis Report (SAR) as well as the NRC prepared Safety Evaluation Report and the Technical Evaluation Report for PDMS.
Based on that review, the staff has identified specific requkements and commitments that need to be implemented or satisfied by GPU Nuclear at Three Mile Island Nuclear Station Unit 2 (TMI-2) prior to entry into PDMS.
Staff identified requirements and commitments are listed in the enclosure.
The staff recognizes. that many of the items listed in the enclosure have already been completed, however, they are listed because the NRC staff has not verified the item's status.
This list will be the subject of the December 8,1992 meeting between your staff and the NRC at the TMI Training Center. We plan to briefly discuss each item with your staff, determining the status of completion or implementation, and discuss what would constitute adequate demonstration that the item had been resolved. Also, we would like to discuss a procedure for modifying the list. A staff proposal for what would constitute-adequate demonstration that an item has been completed as well as a procedure for modifying the list is contained in the enclosure.
Sincerely, ORIGINAL SIGNED BY Michael.T. Masnik, Senior Project Manager Non-Power Reactors and Decommissioning Project Directorai.e Division of Operating Reactor Support Office of Nuclear Reactor Regulation-
Enclosure:
As stata cc w/ enclosures:
See next page DISTRIBUTION:
Docket' File 50-320 BGrimes EHylton ACRS (10)
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Ga Esauq'o UNITED STATES aY [
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j WASHINGTON, D, C. 20555
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December 7, 1992 l
j Docket No. 50-320 i
Dr. Robert L. Long Director, Corporate Services /
Director, TMI-2
-1 GPU Nuclear Corporation
-l Post Office Box 480 Middletown, Pennsylvania 17057-0191
Dear Dr. Long:
SUBJECT:
PROPOSED LIST OF REMAINING THI-2 RELATED REQUIREMENTS OR COMMITMENTS FOR DISCUSSION AT THE DECEMBER 8, 1992 MEETING AT THE TMI SITE 3
The staff has completed a review of.the Post-Defueling Monitored Storage (PDMS) Safety Analysis Report-(SAR) as well as the NRC prepared Safety 1-Evaluation Report and the Technical Evaluation Report for PDMS.
Based on that review, the staff has identified specific requirements and commitments that 4
need to be implemented or satisfied by GPU Nuclear at Three Mile Island Nuclear Station Unit 2 (TMI-2) prior to entry into PDMS.
Staff identified requirements and commitments are listed in the enclosure.
The staff.
recognizes that many of the items listed in the enclosure have already been-completed, however, they are listed because the NRC staff has not verified the item's status.
This list will be the subject of the December 8, 1992 meeting between your staff and the NRC at the THI Training Center. We plan to briefly discuss each item with your staff, determining the status of completion or implementation, l
and discuss what would constitute adequate demonstration that the item had been resolved. Also, we would like to discuss a procedure for modifying the j
list. A staff proposal for what would constitute adequate demonstration that an item has been completed as well as a procedure for modifying the-list is c
contained-in the enclosure.
l Michael T. Masnik, Senior Project Manager l
Non-Power Reactors and Decommissioning Project Directorate Diviston of Operating Reactor Support Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enclosures:
See next page
?
T Dr. R. L. Long Three Mile Island Nuclear Stu ion GPU Nuclear Corporation Unit No. 2 Docket No. 50-320 cc:
Regional Administrator, Region I Mr. Robert Rogan U.S. Nuclear Regulatory Commission GPU Nuclear Corporation 475 Allendale Road P. O. Box 480 King a Prussia, Pennsylvania 19406 Middletown, Pennsylvania 17057 Dr. Judith H. Johnsrud Mr. David J. McGoff Environmental Coalition on Nuclear Office of LWR Safety and Technology Power NE-23 433 Orlando Avenue U.S. Department of Energy State College, Pennsylvania 16801 Washington, D.C.
20545 Ernest L. Blake, Jr., Esq.
Mr. Wythe Keever Shaw, Pittman, Potts, and Trowbridge The Patriot 2300 N Street, N.W.
