ML20210R479

Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2

ML20210R479
Person / Time
Site:	Three Mile Island
Issue date:	08/13/1999
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20210R474	List: ML20210R469 ML20210R479
References
NUDOCS 9908170129
Download: ML20210R479 (53)

Text

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August 13,1999 UNIT 2 PDMS Safety Analysis Report lastruction Memorandum l

CORRECT ADDRESS IF NECESSARY RETURN TO: Debbie Mankbank, Procedure Distribution Control, South Office Building. TML Please apdate your Unit 2 PDMS SAR with the attachments as instructed below. Also, please sign the

- acknowledgement at the bottom of this enemo and arturn to Debble Marshbank at the address shown above.

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CONTINUED 9908170129 990811 PDR ADOCK 05000320 P

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- ADDITIONAL INSTRUCTIONS / COMMENTS:

Remove and replace names as noted in this memorandum. When complete please sinn and return to Debbie Marshbank.

(Signature)

( Ext. No.)

(Date)

A0l00482 7/94 f

PAGE2

f TABLE OF CONTENTS CIIAPTER TITLE t

1 INTRODUCTION AND GENERAL, DESCRIPTION OF PLANT 2

SITE CIIARACTERISTICS 3

DESIGN CRITERIA - STRUCTURES, SYSTEMS AND COMPONENTS 4

FUEL 5

PDMS RADIOLOGICAL CONDITIONS 6

DEACTIVATED SYSTEMS AND FACILITIES 7

OPERATIONAL SYSTEMS AND FACILITIES 8

ROUTINE AND UNANTICIPATED RELEASES 9

DELETED 10 ADMINISTRATIVE FUNCTIONS TC-1 UPDATE 3 - AUGUST 1999

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TABLE 1.4-1 GPUN DRAWINGS TITLE GPUN DWG. NO.

~

Site Plan 1E-120-01-001 Reactor Building Basement Floor 2060 Reactor Building Ground Floor 2061 Reactor Building Operating Floor 2062 Reactor Building Section A-A 2063 Reactor Building Sections 2064 B-B, C-C, D-D Auxiliary and Fuel Handling.

2065 Building, Basement and Sub-Basement Floor Auxiliary and Fuel Handling 2066 Building, Ground Floor Auxiliary and Fuel Handling 2067 Building, First Floor Auxiliary and Fuel Handling,

2068 Floor Building, Operating

- Auxiliary and Fuel Handling 2069 Building, Sections A-A and B-B

' Auxiliary and Fuel Handling 2070 Building, Section C-C Auxiliary and Fuel Handling 2071 Building, Section D-D Auxiliary and Fuel Handling 2072

. Building, Section E-E

, Control and Service Building, 2380 tower Floor Plans Control and Service Building, 2381 Upper Floor Plans Control and Service 2382 Building, Sections

~ River Water Pump House 2338 1.4-2 UPDATE 3 - AUGUST 1999

r TABLE 1.4-1 (Cont'd)

DRAWING REFERENCES -

TITLE GPUN DWG. NQ DELETED Turbine Building Basement Plan - East Side 2051

- Turbine Building Basement Plan - West Side 2052 Turbine Building Ground Floor Plan - East Side

'2053 Turbine Building Ground Floor Plan - West Side 2054 Turbine Building Operating Floor - East Side 2055 Turbine Building Operating Floor - West Side 2056 Turbine Building Section B B 2057 Turbine Building Sections A-A and C-C 2058 Turbine Building Sections'D-D and E-E 2059 9

P&lD SymbolIdentification 2001

{

- Electrical Symbol List 3001 Reactor Building Ventilation and Purge 302-2041 Fire Protection 302-231 l

Radwaste Disposal Miscellaneous Liquids 302-2045 Radwaste Pumps Seal Water 302-2492 Sump Pump Discharge and Miscellaneous Sumps 302-2496 l

Building Air Intake, Exhaust, and 302-2219 Radiation Monitoring 13.2 KV One Line Diagram 206201 480 Volt Unit Substation 206202 480 Volt Unit Substation 206203 480 Volt Unit Substation 206204 120V Regulated Vol' age System 3009 t

l 1.4 3 UPDATE 3 AUGUST 1999

r CHAPTER 2

~

SITE CHARACTERISTICS 2.1 GEOGRAPHY AND DEMOGRAPHY 2.1.1 SITE LO' CATION Three Mile Island is located approximately 2-1/2 miles south of Middletown, Pennsylvania at longitude 76* 43' 30" west and at latitude 40* 9' 15" north. The Unit 2 reactor vessel coordinates are N300, 324.40; E2,286,366.04, based on the Pennsylvania State coordinate system (UTM coordinates, Zone 18,4,446,020 meters north,353,070 meters east). It is one of the largest of a group of several islands in the Susquehanna River and is situated about 900 ft. from the east bank. It is elongated parallel to the flow of the river, with its 11,000 ft. in length and 1700 ft. in width. TMI-2 is located in the northern one-third of the island.

' He southessterly-flowing Susquehanna River makes a sharp change in direction, to nearly due south, in the vicinity of Middletown. After this directional change just north of Three f 4ile Island, the channel widens to approximately 1.5 miles.

The Three Mile Island Nuclear Station, Unit 2 is located adjacent to Unit 1 in Londonderry Township of Dauphin County, Pennsylvania, about 2-1/2 miles north of the southern tip of Dauphin County, where

. Dauphin is coterminal with York and Lancaster counties. Its location with respect to regional topographic and cultural features is shown on Figure 2.1-1 and with respect to local features on Figure 2.1-2. He station is located on Three Mile Island situated in the Susquehanna River upstream from York Haven Dam.

2.1.2 SITE DESCRIPTION

- Figure 2.1-3 shows the site marked to indicate the area owned or controlled by Met Ed. The site consists of 814 acres owned by Met-Ed. Met-Ed owns all of Three Mile Island and al.1 but a small portion on the southern end of Shelley Island. The exclusion area includes portions of Three Mile

' Island, the river surface around it, and a Met-Ed owned portion of Shelley Island, as shown on Figure 2.1-3.

2.1.3.

POPULATION AND POPULATION DISTRIBlJflON De population and population demographics are given in Section 2.2 of the TMI Unit i UFSAR. This

. information is updated as appropriate with the Unit 1 UFSAR updates.

