ML20245L049

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Forwards Response to WR Butler 881206 Request for Addl Info Re Proposed Combined Emergency Operations Facility.Facility to Be Located Adjacent to Existing Bldg & 20 Miles from Peach Bottom Plant.W/One Oversize Map
ML20245L049
Person / Time
Site: Peach Bottom, Limerick, 05000000
Issue date: 08/10/1989
From: Corbin McNeil
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-0696, RTR-NUREG-696 NUDOCS 8908210245
Download: ML20245L049 (70)
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-PHILADELPHIA ELECTRIC COMPANY.

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NUCLEAR GROUP HEADQUARTERS 955-65 CHESTERBROOK BLVD.

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WAYNE, PA 19087-5691 (115) 640-6600:

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'Cx CUTIVE VICE PRESIDENT NUCLEAR

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August 10,.1989 l

Docket Nos. 50-277, j

50-278

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50-352 0

50-353' License Nos. DPR-44 DPR-56 I

NPF-39 NPF-84

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-l U.S.

Nuclear Regulatory Commission

~ ATTN: Document' Control Desk Washington, DC 20555

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SUBJECT:

Limerick Generating Station, Units 1 and 2 Peach Bottom Atomic Power Station, Units 2 and 3 Response to Request for' Additional Information Concerning Proposed Combined Emergency Operations Facility REF:

Letter, W.

R. Butler (NRC) to G.

A. Hunger, I

Jr. (Philadelphia Electric _ Company) dated l

December 6, 1988, requesting additional j

p information regarding the' combined Emergency F

Operations Facility.

i

Dear Sirs:

i Attached-is the Philadelphia Electric Company (PECo) response to the NRC's request for additional information l

regarding our proposed combined Emergency Operations Facility l

L(EOF) for the Limerick Generating Station (LGS) and the Peach j

. Bottom Atomic Power Station (PBAPS).

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' l 8906210245 890810 i

PDR ADOCK 05000277 C __X _ _________________ PDC

U.S.

Nuclear Regulatory Commission Page 2 On September 30, 1988, we submitted a letter requesting NRC approval of a new combined EOF for both LGS and'PBAPS. This new facility would be located adjacent to the existing PECo lL, Coatesville Service Building, and would be greater than 20 miles from the PBAPS site. This request was submitted in accordance with the direction in NUREG-0696, "Funtional Criteria for Emergency Response Facilities," which states that prior NRC approval is required when locating an EOF greater than 20 miles from a plant site.

The NRC letter dated December 6, 1988 (reference),

requested that.we provide additional information in order for the NRC to make a determination on the acceptability of this proposed facility. Specifically, the December 6, 1988, NRC letter requested responses to 10 questions.

On February 10, 1989, a meeting was neld between representatives; of the NRC and PECo to discuss our proposed combined EOF, and to ensure that our response adequately addresses the request for additional information.

l This response restates each question transmitted by the December 6: 1988 NRC letter, our response, and various attachments which will provide the information necessary to L

address each of the NRC's questions. The attachments provide the following information.

o -

Response to Request for Additional Information o -

Internal Pictures of Existing LGS l

and PBAPS EOFs 1

o Map Helicopter Service Agreements o

o -

Proposed EOF Floor Plan o -

PBAPS Data Acquisition System Parameters o -

Existing PBAPS Telecommunications Network l

o -

Coatesville EOF Telecommunications Network o -

Letters of Concurrence from Governmental Agencies

4

)L U.S.

Nuclear. Regulatory Commission Page 3 i

j If you have questions, or require additional.information, please do not hesitate to contact us.

Very truly yours, M

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im Attachments cc:

W.

R.

Russell, Administrator, USNRC, Region I T. J.

Kenny, USNRC Senior Resident Inspector, LGS l

T.

P. Johnson, USNRC Senior Resident Inspector, PBAPS j

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r-ATTACHMENT 1

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION l

l ATTACHMENT 1 PHILADELPHIA ELECTRIC COMPANY RESPONSE TO REOUEST FOR ADDITIONAL INFORMATION REGARDING THE PROPOSED COMMON-EMERGENCY OPERATIONS FACILITY FOR THE LIMERICK GENERATING STATION AND PEACH BOTTOM ATOMIC POWER STATION l~

Backuround An Emergency Operations Facility (EOF) is a licensee controlled and operated facility. The EOF is intended to serve as the central location for coordinating 1) emergency resp 6nse activities between on-site and off-site groups, and 2) off-site radiological and environmental assessment activities. This facility provides a location for licensee senior management personnel to assume the overall emergency management responsibilities and coordinate protective action decision-making.

In addition, this facility provides space for Federal, State, and local. emergency management agencies to 1) interface with licensee personnel, 2) obtain on-site and off-site emergency information and data, and 3) coordinate efforts to protect the health and safety of the general public. To implement these emergency management responsibilities, the facility must be staffed by trained / qualified licensee, Federal, State, and local support agency personnel.in sufficient numbers to effectively manage and control these emergency response functions. The facility must have an assured. mechanism for obtaining essential station data and information needed by these individuals for their decision-making process.

The existing EOFs for the Peach Bottom Atomic Power Station (PBAPS) and Limerick Generating Station (LGS) are located in existing Philadelphia Electric Company-(PECo) buildings which have been modified, within the constraints of the building, to meet the requirements for an EOF. The PBAPS EOF is located in the decommissioned Unit 1 control building and is approximately 0.5 air miles from the center of the protected area of the plant site. The LGS EOF is located in the basement of the PECo Plymouth Service Building and is approximately 18 air mileo from the plant site. Internal pictures of these existing facilities are provided in Attachment 2. _ _ _ -

Introduction PECo proposes to construct a common EOF for the LGS and PBAPS adjacent to the existing PECO Coatesville Service Building.

The use of this location as an EOF requires prior NRC approval because the distance between the proposed EOF and the PBAPS Technical Support Center (TSC), located in the decommissioned Unit 1 control building, exceeds the maximum allowable distance of 20 miles-which is permitted between the TSC and EOF for the facility. This proposed EOF site will, however, be within 20

-miles of the Limerick TSC. This new facility will result in an enhancement of the PECo, NRC, State, and local support agency interface capabilities, command and control capability; emergency responso data availability and display capability, and ability for PECo, NRC, State, and local responders to carry out their emergency response roles and functions.