812 Market Street Washington, D.C.
20037 Harrisburg, Pennsylvania 17105 Secretary Mr. Robert B. Borsum 4
U.S. Nuclear Regulatory Commission B & W Nuclear Technologies Washington, D.C.
20555 Suite 525 1700 Rockville Pike Mr. Russell Schaeffer, Chairperson Rockville, Maryland 20852 Dauphin County Board of Commissioners Dauphin County Courthouse Mr. Marvin I. Lewis Front and Market Streets 7801 Roosevelt Blvd. #62 Harrisburg, Pennsylvania 17120 Philadelphia, Pennsylvania 19152 William Dornsife, Acting Director Mr. Jane Lee l
Bureau of Radiation Protection 183 Valley Road l
Department of Environmental Resources Etters, Pennsylvania 17319 P. O. Box 2063 i
Harrisburg, Pennsylvania 17120 Mr. Walter W. Cohen, Consumer l
Advocate l
Mr. Ad Crable Department of Justice l
Lancaster New Era Strawberry Square,14th Floor 8 West King Street Harrisburg, Pennsylvania 17127 l
Lancaster, Pennsylvania 17601 U.S. Environmental Prot. Agency Mr. Francis I. Young Region III Office Senior Resident Inspector (TMI-1)
ATTN:
EIS Coordinator U.S. Nuclear Regulatory Commission 841 Chestnut Street P. O. Box 311 Philadelphia, Pennsylvania 19107 Middletown, Pennsylvania 17057 Mr. Charles N. Kelber Mr. Frank F. Hooper Atomic Safety and Licensing 4155 Clark Road Board Panel Ann Arbor, Michigan 48104 U.S. Nuclear Regulatory Commission Washington, D.C.
20555 i
Peter B. Bloch, Chairman Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C.
20555 l
s ENCLOSURE-I.
Ef0VIREMENTS FOR ISSUANCE OF THE POL 1.
Before the staff can issue the POL the licensee must submit the final Post-Defueling Survey Report for the Reactor Vessel that provides both-an estimate of the quantity of remaining fuel and demnnstrates that the fuel will remain subcritical. The staff will review the licensee's submittal and conduct an independent assessment of the criticality potential for both the steady state and accident scenarios.
2.
The statement, in paragraph 2.A. of the proposed POL,
"...-and is described in the Post Defueling Monitored Storage Safety Analysis Report as supplemented and amended and the Environmental Report as supplemented and amended" needs to be revised. The identified documents describe the facility as it would be configured during PDMS and not the current Mode 3 condition.
3.
Paragraph 2.C.(1) of the POL refers to the Technical Specifications contained in Appendix A only. This refers to the Technical Specifications that would be in force after the licensee enters PDMS.
'The current Technical Specifications still have a part A'and part B.
l The proposed PDMS technical specifications has only an Appendix A.
Therefore the POL would have to be changed to reference both A and B.
II. RE0VIREMENTS FOR ISSUANCE OF THE PDMS TECHNICAL SPECIFICATIbHS 1.
Resolution of the amount of fuel remaining in the reactor vessel and the potential for recriticality.
2.
Development of a procedure for NRC staff authorization to enter PDMS.
The staff proposes that the PDMS Technical Specifications be issued at the time the POL is issued. The PDMS Technical Specifications would be in effect only after NRC staff authorization. The staff authorization would be granted once the licensee certifies that all requirements and commitments for PDMS (see III. below) have been satisfied.
i 3.
Development of a PDMS punchlist that. lists requirements and-commitments that were part of the PDMS SER_and TER review. This' list was initially developed by the NRC staff.
I 4.
Development and licensee agreement of'a standard of what constitutes completion and what is required for NRC verification of open items.
t During the open meeting to discuss each of the items in III. below the staff and licensee will agree upon what form of primary documentation is required for each item. This issue is further discussed in item Ill.L.
below.-
i l
I t
. ~
2
. 5.