1 2.1-1 UPDATE 3 - AUGUST 1999

m Fuel Handling Building - There are no extemal openings in this building requiring flood protection. He a.

Unit I railroad door, which serves as access to this building, is made watertight. (See the Unit 1 UFSAR, Section 2.6.5.)

b.

Control Building - Flood panels are provided for all ground level entrances.

c.

Auxiliary Building - A flood panel is provided for the ground level entrance.

d.

Control Building Area - Access to the tendon gallery is protected by watertight enclosures and flood panels at ground level.

1 Air Intake - Located at an elevation above PMF level and a watertight hatch.

e.

f.

General - Ground level doors and entrances to the Concrete Power Block Buildings are either water tight or are provided with flood panels. All openings that are potential leaks (e.g., ducts, pipes, conduits, cable trays) are configured to minimize water intrusion.

Unit flood protection will be achieved by instituting operational procedures and actions predicated upon continuous monitoring of upstream river stages and precipitation reports through the River Forecast Center at State College. Operational procedures to establish FLOOD ALERT and EMERGENCY CLOSURE actions are outlined in Section 2.4.6. Reference Section 7.1.4, Flood Protection.

Designs and criteria were established for the structures associated with flood protection facilities including earth dikes, channels, and pressure conduits. The criteria are conservative and based on sound civil engineering practices. The facilities were constructed and will be maintained and inspected consistent with their design as integral parts of a nuclear station. The design of the facilities has been reviewed and approved by the appropriate State and Federal agencies, including the Federal Power Commission, the Corps of Engineers, and the Water and Power Resources Board of the Commonwealth of Pennsylvania, where applicable.

2.4.4 ENVIRONMENTAL ACCEPTANCE OF EFFLUENTS Liquid effluents from TMI-l and TMI-2 enter the middle channel of the Susquehanna River through the station discharge pipe located approximately 640 ft. downstream from the intake structures, as shown in Figure 2.4 2.

Processed liquid waste will be discharged on a batch basis. Prior to release, each batch will be sampled and analyzed to determine its radioactivity content. Based upon the activity analysis, the wastes will either be released under controlled conditions or recycled for further processing. The flowrate of waste discharge will be a function of the activity analysis and the flowrate of the discharge from the Unit I mechanical draft cooling towers. The ability of the Susquehanna River to disperse and dilute the station discharge stream is dependent upon the magnitude of river water flow, 2.4-2 UPDATE 3 - AUGUST 1999

S 3.1.1.4a 10 CFR 50.5 - Deliberate Misconduct

~ Article 50.5 prohibits deliberate misconduct as defined in this anicle by Licensees, applicants for a

- license, contractors, sub-contractors, and the'r respective employees and provides for appropriate enforcement action. No exceptions are taken to the provisions of this article.

3.1.1.5

.10 CFR 50.7 - Employee Protection i Anicle 50.7 describes provisions relating to the protection of employees at nuclear facilities. No exceptions are taken to the provisions of this article.

3.1.1.6

.10 CFR 50.8 -Information Collection Requirements: OMB Approval Article 50.8 states that the OMB has approved NRC information requirements. No exceptions are

' taken to the provisions of this anicle.

~

3.1.1.6a. "10CFR50.9 - Completeness and Accuracy ofInformation" Article 50.9 provides requirements for licensees to maintain and to provide the NRC complete and accurate information. No exceptions are taken to the provisions of this article, i

. 3.1.1.7 ; 10 CFR 50.10 - License Required Article 50.10 describes the requirements and restrictions of a license obtained pursuant to 10 CFR Part

50. No exceptions are taken to the provisions of this anicle.

3.1.1.8 10 CFR 50.11 - Exceptions and Exemptions from Licensing Requirements Article 50.11 describes certain agencies of the Federal Government not required to obtain a license pursuant to 10 CFR 50. No exceptions are taken to the provisions of this article.

3.1.1.9 -

10 CFR 50.12 - Specific Exemptions Paragraph 50.12 allows the Commission to grant exemptions from the requirements of regulations. No exceptions' are taken to the provisions of this article.

3.1.1.10 - 10 CFR 50.13 - Attacks and Destructive Acts by Enemies of the United States; and Defense Activities Article 50.13 exempts Licensees from having to provide design featu'res to protect a facility from sabotage and other destructive acts. No exceptions are taken to the provisions of this article.

3.1.1.11 10 CFR 50.20 -Two Classes of Licenses

' Article 50.20 provides for two classes oflicenses; class 103 and 104. TMI-2 currently possesses a class 103 license.~

3.1-2 UPDATE 3 - AUGUST 1999

50.36a(a)

Paragraph 50.36a(a) establishes requircments for emuents for operating reactors. Although TMI-2 is not an operating reactor and the requirements of this paragraph cannot be complied with as written, the emuents during PDMS will be controlled and limited to very low values.

Theintent of the provisions of this paragraph is addressed by providing emuent limits and the description of how these limits will be met in Chapters 7 and 8.

50.36afa)(1)

Paragraph 50.36a(a)(1) requires that procedures be developed for the control of emuents and that equipment installed in radioactive waste systems pursuant to 50.34(a) be maintained and used. Procedures in use will be in place for the control of emuents during PDMS. The TMI-2 equipment that will be used to process radioactive wastes during PDMS will be maintained and is described in Section 7.2.3.

50.36a(a)(2)

Paragraph 50.36a(a)(2) requires that each licensee submit annual reports on emuents and prepare estimated public dose from those effluents. These requiremuits are applicable to TMI-2 during PDMS.

50.36a(h)

Paragraph 50.36a(b) establishes guidelines for limiting radioactive emuents and references 10 CFR 20.106 and 10 CFR 50 Appendix I as applicable in limiting emuents. These requirements are applicable to TMl-2 during PDMS.

3.1.1.25 10 CFR 50.36b - Environmental Conditions Article 50.36b establishes that the NRC may specify conditions as part of the license to protect the environment. No exceptions are taken to the provisions of this article.

3.1.1.26 10 CFR 50.37 - Agreement Limiting Access to Restricted Data Article 50.37 establishes requirements for access to Restricted Data and classified National Security Information. No exceptions are taken to the provisions of this article.