The improvements that would he realized by the combined EOF will result in an upgrade of the ability of emergency response organizations to respond to and manage an emergency at either station. This enhanced emergency response capability is achieved by incorporating the following elements.

(1)

Operations and logistics improvements made possible by designing the facility to meet the specific funccional needs of an EOF, and (2)

PECo Emergency Response Organization (ERO) improvements made possible as a result of the improved size and location of the proposed facility.

The following section, " Response to Request for Additional Information Issues," provides the information requested by the December 6, 1988 NRC letter.

Response to Reauest for Additional Information Issues l

NRC Item 1.

Provide the exact straight line distance, as well as direct driving distance between the Coatesville l

Service Building and the Peach Bottom Atomic Power l

Station.

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t Fesucnse The distances from PBAPS to the'Coatesville Service Building are specified below.-

Straight Line Distance e 30.7 miles Driving Distance = 50.3 miles L

NRC' Item' 2.

Provide the exact straight line distance as well as direct driving distance between the Coatesville

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Service Building and the Limerick Generating Station.

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Rescoppe The distances'from LGS to Coatesville Service Building are specified below.

Straight Line Distance = 19.8 miles Driving Distance = 31.4 miles NRC Item 3.

Provide the exact time required to drive a motor vehicle from the Coatesville Service Building to the Peach Bottom Atomic Power Station and from Coatesville to the Limerick Generating Station under normal,

-daylight, weather conditions while observing the posted speed limits.

-Response The information is as follows.

To/From Coatesvillg Vehicle Travel Time (minutes)

Peach Bottom 71 Limerick 42 NRC Item 4.

Indicate what modes of personnel transport will be used to travel between the nuclear plant sites and the l

Coatesville Service Building and the time required to make the transit using each mode. _-_ _--

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Resoortse

.The modes of perscnnel transport that will be used for

' travel between the sites and.the proposed EOF at Coatesville.are vehicle 'or. helicopter, with the primary mode being vehicle. The table below provides the transit times fcr traveling between Coatt:sville.and the sites via both modes of transportation.

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'To/From Coatesville Vehicle Helicopter Travel time (minutes)

Travel Time (minutes)

Peach Bottom 71 25 Limerick 42 20 PECo currently has agreements with Keystone Flight Services and Fleet Helicopter Service (Attachment 4), thereby assuring 24-hour availability of helicopter service. These agreements provide for approximately 30 minute response during normal business hours and 1-1/2 hour to 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> response after normal working hours and on weekends. A helipad will be constructed adjacent to the new Coatesville EOF for rapid transit between it and the plant sites and Chesterbrook.

NRC Item 5.

Provide a map, which is to scale, illustrating the locations of the Limerick Generating Station, the Coatsville Service Building, the Peach Bottom Power Station, the proposed PECo nuclear headquarters in Chesterbrook, the State and local government Emergency Operations Centers wthin this general area, and the highway network around and between these facilities.

Response provides a map.that shows the location of the proposed Coatesville facility in relation to LGS, PBAPS, PECo Nuclear Group headquarters in Chesterbrook, the NRC Region I office, and county Emergency Operations Centers (EOCs) for PBAPS and LGS. The only facility that is not indicated on the map is

.the State EOC for Pennsylvania, located in Harrisburg, which is

.approximately 70 miles from the proposed Coatesville EOF. This map also details the highway network in the area surrounding these facilities..

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-NRC Item 6.

Indicate the proposed date when the PECo nuclear headquarters will become operational.

1 Response.

PECo~ Nuclear Headquarters at Chesterbrook became operational'on June 15, 1989.

'NRC Item 7.

. Indicate what modes of personnel transport will be used to travel between the Coatesville Service Building and the. proposed PECo nuclear headquarters'and the tine required to make the transit. Compare this transit time with the time.necessary to reach the primary EOF at both the Limerick and Peach Bottom plant site using the same modes of transport.

Response

The modes of transport that will be used between the proposed EOF-at the Coatesville Service Building and the PECo Nuclear Group headquarters in Chesterbrook will be vehicle or helicopter, with the primary mode being vehicle. As a result of the relocation to Chesterbrook, a majority of thc Nuclear Group corporate-personnel are required to drive their personal vehicles or car pool to the Chesterbrook office, since public transportation servicing this area is limited. Also, company vehicles can be made available for use at-the Chesterbrook location. This will ensure adequate vehicular transportation for day-time EOF activation.

The new Coatesville EOF is adjacent to a major PECo service

. facility with the capability of providing vehicles and fuel on a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> basis as necessary.

PECo currently has agreements with Keystone Flight Services and Fleet Helicopter Service (Attachment 4), therel y assuring 24-hour availability of helicopter service. These agreements provide for approximately 30 minute response during normal business hours and 1-1/2 hour to 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> response after normal working hours and on weekends. A helipad will be constructed adjacent to the new Coatesville EOF for rapid transit between it and the plant sites and Chesterbrook. - - -

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.The' tables _below give the requested travel comparisons.

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To/From Coatesville

~ Heliccpter Vehicle

-Travel Time (minutes)

Travel Time (minutes)

' Chesterbrook 34 8

Peach Bottom EOF 71 25 Limerick' EOF.

42 20 To/From Chesterbrook Vehicle Helicopter Travel Time (minutes)

Travel Time (minutes)

Peach-Bottom EOF 100 30 Limerick EOF 18

  • - No helicopter' service available NRC Iter

. 8.'

Prcvide a detailed description of the reasons or advantages of combining the separate EOFs for Limerick and Peach Bottom at the Coatesville Service Building.

This description should not use generalities such as better maintenance, better control and improved efficiency, but should clearly explain what each advantage _is and how it improves the EOF capabilities.

Response

The proposed new facility is planned to be built adjacent to the PECo Service Building in Coatesville, Pennsylvania, and

~will serve as a common EOF for both LGS and PBAPS.

The highway system in the Coatesville area and the proximity to the Coatesville airport (Carlson Chester County l:

Airport)_ provide excellent accessibility from all locations. This i

l new facility wil2 serve as both an EOF and Joint Information Center'(see Attachment 5 for plan of facility). As a dedicated facility, designed primarily for meeting the requirements of an EOF and incorporating the needs of the responding agencies, this

- faci]ity will significaistly improve the performance capabilities l

of the PECo Emergency Response Organization (ERO) and other l

responding agencies for reasons explained below.