Development of a procedure for resolving deviations from the TMI-2 punchlist. Once the list of remaining activities has been agreed upon by both the licensee and the NRC, then future changes to the list will have to be documanted, a safety evaluation performed by the licensee, and NRC staff r, iew and approval of the deviation or change.
This issue is discussed further in item III.M. below.
]
111.
RE0VIREMENTS FOR ENTRY INTO PDMS (PDMS TECHNICAL SPECIFICATIONS EECOME EFFECTIVE) 1.
The following are the conditions in'the Proposed PDMS POL, contained in the February 20, 1992 letter, that must be met prior to the entry into PDMS:
A.
License Condition 2. D. "Special Auxiliary and Fuel Handling Builfing Ventilation Study." The monitoring program [that is required prior to termirating continuous operation of the AFHB ventilation systems) shall include at least 1 year of data before entry into PDMS.
The licensee currently has collected two quarters of pre-PDMS data.
B.
License Condition 2. E. " Unfiltered Leak Rate Test." The licensee needs to develop [and submit] a[n approved] surveillance requirement for the reactor building unfiltered leak rate test (Section 4.1.1.2) to demonstrate compliance with limiting Condition for PDMS 3.1.1.2.
C.
License Condition 2. F. " Additional Submittals Prior to Post-Defueling i
Monitored Storage." According to the proposed POL the following documents need to be submitted and in some cases approved before the l
facility can enter PDMS:
a.
Site Flood Protection Plan.
Requires NRC review.
The licensee plans to submit the plan by the end of 1992.
b.
Site Radiation Protection Plan.
Requires NRC review.
The licensee plans to submit the plan by the end of 1992.
c.
Offsite Dose Calculation Manual (ODCM).
Requires NRC review and approval and a license amendment to TMI-2 license. On June 18, 1992, the staff received an acceptable ODCM from the licensee.
The staff is processing a license amendment for TMI-2 which should be completed by the end of 1992. The staff should again review the 00CM just before the licensee enters PDMS to verify that references in the ODCM to the Mode 3 technical specifications have been removed and that information regarding the reactor building breather has been incorporated.
d.
Post-Defueling Monitored Storage Fire Protection Program Evaluation. The staff will review this document, which the licensee will likely submit just before entering PDMS.
a 3-e.
Radiological Environmental Monitoring Plan (REMP). Requires NRC review just before the start of PDMS. Currently the licensee has a THI site REMP with redundant requirements in the THI-2 Appendix 4
B technical specifications.
The staff will review the site REMP approximately 2 months before entering PDMS to verify that the programs discussed in the PDMS SER are included. -The rdtiological environmental monitoring requirements in the current Mode 3 THI-2 Append; 8 technical specifications are to be= deleted by a license amendment to be issued independently of.PDMS and prior to entry into PDMS.
These requirements will be placed in the Offsite Dose Calculation Manual.
f.
A revision to the PDMS SAR,-to in lude the results of the completed plant radiation and contamina: on surveys just before entering PDMS.
2.
Based on the licensee's Safety Analysis Report and the staff's Safety Eva's. tion and Technical Evaluation of February 20, 1992, the following additional requirements or licensee commitments must be met prior to entry into PDMS:
1 A.
Removal of Water from Reactor Coolant System and Fuel Transfer Canal I
1.
Remove water to the extent reasonably achievable.
Reactor Vessel; drained to less than 10 gallons (38 liters) of water. (SAR 6.2.27.2; TER 5-9) tor Building Fuel Transfer Canal. (TER 5-9) 2.
Iso 16 : the fuel transfer tubes. (SAR 1.1.2.1).
3.
Drill holes in canal seal plate to prevent refueling canal from filling.
(TER 5-9) 4.
Cover the Reactor Vessel to minimize water entry. (SAR 6.2.27.2) 5.
Drain the Submerged Demineralizer System to the extent reasonably achievable. (SAR 6.2.36.2) 6.