3.1.1.27.10 CFR 50.38 - Incligibility of Certain Applicants Article 50.38 establishes that certain persons are not eligible to apply for or obtain a license. No exceptions are taken to the provisions of this article.

j l

3.1-10 UPDATE 3 - AUGUST 1999 i

l

3.1.1.39 10 CFR 50.50 - Issuance of Licenses and Construction Permits

- Article 50.50 states 'that the Commission will' issue a license or construction permit with such conditions and limitations as it deems appropriate. No exceptions are taken to the provisions of this article.

3.1.1.40 10 CFR 50.51 - Continuation of License.

Article 50.51 establishes the duration oflicenses issued by the Commission. No exceptions are taken to the provisions of this article.

3.1.1.41 10 CFR 50.52 - Combining Licenses Article 50.52 establishes that the Commission may combine licensed activities in a single license. No exceptions are taken to the provisions of this article.

3.1.1.42 10 CFR 50.53 - Jurisdictional Limitations Article 50 53 establishes jurisdictional limitations on licenses No exceptions are taken to the provisions of this article.

3.1.1.43.10 CFR 50.54 - Conditions of Licenses i

Article 50.54 establishes a series of conditions applicabir e s aders of a license. Due to the non-operating and defueled status of TM1-2 during PDMS, many of these requirements do not apply.

The applicability of each paragraph of Article 50.54 has been addressed in the following review.

50.54(a)

Paragraph 50.54(a) requires that each nuclear power plant or fuel reprocessing plant licensee subject to the criteria of 10 CFR Part 50 Appendix B implement a quality assurance program pursuant to paragraph 50.34(b)(6)(ii). Appendix B establishes quality assurance

- requirements for the safety-related functions of those structures, systems and components that prevent or mitigate the consequences of postulated accidents that could cause undue risk to the health and safety of the public. During PDMS, TMI-2 will not have any structures, systems or components classified as safety-related and, therefore, 9

3.1-13 UPDATE 3 - AUGUST 1999

(.

3.1.1.51 10 CFR 50.61 Fracture toughness requirements for protection against pressurized thermal shock events.

' Article 50.61 specifically exempts plants that have permanently ceased operations from the requirements for protection against pressurized thermal shock in pressurized water nuclear power reactors. This exemption applies to TMI-2 during PDMS. Thus, no exceptions to the provisions of this anicle are necessary.

3.1.1.52 10 CFR 50.62 - Requirements for reduction of risk from anticipated transients without scram (ATWS) events for light-water-cooled nuclear power reactors.

Article 50.62 specifically exempts plants that have permanently ceased operations from the requirements to have equipment to address ATWS events. This exemption applies to TMI-2 during PDMS. Thus, no exceptions to the provisions of this article are necessary.

3.1.1.53 10 CFR 50.63 - Loss of alternating current power.

Article 50.63 requires that each light-water-cooled nuclear power plant licensed to operate be able to withstand and recover from a station blackout event. Since this application eliminates the legal authority to operate the TMI-2 facility from the license. a subsequent license application would be necessary to resume operation.

Therefore, during PDMS the requirements of this article are not applicable to TMI-2.

3.1.1.54 10 CFR 50.64 - Limitations on the use of highly enriched uranium (HEU) in domestic non-power reactors.

Article 50.64 establishes requirements for the issuance oflicenses to use highly enriched uranium fuel in non-power reactors. No exceptions are taken to the provisions of this article.

3.1.1.54a 10CFR50.65 - Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants" Article 50.65 specifically exempts plants that have permanently ceased operations from the requirement that each holder of a license to operate and monitor the performance or conditions of structures, systems and components against licensed established goals with the exception of structures, systems and components associated with storage, control, and maintenance of spent fuel in a safe condition. TMI 2's fuel has been shipped off site; thus the requirements of this article do not apply to TMI 2.

3.1.1.54b 10 CFR 50.66 - Requirements for Thermal Anncaling of the Reactor Pressure Vessel Article 50.66 provides a consistent set of requirements for the use of thermal annealing to mitigate the efTects of neutron irradiation. Due to the defueled non-operating status of TMI-2 in PDMS. the TM12 ' Reactor Vessel

- will not be thermally anncated. Thus the requhements of this article do not apply.

3.1.1.54e 10CFR 50.68 - Criticality accident requirements Article 50.68 provides an alternative method that licensees can use to meet the requirements or 10 CFR 70.24. The NRC granted TM!-2 an exemption to 10 CFR 70.24 (Reference 3.1 14). This exemption applies to TMI-2 during PDMS, thus, no exceptions to the provision of this article are necessary.

- 3.1.1.55 10 CFR 50.70 Inspections.

Article 50.70 establishes requirements to permit NRC inspectors to maintain activities at each nuclear power plant site. During PDMS, TMI 2 will be required to support NRC inspection activities to the extent determined necessary by the NRC. No exceptions are taken to the provisions of this anicle.

3.1 20 UPDATE 3 - AUGUST 1999

r, 3.1.1.59 10 CFR 50.75 - Reporting and recordkeeping for decommissioning planning.

Article 50.75 establishes requirements for providing reasonable assurance to the NRC that funds will be available for decommissioning and periodically reporting the status of these funds to the NRC.. No exceptions aretaken to the provisions of this article. Additionally, Reference 3.1-6 provided the decommissioning funding plan for TMI-2 required by 50.75(b) and Reference 3.1-15 provided the initial decommissioning fund status required by 50.75 (f) (1).

3.1.1.60 10 CFR 50.78 -Installation Information and Verification Article 50.78 requires that, "Each holder of a construction permit shall, if requested by the Commission, submit installation information on Form N-71, permit verification thereof by the International Atomic Energy Agency, and take such other action as may be necessary to implement the US/IAEA Safeguards Agreement, in the manner set forth in Articles 75.6 and 75.11 through 75.14 of this chapter." No exceptions are taken to the provisions of this article.

3.1.1.61 10 CFR 50.80 - Transfer of Licenses Article 50.80 specifies requirements for transferring a license from one entity to another. No exceptions are taken to the provisions of this article.

3.1.1.62 10 CFR 50.81 - Creditor Regulations Article 50.81 defines the rights and restrictions applying to any creditor relative to any license issued by the Commission. No exceptions are taken to the provisions of this article.