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A.

Size The proposed facility is significantly larger than the l

cxisting EOFs at either PBAPS or LGS (see Attachment 5). The new EOF will provide more than sufficient space for PECo, NRC, State, and local response personnel. As part of the initial design ph.ase 1

for this facility, PEco reviewed the roles and emergency response philosophy with representatives from other all responding-agencies. The~ size of the core area and office space of the facility reflect the suggestions which came from these discussions. As a result, the ability of responders to perform their functions will be sig lificantly enhanced.

B.

Facility Activation Enhancements The proposed facility will provide significant improvements in EOF operational capabilities over that which is currently t'

provided by the existing EOF facilities. The specific improvements are described below.

1.

Emergency Response Organization (ERO) Logistics PECo utilizes station manpower to aid in staffing the PBAPS and LGS EOF facilities, with a majority of corporate resources reporting to iacilities at the corporate Headquarters (Headquarters Emergency Support Center - HESC) in Philadelphia.

The corporate Nuclear Group personnel that currently staff i

the HESC would be reassigned to the new Coatesville EOF when it becomes operational. The combination of a new EOF in Coatesville, and relocation of the PECo Nuclear Group to Chesterbrook will eliminate the need for the HESC. As a result, corporate personnel who are members of the ERO will report directly to the new EOF.

This new arrangement has the advantage that travel routes from Chesterbrook to Coatesville are significantly less congested during working hours than routes from Chesterurook to metropolitan Philadelphia. The propcsed EOF will also result in a clearer demarcation of the responsibilities of those ERO individuals who man the TSC and EOF. This will consolidate the ERO and. emergency response roles can be clearly defined and effectively managed from the appropriate facilities (i.e. EOF, TSC, etc.) ther2by, improving emergency response capabilities.

Furthermore, a majority of the corporate responders reside in the area west of Philad9lphia. Accordingly, those individuals will be able to quickly ctaff the EOF as well as the Chesterbrook offices in the event of an emergency during non-working hours since both locations are also west of Philadelphia. - _ _ _ -___ _

C.- Design Enhancements 1..

Data Availability and Display As part of the design of the proposed EOF facility, several

. data acquisition system improvements will be incorporated to

' improve operational' capabilities. These include the following.

a.

Incorporation of the new data acquisition system for PBAPS which meets the applicable requirements of NUREG-0737, Supplement 1, " Requirements for Emergency Response capability."

This system, a part of the new plant monitoring system (PMS),-is a Digital Equipment VAX 8530 based system provided by' Science Applications Incorporated (SAIC)

The

-major functions of the PMS include the following.

o Scan-log and alarming of plant variables.

o Nuclear Steam System Supplier (NSSS) performance package (MONICORE by GE).

o Balance of plant package.

o Safety parameter display aystem.

o Control rod worth minimizer. provides specific details.regarding the capabilities of the new data acquisition system for PBAPS.

Tilis system will provide real-time plant condition data via color graghic CRT monitors. This data acquisition system is scheduled to be operational by the end of the eighth refueling cutage for PBAPS Units 2 and

.3, scheduled for July, 1992 for Unit 2, and June, 1991 for Unit 3.

b.

Transfer of LGS Emergency Response Facility Data System (ERFDS).

This system, presently operational for Unit 1 at the existing LGS EOF, is part of the General Electric (GE)

Emergency Response Information System. The LGS Unit 2 system, which will be operational after unit startup, is part ot the GE Plant Monitoring System (PMS). Both systems will be incorporated in the new EOF to provide real-tima plant data.

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c.

Development of a Common Dose Assessment Model for-PBAPS and LGS.

The existing dose projection models for LGS and PBAPS were designed'and obtained at different times.and each was uniquely designed for the particular station. We j

are pursuing the development of a common system, for i

this primary EOF function, with site specific l

characteristics, as part of the new EOF. This common.

model is targeted for completion by March, 1990,

d. Video Projection Display of Data and Information.

A Video Display area will be provided at the new EOF (see ). Each of the above mentioned systems will be connected to video projectors for real-time projection of plant condition and radiological assessment data. The location of this display area assures that EOF personnel.

will be able to view and thereby recieve timely and accurate information.

e.

Reliability of Data and Voice Communications Systems.

The existing modes of data and voice communications between the stations, existing EOFs, and HESC are via microwave and leased telephone lines. Communications with external support agencies are through telephone lines.

The availability and reliability of these systeps was evaluated as part of the design process in selecting a location for the proposed EOF.

The proposed Coatesville EOF will take advantage of an existing sophisticated and reliable telecommunication systen. The Coatesville Central Office (CO) is a SE third generation Private Branch Exchange (PBX) CO. This CO has two (2) major lines; one line serves the Ft.

Washington CO, which is a level 4E PBX and contains 168 individual trunk lines, and the second line serves the Philadelphia CO, which is also a level 4E PBX containing 144 trunks. Long distance capabilities are provided by AT&T with 148 trunk lines, and MCI with 24 trunk lines. illustrates the present communications network available for the existing PBAPS EOF. Attachment 8 illustrates the enhanced telecommunication capabilities at the new EOF.

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PECo utilizes its microwave system.for dedicated

' emergency communications. This system is extremely reliable and economical, ' and has been used since 1981.

Therefore, proximity to a microwave system was a factor in the site location selection proce.ss for the new EOF.

The proposed Coatesville EOF is approximately 1.2 miles from the Coatesville microwave staticn. This will allow L

pECo to ultilize the existing microwave system and maintain the same level of reliability.

The existing methods for communicating with' emergency response field radiation survey and environmental sampling teams is by radio. This methoi also serves as a

-backup for communicating with the stati.ons. This form of-communication will continue to be used at the new EOF for communicating with field radiation survey and environmental sampling teams, and backup for communication with the stations.

C.

Accessability and Adequacy of the Proposed EOF Facility to.

Meet NRC Region I Response Team Needs.