Dran and shield the "B" spent fuel pool to the extent reasonably achievable. (SAR 6.2.36.2) 1 8.
Drain and clean the "A" spent fuel pool to the extent reasonably achievable. (SAR Supp. 4, Item 1)
B.
Radiation Safety & Reduction-of Potential for Releases 1.
Ship offsite or package and stage for shipment remaining radioactive waste irom the major TMI-2 decontamination activities.
(SAR1.1.2.1; TER xiv) l
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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 reactor vessel drainuown to reduce dose rates. (TER 5-23) 4.
Define and establish an adequate surveillance program for PDMS environmental protection systems to ensure public health and safety.
4 (TER xiv)
C.
Ventilation 1.
Verify that a surveillance program exists to 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 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) 3.
Ensure that penetration R-626 has had all existing piping removed and a cover bolted over the penetration with a single pipe centered in the cover that has been blind f!:7ged for future use. (SAR Supp. 3, Item B.2; TER 6-17) 4.
Ensure that the reactor building breather 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.
Leak test the HEPA filter in breather prior to entry into PDMS.
(SAR l
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 procedure that requires an evaluation of the reactor building atmospheric conditions prior to personnel entry.
(SAR7.2.1.3) 8.
Develop and implement procedures for maintaining HEPA filter banks for the Reactor Building Purge System.(SAR 7.2.1.3) 9.
Develop and implement procedures for monitoring the Reactor Building vent during reactor building purge. (SAR 7.2.1.3)
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5-D.
Elant Contamination Survey 1.
Licensee will meet estaWshed contamination 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 THI-2 or ALARA considerations, the licensee will provide an evaluation of the j
specific situation to the NRC. (SAR 5.3.1 and Supp. 3, Itea A.11; TER i
- p. 4-2) 2.
Update information in the following tables from the SAR as final decontaminationresultsbecomeavailable.(SAR5.4.3) i'
- Table 5.3-2 (SAR) "PDMS Radiological Conditions - AFHB" l
i Table 5.3-4 " Surface Contamination - Reactor Building" l
-- Table 5.3-5 " Surface Contamination - AFHB"
- Table 5.3-6 " Surface Contamirretion - Other Buildings" i
3.
Perform survey of the service building, 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 l
PDMS in order to establish a radiological baseline for the facility.
Ensure that a program exists for periodic measurement of radiation and i
contamination levels to verify radiological conditions. (SAR 7.2.4.1 l
and 7.2.4.2; TER 6-42 and 6-43).
E.
physicai Maintenance in Reactor Buildina and Vessel i
1.
Have the capability of inserting a video 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.
Perform monthly entries into the reactor building for at least 6 months. (PDMS SAR 7.2.4; TER 5-23)
F.
Physical Maintenance in AFHB 1.
Perform monthly entries into the AFHB 'for at least 6 months. (SAR 7.2.4; TER 5-23) 2.
Ensure that both fuel pool structures remain intact (SAR 7.1.3.2)
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Physical Maintenance in other Buildinas 1.
Ensure that the Control Room Ventilation Systems (i.e., Control Room HVAC and Cabl" S om HVAC) and the Service Building Ventilation System are mainta w 4 <n operational condition and will be operated as required. (T
,2.6.8,9,10) 2.
Maintain the capability to process potentially contaminated liquids.
H.
Electrical Related 1.
In reactor containment, reactor building 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 480/277-voltage alternating current power to lighting, fire dd ectors, and sump level indication circuits will be energized and will remain operational.
The auxiliary sump, j
auxiliary sump tank and associated level indication will also remain i
operational.. Selected loads (i.e., welding receptacles, heaters, pump motors, and fan motors) will remain energized and available for use, as needed. (SAR 7.1.2.2; TER 6-37) 3.
In the fuel-handling building, low voltage circuits (120/208 VAC) to lighting and fire detection will be energized. (SAR 7.1.3.2; TER 6-37) 4.