3.1.1.63 10 CFR 50.82 -Termmation of Licenses Article 50.82 defines the requirements for termmating a license. No exceptions are taken to the provisions of this article.

3.1.1.64 10 CFR 50.90 - Application for Amendment of License or Construction Permit Article 50.90 establishes that a holder of a license must file an application for an amendment. describing the changes desired, if the license holder wishes to amend the license. No exceptions are taken to the provisions of this article.

3.1.1.65 10 CFR 50.91 - Notice for Public Comment; State Consultation Article 50.91 establishes requirements applying to the Commission and TMI-2 regarding the application for an amendment to a 10 CFR Part 50 license following permanent removal of the fuel. The requirements of this article apply to TMI-2.

'3.1.1.66 10 CFR 50.92 -Issuance of Amendment Anicle 50.92 establishes the standards by which the Commission determines if no significant hazards exist for a license amendment. The licensee must file a no significant hazards analysis with each amendment application using the standards set forth in Article 50.92 as required by Article 50.H Ihe requirements of this article apply to TMI-2.

3.1-22 UPDATE 3-AUGUST Iw9

REFERENCES 3.1 1 Letter, Travers, W. D. (NRC) to Standerfer, F. R. (GPUNC), " Approval of Exemption from 10 CFR 50.61," dated December 30,1985.

3.1-2 Letter, Snyder, B. J. (NRC) to Kanga, B. K. (GPUNC), "10 CFR 50.49, ' Environmental Qualification of Electrical Equipment important to Safety for Nuclear Power Plants'," dated July 22,1983.

3.1-3 Letter, Stolz, J. F. (NRC) to Standerfer, F. R. (GPUNC),." Issuance of Amendment (TAC No.

65337)," dated May 27,1988.

1 3.1-4 Letter, Snyder, B. J. (NRC) to Hovey, G. K. (Met-Ed), Re: Exemption from 10 CFR 50 Appendix J, dated September 2,1981.

3.1-5 Letter, Snyder, B. J. (NRC) to Hovey, G. K. (Met-Ed), Re: Relief from the Inservice inspection Program Requirements of 10 CFR 50.55a, dated April 27,1981.

3.1-6 GPU Nuclear letter,4410-90-L-0044, " Decommissioning Financial Assurance Certification Report for... TMI-2," dated July 26,1990.

3.1-7 GPU Nuclear letter,4410 90-L-0012, "Defueling Completion Report, Final Submittal," dated February 22,1990.

3.1-8 GPU Nuclear letter, C312-91-2045, "SNM Accountability," transmitting the Auxiliary and Fuel Handling Buildings PDSR, dated June 7,1991.

3.1-9 GPU Nuclear letter, C312-91-2052, "SNM Accountability," transmitting the Reactor Building Miscellaneous Components PDSR, dated June 18.1991.

3.1-10 GPU Nuclear letter, C312-91-2055, "SNM Accountability," transmitting the Reactor Coolant System PDSR, dated July 3,1991.

3.1-11 GPU Nuclear letter, C312-91-2064, "SNM Accountability," transmitting the 'A' and 'B' Once-Through Steam Generators PDSR, Revision 1, dated July 3,1991.

j 3.1-12 GPU Nuclear letter, C312-93-2004, "SNM Accountability, transmitting the Reactor Vessel PDSR, dated February 1,1993.

3.1-13 GPU Nuclear letter, C312-92-2080, "TMl-2 Reactor Vessel Criticality Safety Analysis, " dated December 18,1992.

3.1-14 Letter, Masnik, M. T. (NRC) to Standerfer, F. R. (GPUNC) "Three Mile Island Nuclear Station Unit 2 Approval of Exemptions from 10 CFR 70.24 ' Criticality Accident Requirements'," dated May 27,1988.

3.1-15 GPU Nuclear, letter, 1920-99-20112, " Decommissioning Funding Status," dated March 31,1999.

3.1-43 UPDATE 3 - AUGUST l'm

I CHAPTER 6 DEACTIVATED SYSTEMS AND FACILITIES

]

6.0 INTRODUCTION

This chapter describes those systems and facilities which have been deactivated for PDMS. There are two categories ofdeactivated systems and facilities: 1) deactivated systems and facilities with passive PDMS functions and 2) deactivated systems and facilities.

The first category consists of those systems or facilities which have been deactivated but provide the passive function (s) during PDMS of contamination control and/or containment isolation. No effort will be expended to maintain the design functional capability of these systems and facilities. However, the passive function (s) of the affected systems or facilities will be maintained throughout PDMS to provide reasonable assurance that TMI-2 can be maintained in the PDMS condition with no risk to the health and safety of the public. The passive function of containment isolation will be maintained as required in the PDMS technical specifications section 3.1.1.1, primary containment isolation. The passive function of contamination control will be maintained by adherence to the requirements of 1000-PLN-4010.01 (TMI Radiation Protection Plan) and 1000-PLN-7200.04 (PDMS Quality Assurance Plan).

The second category consists of those systems and facilities which are deactivated because they serve no active or passive function during PDMS. No maintenance is required and no attempts will be made to preserve or maintain these systems and facilities.

Tables 6.1-1,6.2-1, and 6.3-1 provide a listing of those facilities and systems which will'be deactivated during PDMS These tables also provide other relevant status information for the listed facilities and systems.

Equipment, components, and parts may be removed from systems and facilities designated as deactivated, and used for other purposes, provided their removal does not adversely affect the PDMS fimetion of the system (s) or facilities involved. This may include complete system dismant!cment, component removal for use elsewhere, and possible conversion of portions of systems for other uses.

Similarly, equipment, components, and parts may be removed from systems and facilities designated as deactivated with PDMS passive functions provided, the passive function is not compromised or provided, decontamination activitics have negated the need for the passive function of contamination control.

A detailed original design description of deactivated facilities and systems may be found in the TMI-2 FS AR and/or system operating description books.

6.0-1 UPDATE 3-AUGUST 1999

6.1 DEACTIVATED *'ACILITIES Table 6.1-1 provides a listing of deactivated facilities for TMI-2. Also listed are the status ofinternal contamination and relevant remarks regarding the final layup of the facility. The following sections address the facility description and the PDMS function of the facility.