1 shows the location of the proposed EOF in relation to the NRC Region I offices. Accessibility,

,1 particularly for an emergency at PBAPS, is significantly improved. ~shows the functional layout of the proposed EOF, including space and accommodations for the NRC Region I response team. The space and accommodations afforded by the proposed facility were coordinated with the appropriate personnel from the NRC Region I.

These accommodations provide a significant improvement over

.that which currently exists at either the PBAPS or LGS EOF.

For the NRC kugion I emergency response team reporting directly to the stations, muster areas are provided at the LGS personnel processing center and the PBAPS Unit 1 TSC.

NRC' Item 9.

Indicate whether this location for the EOF has been i

coordinated with State and local governments within the 10-mile EPZ of each plant site. Provide 3etters from these government entities indicating their approval or acceptance of this location, if possible. _ _ - _ -.

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l Resoonse l

The selection of this. location has been reviewed with all i

responding agencies. Letters of concurrence have been recieved from Pennsylvania Emergency Management Agency (PEMA), Ma~ryland Emergency Management and' Civil Defense Agency (MEM&CDA),

Commonwealth of Pennsylvania; Department of Environmental Resources / Bureau of Radiation Protection (PA DER /BRP), and Maryland Center for Radiological Health (MC CRH). Copies o-f these l'

letters are included in Attachment 9.

NRC Item 10.

Provide a description of the new plant monitoring system (PIIS) for Peach Bottom plant including the type of system, the number of parameters and individual variables covered in the data base, methods of transmission to the TSC and EOF, and a general description of the system hardware. Compare the PMS with the emergency data acquisition system available at Limerick and describe how the Limerick system will be transferred and installed in the new EOF.

Response

The new PMS, for PBAPS, as previously described in response to Item 8, is a Digital Equipment VAX 8530 based system (see ). Science Applications Incorporated (SAIC) is the prime contractor, providing their plant monitoring software (SAIPMS) and system integration. The major functicas are as follows.

o Scan-log and alarming of plant variables.

o Nuclear Steam System Supplier (NSSS) performance package (MOICORE by GE).

o Balance of plant package.

o Safety parametcr display system.

o Rod worth minimizer. provides specific details regarding the capabilities of the new data acquisition system, a part of the new PMS, at PBAPS.

At PBAPS the man machine interface will be via color graphic CRTs with touch screen capabilty (IDT model 2250). The keyboard will support function keys as well as provide for normal data entry. Attachment 6 indicates the number of plant parameters monitored by the PMS and the individual variables covered in the PMS data base. The transmission link to the EOF will utilize leased line communication. The transmission link to the TSC is via house cable. - _

i The ERFDS for LGS Unit 1 is part of the General Electric

~ Emergency Response.Information System (ERIS), while the ERFDS for Unit 2 is part of the General 21ectric PMS. Presently, there is a Toshiba Intelligent Graphic Display Terminal (IGDT) for each system (ERIS and PMS) in the LGS EOF located in the Plymouth Service Building. Both terminals communicate with respect.ive computer systems via modems which are connected to the Limerick / Plymouth microwave link. The Toshiba terminals provide personnel'in the EOF with real-time plant data via the ERFDS displays.

A new microwave link will be established between LGS and

'Coatesville EOF. After completion and testing of this new microwave link, the Toshiba terminals would be moved to the Coatesville EOF and installed in the EOF display area (see ).

A Tektronix video terminal and copier, which are part of

.the Radiation Meteorological Monitoring System (RMMS), will be relocated from the existing LGS EOF to the Coatesville EOF in an identical manner. The Tekronix terminal is used to provide access to the LGS dose assessment model and site meteorological information.

The PBAPS and LGS emergency data acquisition systems are very similar in that they will provide the required plant

-data via their own color CRT terminals; however, the systems do differ in the manner in which the data is displayed.

The relocation of the data acquisition system for LGS, and incorporation of a new system for PBAPS, will allow emergency r6sponse personnel to access real-time plant and meteorological parameter data thereby, increasing their ability to assess accident conditions and take the appropriate response measures. _ _ _

ATTACHMENT 2 INTERNAL PICTURES OF EXISTING LGS AND PBAPS EOFs i

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1 I ATTACHMENT 4 1 HELICOPTER SERVICE AGREEMENTS +

7x.4=::,-+ - ~ u.. .: :::~ ; ..-c . ~ :..w 'I i ? v& l l' - KEYSTONE FLIGHT SERVICES A emon at MEYSTONE HEUCOPTER CORPORATION February 128, 1989 j Mr. Ed Dold General Superintendent PHILADELPHIA ELECTRIC Transportation Division ~1050 Swedesford Road Bervyn, PA. 19312 1

Dear Ed:

3 I am very pleased-to. respond to your request for helicopter ' :I i support during emergencies. { Keystone Flight Services will be able.to receive and dispatch -l . helicopters during a PECO emergency on a twenty-four hour per j day, 7 day,per week basis. We vill be'able to have the helicopter dispatched within j approximately.1/2 hour of PECO's request during. normal business hours and 1 1/2 hours during after business hours, veekends and ' holidays. 1 If at the time of PECO's request, the weather, aircraft or pilot-tj availability prevents immediate dispatch, Keystone vill inform 1 'PECO of the earliest time an aircraft can be dispatched. i This service can.be obtained during any hour by calling our .i normal business phone number (215) 644-4430. After normal business hours our answering service vill relay your request to one.of our Flight Services managers "on-call". j .As~you know,' Keystone has been providing quality helicopter service to PECO for over thirty years and we have always taken great pride in the trust you have placed in us. Thank you. j Sincerely, l KEY KE7fLIGH S$RVICES j i 1 / '/ k Hinkle Rf Division Manager RH/ss i h L 1420 Phoenixvme Pike + West Chester, Pennsylvania 19380 * (215) 644-4430

  • rAr (215) 644-7681
  • TELEX 510 668 5061

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!i y - HEllCOPTER TRANSPORTATION AT ITS FINEST ' RT.309 & HILLTOP ROAD