In the Control and Service Buildings, verify that the electronic l
distribution will remain configured to power low voltage (120/208 VAC) lighting loads and fire detectors. (SAR 7.1.7.2) 5.
Portions of the TMI-2 auxiliary electrical distribution system will be operational and energized to 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) l 7.
Verify that exit signs are powered from the normal lighting system and from a locally mounted battery during emergency conditions. (SAR l
7.2.5.2.5) j 8.
DC power during PDMS will be supplied through a group of four static rectifiers to the 2-Idc and 2-2dc buses.
Loads have been consolidated where practicable, using bus tie-breakers to reduce the number of energized circuits. (SAR 7.2.5.1.3; TER 6-38)
. 9.
Verify that direct current backup power supplies are provided to the support radiation monitoring during a temporary loss of power. (SAR 7.2.5.1.3; TER 6-38) 1.
Fire Protection 1.
Have procedures in place to ensure that the fire mains within the reactor building 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 7.2.2.2,2k.; TER 6-2) 2.
Ensure that automatic fire. suppression f a provided to areas of the facility and systems which contain signtficant amounts of combustibles and possible ignition sources (i.e., auxiliary transformers). (SAR 7.2.2.1) 3.
Ensure that either the TMI-2 control-room is manned or that remote monitoring capabilities are available in TMl-1 control room to identify the specific zone in which a fire in the THI-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.
Ensure maintenance of deluge systems in turbine building for auxiliary transformers and east turbine building wall.
5.
Demonstrate that THI-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) 6.
Deactivate deluge systems in the auxiliary building and the control building. (SAR 7.2.2.3; TER 6-29) 7.
Ensure that the Halon systems protecting the Air Intake Tunnel have been deactivated by removing the Halon cylinders and de-energizing the ultraviolet and pressure detectors. Verify that the Halon system protecting the relay room has been deactivated by disconnecting the cy1_inders and either emptying or removing them. (SAR 7.2.2.2d) 8.
Ver_ify 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.)
9.
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.)
10.
Ensure that the fire detection system remains operational in the Air Intake Tunnel and the relay room. (SAR 7.2.2.2d.)
. 11.
Ensure that freeze protection has been added to applicable portions of the fire main. (SAR 7.2.2.2j.; TER 6-31) 12.
Ensure that the yard fire main is kept pressurized using the station fire pumps in THI-l and the altitude tanks as a backup pressure sources. (SAR 7.2.2.2a.; TER 6-31) 13.
Ensure isolation of the 12-inch fire service loop, which runs through the diesel generator building, the AFHB, the control building area and the turbine building (east and west). (SAR 7.2.2.2k.; TER 6-32) 14.
Ensure that the fire system line is cut and blanked off at the fuel-handling building, where the fire system line runs from the diesel generator building. (SAR 7.2.2.2k.; TER 6-32)
- 15. Deactivate river water and fire pump houses.
Use facility to provide a passive pathway for intake water to diesel fire pump FS-P-1, which will be used only as an emergency backup water-supply source. Ensure that maintenance and operability requirements for diesel fire pump FS-P-1 has been turned over to THI-1. (SAR 6.1.10 and Supp.1, Item 14; TER 6-33)
- 16. Have heat available (heat trace, or building HVAC system) for diesel fire pump FS-P-1, or maintain the pump in layup. (SAR Supp. 1, item 14; TER 6-33) 17.
Ensure that transient combustibles have been removed from inside the containment and the AFHB to the extent practicable. (SAR 7.2.2.29.;
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 BTV/ square foot. (SAR Supp.1, item 17)
- 18. Drain oil to the extent reasonably achievable from the main turbine, main feedwater pumps, emergency feedwater pumps, steam generator feedwater pumps, condensate booster pump reservoirs and hydrogen seal oil unit. (SAR 7.2.2.2h.; TER 6-34) 19.
Taken as an aggregate, ensure that no more than 57 percent of the original total volume of reactor ccolant 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)
- 20. Charcoal filters have been removed from all HVAC systems in TMI-2.