6.1.1 DELETED 6.1.2 DELETED-6.1.3 CONTAINMENT AIR CONTROL ENVELOPE The CACE was installed during the cleanup period and provided space to mobilize equipment and materials needed to support the in-containment activities through defueling. Location of the CACE at

' the equipment hatch allows equipment and rnaterials to be moved into and out of the Containment Building with a minimum of difficulty through the equipment hatch airlock doors. The CACE sened as an aid in the control of the spread of contammation and airborne radioactivity during those times when the airlock doors were opened.

During PDMS, this facility serves no active function and as such is designated deactivated. Certain types of RB entries require the CACE to be in a closed condition; thus, the CACE sen>es a passive function.1

-6.1.4 CIRCULATING WATER PUMP HOUSE The Circulating Water Pump House contained the six circulating water pumps and their controls which provide, a flowpath from the circulating water fiume to the main condenser.

This facility has had its contents dismantled, the pump bay filled in and is being utilized by the site transportation department. Final Decommissioning release surveys were completed on the pump

. basin prior to Alling it with crushed stone. Since this constituted final release surveys, the area is posted with warning signs against the admittance of radioactive material into the building.

Reference 6.5-129.

6.1.5 CIRCULATING WATER CHLORINATOR HOUSE The Circulating Water Chlorinator House contained the chlorine evaporator, chlorinator and ejector and storage tanks in addition to the sulfuric acid storage tank. This facility supported the chemical treatmen' of the Circulating Water System. All equipment and hazardous materials (chlorine, sulfuric t

acid) have been removed.

During PDMS, this facility serves no active or passive function and as such is designated deactivated.

6.1-1 UPDATE 3

. AUGUST 1999

g 6.1.11 BWST PIPE CHASE The Borated Water Storage Tank (BWST) Pipe Chase is an underground tunnel extending from the BWST into the Auxiliary Building on the east side. It enclosed piping for the Decay Heat Removal and Building Spray Systems. During PDMS, this area serves the passive function of contamination control.

6.1.12 CONTROL BUILDING (M-20) AREA EAST The Control Building Area is the plant area below elevation 305' between the Turbine, Reactor, and Service Buildings.. The east portion is separated from the west by a barrier wall. This area provides

. access to the Tendon Access Gallery on the east side and the Control and Service Buildings from the 3

Turbine Building.

During PDMS, this area serves the passive functions of housing containment isolations and 4

contamination control. It also contains a portion of the cork seam monitoring system.

6.1.13

. CONTROL BUILDING (M-20) AREA WEST The Control Building Area west portion houses the turbine-driven Emergency Steam Generator Feed Pump. Main Steam isolations, Relief and Atmospheric Vent Valves, the Control Building Area Sump, and Unit Substations 2-34 and 2-44. This area also provides access to the Tendon Access Gallery on the west side.

During PDMS, this area serves the passive functions of housing containment isolations and contamination control. However, one sump pump and a portion of the cork seam monitoring system will remain operational.

6.1.14 DELETED

)

+

'6.1-3 UPDATE 3-AUGUST 1999

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6.2 - DEACTIVATED PASSIVE SYSTEMS His section describes those systems which have been deactivated but provide some passive function during PDMSJo effort will be expended to maintain the design function of these systems. The identified passive function or functions of the affected systems will be maintained through the PDMS configuration of the TMI 2 facility. Equipment, components, and parts may be removed from these systems provided the passive function is not compromised or provided decontamination and dismantlement activities have negated the need for the passive function. Removal may involve dismantlement,' scrap recovery or conversion of components or systems to other uses in support of dismantlement or in support of Unit I activities.

Table 6.2-1 provides a listing of deactivated passive systems for the TMI-2 facility. Also listed are the system code, status of containment isolation, whether the system has internal contamination, and

~ relevant remarks regarding the final layup of the system. Each of the following sections addresses the I

original design function of the system and its PDMS passive function or functions. Additional reference information is listed in Section 6.5.

i 6.2.1 MAIN AND REHEAT STEAM SYSTEM '

I 6.2.1.1 System Design De main steam pipmg was ongmally designed to deliver main steam from the steam generators to the high pressure turbine It was also designed to provide main steam to the steam generator feed pump turbines, emergency steam generator feed pump turbine, second stage reheaters of the moisture separator-reheaters, turbine bypass valves, and the turbine gland seal system.

1 The primary function of the Rcheat Steam Piping System was to deliver reheat steam from upstream of the high pressure turbine to the moisture separator-rcheaters to reheat the high pressure turbine exhaust steam It also provided reheat steam to the steam generator feed pump turbines.

- 6.2.1.2 PDMS Function

- This' Main and Reheat Steam System provides no active function during PDMS. The passive functions.

provided by this system during PDMS are Containment isolation and contamination control. The Containment isolation function is provided by maintaining valves MS-VINB, MS-V2A/B, MS-V4A/B, MS-VilNB, MS-V7A/B, MS-VI5A/B, MS-V50A/B, MS-V51 A/B, MS-V224, MS-V225, MS-V226, and MS-V227 in the closed position. Also MS-R 21 A/B, MS-R-22A/B, MS-R-23A/B, MS-R.

24A/B, MS-R-25A/B, MS-R 26A/B, MS-R-27A/B, MS-R-28A/B, MS-R 29A/B AND MS-R-

~ 30A/B are in the closed position.

' 6.2.2 PRIMARY NUCLEAR PLANT HYDROGEN SUPPLY SYSTEM 6.2.2.1 System Design

' He Nuclear Plant Hydrogen Supply System 'was designed to store nuclear grade hydrogen and supply it at a reduced pressure to the make-up tank in the Auxiliary Building. Hydrogen was used in the primary

- coolant to reduce the concentration of free oxygen.

t 6.2 - 1 UPDATE 3-AUGUST 1999 f '

1 6.2.12.2 PDMS Function This system provides no active function during PDMS. However, RB pressure monitoring is provided i

via BS-Vl46 and 149 for RB pressure indic.ation and a 0.5 psig Hi RB pressure alarm. A portion of

{

the R.B. spray system piping will be utilized as a flow path for R.B. sump drainirg if required. The passive functions provided by this system during PDMS are Containment isolation and contamination control. The Containment isolation function is provided by maintaining valves BS-V148, BS-V147, BS-VIA/B BS-V130A/B in the closed position.