  • COOPERSBURG, PA 18036 -+ '(215) 282-4100 I

L i February 27th, 1989 Philadelphia Electric Company 1950 Sweedesford Road t Berwyn. Penna. 19312 j ATTENTION: Mr. E.L. Dold- ) i Dear Mr. Dolds I'am responding to an inquiry made by Mr. Robert Leifhold, of your office in reference to Fleet Helicopter' Services responding to I Philadelphia Electric Company under emergency situations. i Please be. advised that Flect Helicopter Services would respond to an emergency call.made'to'our office in any.24 hour span. We feel that from the time of the.callf(weather' permitting) we would-I be eble'to respond'within.-three hours, probably sooner. This would give the pilot sufficient. time to drive in,: fuel up, flight plan, and ) depart for wht.tever site we:would be called.- _q i, Our pilots are trainhd to respond ut. der emergency situations, of course if Philadelphia Electric' Company was requesting something>that was unreasonable or unsafe..we could not ask our pilots;to adhere to such a request. Please note that Mr. William Thayer, our President and l . Director of Operations, depending on the situation would be called upon l to supervice and if additional flying is requited will be able to fly the miseion, as he is also a pilot with many hours of experience. 1 Please be-assured that if the need arises and Fleet Helicopter Services would be called upon, we.would make every effort 1 to-make sure that our part would run as smoothly as possible. l Thank you, if you have any questiors, please do not hesitate to call us. J Tincerely, ) Fleet elicopter services / jt j i =

l ATTACHMENT 5 4 PROPOSED. EOF FLOOR PLAN

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ATTACHMENT 6 PBAPS. DATA ACQUISITION SYSTEM PARAMETERS L 1

W,"'~ T5: im-. < ' ~ 4 m 'REGGUIDE1.97'POINTSFkRP Elbh 29 MAR 1989 PAGE 1 F INPUT NO PT ID POINT DESCRIPTION............... RG 1.97 PARAMETER... l ,[A1912 M300 OFF GAS' STACK RADIATION LEVEL Al C13/E4 PART 6 L' -(NARROW RANGE) A1913 M301' O'F GAS STACK RADIATION LEVEL B C13/E4 PART 6 (HARROW RANGE) A1970 - E335 EMERGENCY DIESEL GENERATOR D25 PART3 VOLTAGE El A1971-

E336 EMERGENCY DIESEL GENERATOR D25 PART3 L

VOLTAGE E2 CA1972 E337 EMERGENCY DIESEL GENERATOR D25 PART3 VOLTAGE E3 A1973-E338' EMERGENCY DIESEL GENERATOR D25 PART3 VOLTAGE E4 'A1974 E339 EMERGENCY DIESEL GENERATOR D25 PART3 CURRENT El A1975-E340 EMERGENCY DIESEL GENERATOR D25 PART3 CURRENT E2 ~ 'A1976 'E341 EMERGENCY DIESEL GENERATOR-D25 PART3 CURRENT E3 A1977-E342-EMERGENCY DIESEL GENERATOR D25 PART3 CURRENT E4 )921 M359 VENTILATION STACK RADIATION 'E4 PART 5/C14 LEVEL A' A2093 M360 VENTILATION STACK RADIATION E4 PART 5/C14 l LEVEL B ] A2094 T379 UNIT VENT' STACK FLOW A E4 PART 7 A2111 F300- CONDENSER PRESSURE A D28 A2112 F301-CONDENSER PRESSURE B D28 A2113 F302 CONDENSER PRESSURE C D28 A2164 T381 DRYWELL HIGH RADIATION CH A CS/El A2173 T361 DRYWELL HIGH RADIATION CH C CS/El l A2174 T362 DRYWELL HIGH RADIATION CH B C5/El A2175 T363 DRYWELL HIGH RADIATION CH D - C5/El 'A2677 B300 AVG. POWER RANGE MONITOR LEVZL CH B1 A i A%678 B301 AVG POWER RANGE MONITOR LEVEL CH B1 C 'i' 57 9 B302 AVG JWER RANGE MONITOR LEVEL CH B1 x ;. - g c

y.a [ ~ -- J.z ~... -. - I ' REG GUIDE 1.97 POINTS FOR PEACH 3 29 MAR'1989 PAGE 2 , IN1-iJT NO PT ID POINT - DESCRIPTION............... RG 1. 97 PARAMETER... T580 B303 AVG POWER RANGE MONITOR LEVEL CH'B1' {2.f B ^ -A2681

B304':AyG POWER RANGE MONITOR' LEVEL CH B1 D

l A2682 B305 AVG POWER RANGE MONITOR LEVEL CH B1 F A2713 B344-REACTOR FEEDWATER DSCH FLOW A Y (DELTA-P) A2714 B345 REACTOR FEEDWATER DSCH FLOW B Y (DELTA-P) A2715 B346. REACTOR FEEDWATER DSCH FLOW C Y (DELTA-P) A2731 B333 RECIRCULATION DRIVE FLOW Al D30 ! 'A2732 B334 RECIRCULATION DRIVE FLOW A2 D30 i ~A2733 B335 ~ RECIRCULATION DRIVE FLOW B1 D30 A2734 B336 RECIRCULATION DRIVE FLOW B2 D30 A2918 M306 Pl1 ACTOR BLDG SUMP AREA RAD (ARM E2 j

  1. 1)

{; .. s.. b~/919 M307 TORUS' COMPARTMENT RAD-(ARM #2) E2 1 l -A2920 M308 HPCI ROOM RAD (ARM #3) E2 l lA2921 M309.RCIC ROOM RAD (ARM #4) E2 p 'A2922 M310 RHR PUMP ROOM D RAD (ARM #5)- E2 t A2923 M311 RHR PUMP. ROOM A RAD (ARM #6) E2 A2924 M312 CORE SPRAY ROOM A RAD (ARM #7) E2 A2925 'M313 ELEV. 116' REACTOR BLDG SOUTH E2 TRIANGLE RM RAD (ARM #9) A2926 M314 ELEV. 116' REACTOR BLDG NORTH E2 ~ TRIANGLE RM RAD (ARM #10) 'A2928 M316 D/W EQUIP ACCESS LOCK /TIP E2 CONTROL AREA RAD (ARM #15) 'A2929 M317 TIP WITHDRAW AREA RAD (ARM #18) E2 3 -A2931 M319 NEW FUEL STORAGE AREA RAD (ARM E2

  1. 26)