- 21. 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) 22.
Procedure in place for reactivation of the deactivated portions of the fire protection system if necessary. (SAR 7.2.2.21.; TER 6-29)
. 23. Verify that the procedure for inspection of the fire loop drain valves during freezing weather is in place. (SAR 7.2.2.2k.;
TER 6-32)
- 24. Verify that the procedures and system are in place for testing of the operable portion of the fire detection and alarm system. (SAR 7.2.2.2b ; TER 6-34)
- 25. Verify that procedures for manual suppression of fire by the fire brigade are provided as stated in the FPPE. (TER 6-35)
J.
Flood Protection l.
Ensure that flood aanels are provided for all entrances to the control building, and to tie 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) 2.
Verify that the containment basement and auxiliary building sumps level indications will be maintained.
(SAR 7.2.3.1.2) 3.
Verify that the auxiliary building sump pumps are maintained operational and placed in a manual control mode. (SAR 7.2.3.1.2) 4.
Verify that the Miscellaneous Waste Holdup Tank and the Auxiliary Building Sump Tank (ABST) have been isolated from the Radwaste Disposal Gas System and vented to the auxiliary building atmosphere by disconnecting and opening either the vent header connection, relief valve, rupture disc, or other penetration, and that cartridge-type HEPA filters have been installed on the openings to protect against airborne releases from these tanks. (SAR 7.2.2.3.1.2) 5.
Ensure that a flow path exists to drain down the reactor building basement floor. (SAR 7.2.3.1.2) 6.
Verify that freeze protection has been provided for portions of the Waste Disposal Liquid (WDL) system that are determined to be subject to freezing due to deactivation of building ventilation systems. (SAR 7.2.3.1.2) 7.
Verify that alternate provisions have been provided for operating the air-operated valves required for the WDL system during PDMS (SAR 7.2.3.1.2) 8.
Ensure that the sumps have a high level alarm that annunciates in the control room and the PDMS Alarm Monitoring System. (SAR 7.2.3.2.2) l
r 10 -
K.
Procedures and Proarams 1.
Include a surveillance program under which 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.
STANDARDS FOR SATISFYING RE0VIREMENTS AND COMMITMENTS The staff recognizes that many of the above requirements and commitments have been acted upon by the licensee. Once this list is finalized the licensee will submit a letter that documents which of the listed requirements and commitments have been satisfied. The letter will reference primary documentation (VWis, procedure numbers, drawings etc.) that demor. strate that the work was completed or the requirement or commitment met.
It will not be necessary to submit the primary reference documents but only have them accessible at the TMI-2 site.
The staff will verify by reviewing the primary documentation and/or inspection of the actual modification.
Once the so 'f has conducted its review and determined that the requirement or commitment has been satisfied the staff will close out the item. As other items are completed the licensee will continue to notify the staff in writing of the completed status and identify the appropriate primary references. The staff and licensee plan to agree prior to notification of completion of an item what constitutes the standard for demonstrating completion of the item.
M.
PROCEDURES FOR CHANGING THE AB0VE REQUIREMENTS AND PROCEDVRES During the remainder of the current cleanup effort conditions may chat.ge resulting in a change in the licensee's ability to satisfy the above requirements and commitments.
Licensee's request for deviations to the above list of requirements and conditions must be made in writing, as an amendment to the 3AR, providing a description of the old requirement or commitment and a description of the change. The deviation request must include a safety analysis evaluating the proposed change.
Requests for deviations to the above list must be timely and allow for staff review (typically 60 days). The NRC staff will either approve or disapprove the licensee's request in writing based on the results of the staff review. The licensee understands that PDMS was evaluated and received staff approval based on the requirements and commitments made by the licensee through SAR Amendment 15.
Significant changes to the requirements and commitments may invalidate, or require a reevaluation of the staff's Safety Evaluation and Technical Evaluation Report.
_ _ - - - -