6.2.13 NUCLEAR SAMPLING SYSTEM 6.2.13.1

System Design

The Nuclear Sampling System was designed to provide the capability to obtain representative liquid and gas samples from nuclear systems.

6.2.13.2 PDMS Function This system provides no active function during PDMS. The passive functions provided by this system during PDMS are Containment isolation and contamination control. The Containment isolation function is provided by maintaining valves CA V8, CA-V9, and CA-V10 in the closed position.

6.2.14 NUCLEAR PLANT AND RADWASTE NITROGEN SYSTEMS 6.2.14.1

System Design

The Nuclear Plant and Radwaste Nitrogen System was designed to store and supply nuclear grade nitrogen at various pressures to several systems in the Reactor and Auxiliary Buildings and storage tanks in the yard.

6.2.14.2 PDMS Function This system provides no active function during PDMS. The passive functions provided by this system during PDMS are Containment isolation and contamination control. The Containment isolation function is provided by maintaining valve NM-V52 in the closed position. All nitrogen bottles have been removed.

j l

)

6.2-7 UPDATE 3 - AUGUS I 1999 l

6.2.48 MAKEUP WATER TREATMENT AND CONDENSATE POLISHING SYSTEM 6.2.48.1

System Design

The makeup EEter treatment system processed Susquehanna River water and provided high purity demineralized water to the Demineialized Service Water System. It also supplied the condensate polishing system which reduced the !cvel of suspended and dissolved impurities in the condensate and feedwater systems to acceptable levels. This system is dismantled.

6.2.48.2 PDMS Function This system prondes no active ftmetion for PDMS. The passive function provided by this system is contamination contrel.

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6.2-19 UPDATE 3 - AUGUST 1999

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SYSTEM REFERENCES (Cont'd)

REFERENCE DOCUMENT NO.

DOCUMENT DESCRIPTION

~

6.5 Dwg. No. 2004 Auxiliary Steam System 6.5-25 Dwg. No. 2005 Feedwater and Condensate System 6.5-26 Dwg. Nol 2006 Make-Up Water Treatment and Condensate Polishing 6.5-27 Dwg. No. 2007 Demineralized Service Water System 6.5-28 Dwg. No. 2008 Feedwater Heater Vents, Reliefs and Misc. Drains System 6.5-29 Dwg. No. 2009 Feedwater Heater Drains System

'6.5-30 Dwg. No. 2010 Condenser Air Extraction System 6.5-31 Dwg. No. 2011 Turbine Lube Oil Purification and Transfer System 6.5-32 Dwg. No. 2012 Instrument and Senice Air System 6.5-33 Dwg. No. 2013 Domestic Water 6.5-34 Dwg. No. 2014 Service Air System 6.5-35 Dwg. No. 2015 Turbine Plant Sampling System -

Secondary Plant 6.5-36 Dwg. No. 2018 Secondary Services Closed Coo!ing Water 6.5-37 Dwg. No. 2021 Circ. Water & River Water Chemical Treatment 6.5-38 Dwg. No. 2023 Circulating and Secondary Senices River Water System 6.5-3 UPDATE 3-Al'Gt s r 1999

F-SYSTEM REFERENCES (Cont'd)

REFERENCE. DOCUMENT NO.

DOCUMENT DESCRIPTION 6.5-39 ~

Dwg. No. 2024 Reactor Coolant, Make-Up and Purification System 6.5-40 Dwg. No. 2025 Chemical Addition 6.5-41 Dwg. No. 2026 Spent Fuel Cooling and Decay Heat System 6.5-42 Dwg. No. 2027 Radwaste Disposal Reactor Coolant Liquid 6.5 43 Dwg. No. 2028 Radwaste Disposal Gas 6.5-44 Dwg. No. 2029 Intermediate Closed Cooling Water System 6.5-45 Dwg. No. 2030 Nuclear Senices Closed Cooling Water System 6.5-46 Dwg. No. 2031 Nuclear Sampling System 6.5-47 Dwg. No. 2033 Nuclear Services River Water System 6.5-48 Dwg. No. 2034 Reactor Building Emergency Spray and Core Flooding 6.5-49 D'wg. No. 2035 Decay Heat Closed Cooling Water System 6.5-50 Dwg. No. 2036 Nitrogen for Nuclear and Radwaste Systems 6.5 51 Dwg. No. 2037 Fire Protection System 6.5-52 Dwg. No. 2038 Diesel Fuel Emergency Diescl Generator 6.5-53 Dwg. No. 2039 Radwaste Disposal-Solid 6.5-4 UPDATE 3-At GL s r 1999

SYSTEM REFERENCES (Cont'd)

REFERENCE DOCUMENT DOCUMENT DESCRIPTION 6.5-95 ~~

Dwg. No. 3073 Diesel Generators Sheets 57,59, and 60 6.5-96 Dwg. No. 3091 Safety Features Actuation System Index 6.5-97 Dwg. No. 4148 Reactor Building Containment Wall Penetrations Schedule t

6.5-98 Dwg. No. 4479037 Steam Turbine Piping Steam Drain &

Gland Diagram 6.5 99 Dwg. No. 614F177-5 (B&R File No. 01-00-0504) Seal Oil Diagram - Turbine Generator 6.5-100 Dwg. No. 614Fl 77-6 Seal Oil System (B&R File No.1 -

0504) 6.5-101 Dwg. No. 721J843 (B&R File No. 01-00-0210)

E. H. Fluid STS & Lube Diagram 6.5-102 Bechtel Dwg.

Piping and Instrument No.15737-2-M74 DS01 Diagram - Dewatering System 6.5-103 TMI-l Dwg. No. C-302-052 Unit ! Auxiliary Steam System 6.5-104 TMI-l Dwg. No. C-302-05l Auxiliary Steam System of TMI Unit No.