A2932 M320 FUEL POOL AREA RAD (ARM #30) E2/E3 r '[ 45 M333 CONDENSER WATER BOX #5 EFFLUENTS B2 CONDUCTIV1TY

7p%g x y m ,w --u.. xf a.-,::a:n...--';u-.-.,;.:...s ;:..,a.-:;;;zz a p m zy m a m [. /h . ;; e yREG GUIDEol.97LPOINTS FOR PEACH 3L' 29aMARl1989... -PAGE 3' JINPUTfNO-lPT.1ID~ POINT DESCRIPTION.... 3......'...'RG 1.97 PARAMETER.'.. L r .jy I \\ j-N.946h LM334 MCONDENSER WATER. BOX 46? EFFLUENTS B2 ' df.' CONDUCTIVITY- ' l'A29 671 ' 'E332. ?4 KV-EMERGENCY BUS.1~ D25.PART3 i j s, y LA29681 iE333~ 4'KV EMERGENCY. BUS'2- 'D2'5 PART3+ J 4 KV EMERGENCY BUS-3 'D25 PART3-4.-A2969 E334 EA2980 .E345; 4KV EMERGENCY BUS.4 D25 PART 3-

1. p-

?A2982.: E347'-125/250 VOLT.DC SYSTEM l' D25 PART.3 LA2983. E348125/250 VOLT:DC. SYSTEM 2 D25 PART,3 MA2986' .F367; CIRCULATING WATER PUMP A D29 . DISCHARGE' my .A2987 F368'; CIRCULATING WATER PUMP B D29 DISCHARGE /A2988l F369'.! CIRCULATING WATER PUMP Ci D29 DISCHARGE. 'l 0A'4000 H300 'RTR WTR LVL A.(WIDE' RANGE)' DELTA-A2/B4 -P. s .s A4001-

H301.RTR WTR LVL.B (WIDE RANGE)

A2/B4L .j DELTA-P g:<. ~ qi lI4002~. 'H202 -RTR WTR LVL A (FUEL ZONE) A2/B4 DELTA-P !A4003' H303 RTR WTRl.LVL B'(FUEL ZONE) -A2/B4 -DELTA-P <lA40041 H304: -REACTOR PRESSURE.A A1/B6/C4/C9 tA4005 .H305' REACTOR PRESSURE B A1/B6/C4/C9 'A4006.- -H30'6 DRYWELL' PRESSURE A-(WIDE RANGE) AS/,B7/B9/C8/C10/D4 ~A4007! H307-DRYWELL PRESSURE B (WIDE RANGE) AS/B7/B9/C8/C10/D4. 'A4008 'H308:.DRYWELL PRESSURE C (NARROW A5/B7/B9/C8/C10/D4 RANGE) J A4009; _H309-DRYWELL PRESSURE D (NARROW AS/B7/B9/C8/C10/D4 RANGE) A4'010-H310 DRYWELL TEMPERATURE A D7 A4 011 - iH311 cDRYWELLxTEMPERATURE.B D7 eA4012 H312i SUPPRESSION POOL BULK (AVG.) A3/D6 TEMPERATURE A 3: Ao013 H313 SUPPRESSION POOL BULK (AVG.) A3/D6

y ++w+Rymm gwa g anfa +a7m nan==+i a aa a =; a= = = w i = +.-=- w a : n fiU2)iL* b,, R-291 MAR 1989. _4- 'l + .i PAGE 1:K REG GUIDEil.97=l POINTS:FORiPEACH3-3 s fM INPUT;NO>PTJIDl POINT DESCRIPTION- ' ~^ ~ .RG,1.97 PARAMETER... ,] p.y e O 4,, g > TEMPERATURE Bi e LI i l hin,. 2 , hh14 y

H3141. SUPPRESSION POOL
LEVEL A' (WIDE L.A4/C7/05 QgM N

-RANGE) . yc , a; e f,pA4015 i_ H315 ) LSU' PRESSION i POOI? LEVEL.B (WIDE ' .A4/C7/D5 - P g RANGE)l 1 4 9 J A4016L IH316.~ SUPPRESSION: POOL. LEVEL A.(NARROii - u gi7, RANGE). J A4 017. ' LH317: SUPPRESSION POOL LEVEL B~(NARROW'- ..m-RANGE)- a J '[A4018L 'H318'? SOURCE RANGE MONITOR CHANNEL A B1 fA$$19.

H319I SOURCE RANGE MONITOR CHANNEL B
Bl.

'A4020J ,l K.. EH320 ISOURCE RANGE MONITOR CHANNEL C Bl. 1A4021 H321; SOURCE' RANGE-MONITOR ~ CHANNEL D B1-1 H[A4022L eH322..0FFGAS STACK RADIATION (WIDE-C13/E4 PART 6 4 RANGE). ,mH 7A'023L H323{ VENT STACK RADIATION (WIDE C14/E4 PART 5 4 . RANGE). -j >l JA4024'

H3'24-LDRYWELL~ HYDROGEN CONCENTRATION C C11 M 25-

.LH325siTORUS AIRSPACE" HYDROGEN C11 CONCENTRATION.A' .a L ' A4 026 - - H332, STANDBY LIQUID CONTROL SYSTEM D17! kj = (SLCS) o PRESSURE. g -i 4

A4027-

.H342i DRYWELL HYDROGEN CONCENTRATION B C11 A4028. H345 TORUS AIRSPACE HYDROGEN' C11 l CONCENTRATION D 1 ': AkO29' H344 TORUS AIRSPACE OXYGEN C12/A6 CONCENTRATION A JA4030. 'H3451 DRYWELL OXYGEN CONCENTRATION B C12/A6 -A4031 H346-DRYWELL OXYGEN CONCENTRATION C C12/A6 jA4032; iH347 TORUS AIRSPACE OXYGEN C12/A5 l CONCENTRATION D A4033- ~H350 CONDENSATE STORAGE TANK LEVEL D2 A4034' H351. SUPPRESSION CHAMBER SPRAY FLOW A D3 ~ ] 'A4D35; -;H352' SUPPRESSION-CHAMBER SPRAY FLOW B D3 )f036' ?H353' HIGH PRESSURE COOLANT INJECTION D14 4 FLOW A J .L_L_ _ _ _______J____.

p : Y :.L.~ ' L.- - w. ~, ~.-. : ~~ x:. -....- ~ ga LREG GUIDEL1.97 POINTS FOR PEACH 3 29 MAR 1989 PAGE-5 . INPUT No PT ID POINT DESCRIPTION............... RG 1.97 PARAMETER... JA4037 H354.1 REACTOR CORE ISOLATION COOLING ~ D13 b?\\ A[038 'H355-CORE SPRAY FLOW (A&C PUMPS) D15 .l /. j A4039. H356 CORE SPRAY FLOW (B&D PUMPS) D15 i A4040 H357' STANDBY LIQUID CONTROL TANK D18/D17 . LEVEL - A4041-H358 RESIDUAL HEAT REMOVAL - A LOOP D19, D16 FLOW (A&C PUMPS) 'A4042 H359 RESIDUAL HEAT REMOVAL - B. LOOP D19, D16 FLOW (B&D PUMPS) A4043 H360 RHR HX OUTLET TEMPERATURE (A D20 PUMP) h4044' H361 'RHR HX OUTLET TEMPERATURE (B D20 PUMP) LA4045 'H362 RHR HX OUTLET TEMPERATURE (C D20 PUMP) A4046 H363 RHR HX' OUTLET TEMPERATURE (D D20 PUMP) A4047 H364 RAD WASTE COLLECTOR TANK LEVEL D23 k.[948-H365 RADWASTE SURGE COLLECTOR TANK D23 LEVEL ,A4049 H366 FLOOR DRAIN COLLECTOR TANK D23; A4050 H367 FLOOR DRAIN SURGE TANK D23 iA4051 H373 El D/G TO E13 BUS CURRENT D25 PART 3 A4055 H385

  1. 3 SU TO E23 BUS CURRENT D25 PART 3 A4056 H386 -E3 D/G 10'E33 BUS CURRENT

'D25 PART 3 A4057.- H387

  1. 2 SU TO E33 BUS CURRENT D.25 PART 3 A4058 H388
  2. 3 SU TO E33 BUS CURRENT D25 PART 3 A4059 H389 E4 D/G TO E43 BUS CURRENT D25 PART 3 A4060 H390
  3. 2 SU TO E43 BUS CURRENT D25 PART 3 A4061 H391
  4. 3 SU TO E43 BUS CURRENT D25 PART 3

~A4062 H409 24 VDC BUS PANEL 3AD45 VOLTS D25 PART 2 A4063 H410 24 VDC BUS PANEL 3BD45 VOLTS D25 PART 2 M064 H412 RBCCW PUMP AREA RAD (ARM #11) E2 A*065 H415 REACTOR BLDG NEAR PERSONEL D/W E2 l

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wa-an:n.:+..-

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,u - ~. j P 4.. iREG. GUIDE:1.971 POINTS FOR PEACH 3 29' MAR 1989 <PAGE 6l .j SINPUT NO*PT ID POINT DESCRIPTION.............. 2G 1.97. PARAMETER.... . ACCESS '(ARM.: #16) : 66, H416.! REACTOR: BLDG SE STAIRWELL ELEV E2- -o I .135.(ARM #17) lA'4'067: H419 RINCTORBLDGSAMPLESINKELEV 'E2 165 RAD (ARM #21). j .A4068- 'H420 -REACTOR BLDG STAIRWELL ELEV 165 E2 -l RAD (ARM _#22) hA4069-H423 FAN ROOM ELEV 195 AREA RAD'(ARM-E2 l ~

  1. 27).

A4070 H424 STEAM SEPARATOR POOL AREA RAD E2/E3 l -(ARM #28) j

  • A4071 H425-REACTOR REFUEL SLOT AREA RAD.

E2 t (ARM #29) 'A4072

H426. REFUELING BRIDGE AREA RAD (ARM.

E2

  1. 31)"

..A4 075 H447 OFFGAS STACK FLOW B E4 PART 8 LA4076 H450 UNIT VENT STACK FLOW B E4 PART 7 -A4081 -H455 EMERG SERVICE WATER PRESSURE' D22, 21 1

  • ~~pB2 H456 'EMERG SERVICE WATER PRESSURE D22, 21 e

II'083l H470. TURBINE BYPASS VALVE POSITION D26 PART 10 L i 'A4084 .H471 CONDENSER HOTWELL LEVEL A D27i i i EA4085 .H472 CONDENSER HOTWELL LEVEL B D27 A4086 H473 ' CONDENSER HOTWELL LEVEL C D27 /A4088 H4751 VOLTAGE TRANSDUCER TO OUTPUT OF D25 PART 1 30Y50 PANEL ~A4089 H476

  1. 2-SU TO E23' BUS CURRENT D25 PART 3

?A40'2 H534 EMERG SERVICE WATER TEMP A D21, 22 9 l l-A4093 H535 EMERG SERVICE WATER' TEMP B-D22, 21 A4173^ H337 DRYWELL FLOOR DRAIN SUMP LEVEL B8, C6 l ~. ' A417 5 'H463 DG MAN START AIR' PRESSURE B-D25 PART 10

  • I ?,4176 H465 DG MAN START AIR PRESSURE D D25 PART 10

!A4177 kH467 DG: AUTO START.. AIR PRESSURE B D25 PART 20 1A4178L H469 DG AUTO START AIR PRESSURE DIR D25 PART 10 I START SUPPLY D i~ (t A4181' 'H330 LIQUID N2 CAD TANK LEVEL D25, PART 6