I Auxiliary Boilers 6.5-105 TMI l Dwg. No. C-302-162 TMI-l Plant Filtered H2O to and from TMI #2 Plant 6.5-106 TMI-I Dwg. No. C-302-163 The 1,000,000 Gallon Demineralizrd Water Storage Tank 6.5-107 TMI-l Dwg. No. C-302-301 The Unit 1 Plant Generator Gas & Vents 6.5-8 UPDATE 3-AUGUST 1999

SYSTEM REFERENCES (Cont'd)

REFERENCE DOCUMENT DOCUMENT DESCRIPTION 6.5-108 ~

TMI-l Dwg. No. C-302-671 Unit 1 - Sampling; Liquid and Gas 6.5-109 TMI-l Dwg. No. C-302-692 Liquid Waste Disposal System for Unit 2 6.5-110 TMI-I Dwg. No. C-302-840 Unit 1 - Auxiliary Building Heating &

Ventilation 6.5-111 TMI-l Dwg. No. D-60372 Gland Seal & Ejector System 6.5-112 Dwg. No. E-032 Misc. Power Panel Schedules, SDS 6.5-113 Dwg. No, E-302-191 Unit No.1 OTSG Chemical Cleaning System 6.5-114 TMI-l Dwg. No. E-302-196 Unit No. I OTSG Chemical Cleaning System 6.5-115 TMI-l Dwg. No. E-302-231 Fire Service Water 6.5-116 Dwg. No. M006 Auxiliary Building Emergency Liquid Clean-Up 6.5-117 Dwg. No. M0ll Flow Diagram Condenser Air Extraction Filtration System 6.5-118 Dwg. No. M012 Alternate Condensate System 6.5-119 Dwg. No. M013 HVAC Chemical Cleaning and Health Physics Building 6.5-120 Dwg. No. M014 Fuel Pool Waste Storage System 6.5-121 Dwg. No M015 Auxiliary Building Emergency Liquid Clean Up System Sampling 6.5-122 Dwg. No. M016 Flow Diagram, Temporary Auxiliary &

Fuel Handling Building HVAC O

6.5-9 UPDATE 3-AUGUST 1999

SYSTEM REFERENCES (Cont'd)

REFERENCE DOCUMENT DOCUMENT DESCRIPTION

~

6.5-123 Dwg. No. M021 Long Term OTSG "B" Cooling 6.5-124 Dwg. No. M022 Standby Reactor Coolant System Pressure Control System 6.5-125 Dwg. No. M041

" Temporary" Nuclear Services Closed Cooling Water System 6.5-126 Dwg. No. M043 Mini Decay Heat Removal System 6.5-127 Dwg. No. M044 & M045 Temporary Nuclear Sampling System, SNS 6.5-128 Dwg. No. M208 Chemical Cleaning & Health Physics Building Fire Protection 6.5-129 GPUN REPORT Post Dismantlement Radiological No. 990-2548 and Environmental Survey of the Three Mile Island Unit 2 Circulating Water Pump flouse Pump Bay 6.5-10 UPDATE 3 - AUGUST 1999

)

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approximately six feet above the design flood at that location. The dikes along both sides of the island descend uniformly frortrelevation 310.0 ft. to elevation 305.0 ft., which is sufficient to protect the entire site for the j

design flood. A dike with a top elevation of 304.0 ft. cxtends across the southern end of the site.

l Structures are provid:d with complete protection at the exterior faces rather than attempting to protect individual equipmenc or systems. The waterstops between adjacent building walls and mats were designed to be capable of withstaading a maximum water head of 4511. which is in excess of the maximum head associated with the floal level. The exterior sliding doors and flood panels are provided with watertight seals.

Specific design features of these structures are:

I a.

Containment - There are no external openings in the Containment below the 305 ft. elevation.

b.

Fuel Handling Building - There are no external openings in the Unit 2 Fuel Handling Building that require flood protection. The railroad door in the Unit 1 portion of the Fuel Handling Building is designed to be watertight.

c.

Control Building - Flood panels are provided for all ground level exterior entrances.

d.

Auxiliary Building - A flood panel is provided for the cast roll-up door entrance.

e.

Control Building Area - Access to the tendon gallery is protected by watertight enclosures and flood panels at ground level.

f.

Air intake - The openings in the Air Intake Tunnel are located higher than the probable maximum flood level except for a water tight hatch located at ground level, southeast of the BWST.

g.

General - Doors and entrances (not flood protected) to the Concrete Power Block Buildings are either watertight or are provided with flood panels. All openings that are potential leak paths (e.g.,

ducts, pipes, conduits, cable trays) are configured to minimize water intrusion, 7.1.4.3 Evaluation In addition to specific building flood protection provisions, the entire site is protected by an early warning i

system provided by the Federal State River Forecast Center and a dike with a top elevation of 310.0 ft. The j

probable maximum flood is calculated to reach elevation 308.5 ft. on the west side and 30811. on the east side of the site. Therefore, systems and facilities required to support PDMS activities are protected from flooding.

7.1.5 AIR INTAKE TUNNEL 7.1.5.I PDMS Function During PDMS, the Air Intake Tunnel provides a pathway for screened air to the following operational plant ventilating systems:

a.

Reactor Building Ventilation b.

Auxiliary Building Ventilation c.

- Fuel Handling Building Ventilation 7.I 5 UPDATE 3 - AUGUST IPM e

n

. d.

He Halon systems' protecting the Air intake Tunnel have been deactivated by

~

removing the Halon cylinders and deenergizing the ultraviolet and pressure

' detectors. The Halon system protecting the relay room has been deactivated by

. removing the cylinders. The fire detection system will remain operational to monitor these areas.

Portable fire extinguishers and self-contained breathing apparatus are staged with c.

emergency response crew equipment. Additional portable fire extinguishers are located throughout the plant as needed to support work activities.

f.

Transient combustibles inside the Containment and the AFHB have been removed

' to the maximum extent practical.

g.

The oil has been drained from the main turbine and tube oil reservoir, feedwater pump turbines, emergency feedwater pump turbine, emergency feedwater pumps, condensate pumps, condensate booster pumps, and the hydrogen seal oil unit.

h.

The charcoal filters have been removed from all HVAC systems in Unit 2.

i.

The 12 in. fire service loop, which runs through the Diesel Generator Building, AFHB, Control Building area and Turbine Building (east and west), has been cut and capped off. The Diesel Generator Building has been turned over to TMI-1.

Fire Service Water System standpipes have been configured to the East and West side of the Turbine Building which permits connection of the local fire hydrants to the 331' elevation of the Turbine Deck by way of staged fire hoses. This will allow responsive action by the Station Fire Brigade and or local Fire Departments.

j.

DELETED k.

The station fire brigade is fully trained to assure that the personnel are familiar l

with system configurations, plant layout, and the procedures in Unit 2.

1.

The Fire Protection Program and housekeeping inspections and their frequency are addressed in plant procedures.

The air intake tumEl halon system was removed because the probability of an airplane crash in the vicinity 2

of the air intake tunnel was estimated to be less than 2E-7/ year and because of the presence of heat activated detectors.

7.2-9 UPDATE 3 - AUGUST 1999

7.2.5.2.3 Evaluation The majority of the existing lighting systems remains operational during PDMS. Sufficient lighting capability is provided for anticipated support activities. If further needs arise, temporary lighting will be added for specific PDMS activities.

7.2.5.3 Communications System 7.2.5.3.1 PDMS Function The TMI 2 Communications System during PDMS will provide normal communication channels throughout Unit I and Unit 2.

In addition, the Communications System will provide the capability to announce alarms and alert personnel to radiation and fire hazards.

7.2.53 2

System Description

Portions of the original system have been retained for PDMS as follows:

a.

Normal Patte - Party System This system is powered from a separate 120-volt, single-phase AC power bus. The system is compatible with TMI Unit I and was merged with the TMI Unit I system through a merge-isolate switching arrangement in the control room to provide normal communication channels throughout TM1 Units I and 2 (excluding Unit 2 RB) during PDMS.

The reactor building paging system is currently disabled. This was accomplished by disonnecting five cables and removing the handsets inside both air locks. The cables can be re-landed and the handsets reinstalled to allow the reactor building paging system to be returned to service.

The system consists of hanusets, amplifiers, loudspeakers, evacuation tone generator, isolating transformer, and the necessary special equipment to provide a paging channel and three party line channels.

b.

Radie.Antsnna.sys.tsm This system consists of antennas located at strategic points within the TMI-2 PDMS Buildings to ensure full coverage for radio communications. This system is the back up system for a loss of the nonnal page-party system.

c.

Commsrs.ial.Tskal.9ns Sis!sm This system's trunk lines are leased from the Bell Atlantic Company. The handsets and switching equipment are maintained by GPU Service Corporation personnel. This system provides links with all on site as well as oft-site locations.

7.2 20 UPDATE 3 - AUGUST 1999

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E CHAPTER 10 ADMINISTRATIVE FUNCTIONS TABLE OF CONTENTS SECTION TITLE PAGE

10.0 INTRODUCTION

10.0-1 10.1 QUALITY ASSURANCE PLAN 10.1-1 10.2 SECURITY PLAN 10.2-1 10.3 EMERGENCY PLAN 10.3-1 10.4 RADIATION PROTECTION PLAN 10.4-1 10.5 ORGANIZATION 10.5-1 10.5.1 CORPORATE ORGANIZATION 10.5-1 10.5.1.1 President.GPU Nuclear 10.5-1 10.5.1.2 TMI Division 10.5-1 10.5.1.3 Engineering Division 10.5-1 10.5.1.4 Deleted 10.5-1 10.5.1.5 Adnunistration and Finance Division 10,5-1 10.5.1.6 Other Functions 10.5-2 10.5.2 ONSITE ORGANIZATION 10.5-2 10.5.2.1 PDMS Manager 10.5-2 4

UPDATE 3-AUGUST 1999 s..m.

10.5 ORGANIZATION 10.5.1 CORPORATE ORGANIZATION The corporate organizational elements responsible for the PDMS phase of TMI-2 are shown on Figure 10.5-1. The specific responsibilities are discussed below. Additionally, the PDMS Technical Specifications prescribe specific requirements for staff qualifications, training, and the review and audit of TMI-2 activities.

10.5.1.1 President - GPU Nuclear

)

The President - GPU Nuclear has the overall responsibility for the management of TMI-2 during PDMS. This responsibility is administered through the management staff, including:

' Director, TMI Division

' Director, Engineering Division

• Director, Nuclear Services Division Director, Administration Sand Finance Division 10.5.1.2 TMl Division The TMI Division has responsibility for operating and maintaining TMI-l and maintaining TMI 2 in the PDMS condition. The Director, TMI Division is charged with assuring consistent implementation of policies and procedures at TMI-2.

10.5.1.3 Engineering Division The Engineering Division provides a centralized technical capability to support GPU Nuclear facilities and, when requested, will provide such support to maintain the PDMS condition. The division provides the general mechanical, civil, electrical and

' instrumentation, engineering mechanics, and chemistry / materials disciplines. Further, the division also provides technical support in the areas of nuclear fuel management, computer applications, human engineering, risk analyses, environmental qualification, 1

plant analysis, and decommissioning.

10.5.1.4 Deleted l

10.5-l UPDATE 3-AUGUST 1999

l l

10.5.1.5 J Financial and Planning Services Division i

The Financial and Planning Services Division provides corporate-wide support in the areas of Materials Management, Expense Analysis, Budget and Rate Case support and

~1 ong Range and Strategic Planning.

10.5.1.6 Human and Administrative Services Division

The Human and Administrative Services Division provides corporate wide support in the areas of Human Resources including Labor Relations, Information Resource Management, Nuclear Security and the GPU Nuclear Medical Program.

10.5.1.7 Other Functions In addition to the divisions listed above, the following five smaller independent functions report to the Office of the President:

Nuclear Safety Assessment - Quality Assurance, Audits, and Ombudsman, including the General Office Review Board (GORB)

Communications deleted Continuous improvement deleted 10.5.2 ONSITE ORGANIZATION The onsite or5anizational elements responsible for the PDMS phase ofTMI-2 are shown on Figure 10.5-2.

i 10.5.2.1:

PDMS Manager The PDMS Manager has the first-level management responsibility for maintaining the TMI-2 PDMS condition. The PDMS Manager is directly responsible for the operations and maintenance activities associated with the TMI-2 PDMS. Reporting to the PDMS Manager are the subordinate supervisors responsible for execution of the above-listed functions.

10.5-2 UPDATE 3 - AUGUST 1999

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UPDATE 3 August 1999

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