~ ~ - - - - - ~ - - w.~. .w . ~... . REG' GUIDE.1.97 POINTS FOR PEACH 3 29 MAR 1989 PAGE 7 . INPUT'NO PT ID POINT DESCRIPTION............ ...~RG 1.97 PARAMETER... 1 H335 DRYWELL EQUIP DRAIN SUMP LEVEL B8, C6 {".8 4 ' 51186 . H4 62' DG AMN START AIR PRESSURE A D25 PART 10 'A4187 .H464 DG' MAN START AIR PRESSURE C D25 PART 10 A4188 H466 DG AUTO START AIR PRESSURE AIR D25 PART 10 START SUPPLY A A4189 H468 DG AUTO START AIR PRESSURE C D25 PART 10 A419S H478 LONG' TERM ADS N2 SUPPLY A D25 PART 5 A4196 'H479 LONG TERM ADS N2 SUPPLY B D25 PART 5 A4199' H413 HPC1 TURBINE CASING #1 TEMP A4200 H414 HPCI TURBINE CASING #2 TEMP A4202 H411' BATTERY ROOM VENTILATION 'C2142' 'M809 INSTRUMENT AIR HEADER A LOW D25 PART 9 PRESSURE C2145 M812 INSTRUMENT AIR HEADER B LOW D25 PART 9 PRESSURE C2585 D869 RV3-71A VALVE POSITION D10 INDICATION. C2586 D870 RV3-71B VALVE POSITION D10 INDICATION C2587-D871 RV3-71C VALVE POSITION D10t INDICATION C2588-D872 'RV3-71D VALVE POSITION D10 INDICATION C2589 DB73 'RV3-71E VALVE POSITION D10 INDICATION C2590 DB74-RV3-71F VALVE POSITION D10 INDICATION C2591 D875- 'RV3-71G VALVE POSITION D10 INDICATION C2592 D876 RV3-71H VALVE POSITION D10 INDICATICN' 1 I l C2593 L877 RV3-71J VALVE POSITION D10 INDICATION t i C2594 D878 RV3-71K VALVE POSITION D10 INDICATION ( - ;9 5 D879 RV3-71L VALVE POSITION D10 INDICATION l l

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  • i960 ;DS87 lRV3-70ALVALVE POSI"' ION D10 i

t'{Q - INDMATION.; j L i @{U257% ID881f Ry3-70B VALVE POSITION D10 p INDICATION C2801". .ZC00: CONTROL ROD SELECT. B2. j (C2802; Z801-. CONTROL ROD. SELECT B2 [ C2803, Z802i CONTROL ROD SELECT- ' B2 .C2804: .Ed03,LCONTROL-ROD SELECT B2 y g _ ,iZ304: -CONTROL ROD SELECT B2 .C2805~ C2806: .Z805 ' CONTROL' ROD SELECT B2 . C2807' Z80'6L'CCNTROL' ROD SELECT B2

C2308 Z807 ' CONTROL ROD SELECT

-B2 ~ 'C2810 Z808' CONTROL. ROD' POSITION XO 'B2 C2811 'Z809 CONTROL. ROD POSITION X2-B2 -C2812 Z810t CONTROL ROD POSITION'X4 B2 "C'813

ZBill CONTROL ROD' POSITION X6 B2

'.C2 814 'Z812 ~ CONTROL ROD POSITION X8 B2 C2815-Z813.' CONTROL ROD' POSITION TENS.0X-B2 i C2816 Z814 CONTROL ROD POSITION'TENSL1X B2' 'C2817. Z815-CONTROL ROD POSITION-TENS'2X B2 C2818 .Z816' CONTROL ROD POSITION' TENS 3X B2 C2819 Z817 ; CONTROL ROD POSITION TENS 4X B2 C4000 H326 SRM PROBE POSITION A B1 .C4001~ H327.'SRM PROBE POSITION B B1 C4002 H328 'SRM PRODE POSITION C B1 ,C4003 H329 SRM PROBE POSITION D B1 .C4025 H392 REFUEL FLOOR EXHAUST DUCT D24 OUTBOARD ISOLATION DAMPER L.iC4026 rH393 ' REFUEL FLOOR; INLET, DUCT INBOARD..D24 ? ISOLATION DAMPER -Cd027' 'H394' REACTOR BUILDING EXHAUST DUCT D24 L (u'. OUTBOARD ISOLATION DAMPER i-

mas

p.==:~ : : -. ; -.z. u.a..; :ua =... :.;;. a. x..-. L REG GUIDE 1.97 POINTS FOR PEACH 3 29 MAR.1989 PAGE 9 INPUT NO PT ID POINT DESCRIPTION............... RG 1.97 PARAMETER... C4 018' H395 ' REACTOR BUILDING INLET DUCT D24 INBOARD ISOLATION rAMPER (ap NO29 H396 REACTOR BUILDING EQUIPMENT CELL D24 .l EKHAUST OUTBOARD ISOLATION DAMPER C4030 H397 DRYWELL PURGE SUPPLY-INLET D24 INBOARD ISOLATION DAMPER C4031 H402 ' REFUEL FIDOR EXHAUST DUCT D24 INBOARD ISOLATION DAMPER C4032 H403 REFUEL FLOOR INLET DUCT OUTBOARD D24 ISOLATION DAMPER C4033 H404 REACTOR BUILDING EXHAUST DUCT D24 INBOARD ISOLATION DAMPER C4034 H405 REACTOR BUILDING INLET DUCT D24 OUTBOARD ISOLATION DAMPER C4035 H406. REACTOR BUILDING EQUIPMENT CELL D24 EXHAUST INBOARD ISOLATION DAMPER C4036 H408 DRYWELL PURGE SUPPLY INLET D24 OUTBOARD ISOLATION DAMPER C4040 H457 INST. N2 A SUPPLY PRESS D25 PART 9

g Q.041' H458-INST. N2 B SUPPLY PRESS D25 PART 9 C4052 H480 MAIN STEAM INBOARD ISOLATION B10 VALVE A C4053 H481 MAIN STEAM INBOARD ISOLATION B10 VALVE B C4054 1I482 MAIN STE!JI INBOARD ISOLATION B10 VALVE C C4055 H483 MAIN STEAM II; BOARD ISOLATION B10 VALVE D C4056 H484 MAIN STEAM OUTBOARD ISOLATICif B10 VALVE A C4057 H485 MAIN STEAM OUTBOARD ISOLATION B10 VALVE B C4058 H486 MAIN STEAM OUTBOARD ISOLATION B10 VALVE C C4059 H487 MAIN STEAM OUTBOARD ISOLATION B10 VALVE D

~ C4060 H488 MAIN STEAM DRAIN INBOARD B10 ISOLATION VALVE i C4061 H489 MAIN STEAM DRAIN OUTBOARD B10

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INPUT'NO PT ID POINT DESCRIPTION........;....... RG 1.97 PARAMETER...

ISOLATION VALVE .) 62 H490 RECIRC. LOOP SAMPLE INBOARD B10 ISOLATION VALVE C4063 H491 RbCIRC. LOOP SAMPLE OUTBCARD B10 d ISOLATION VALVE C4064 H492 MAIN STEAM SAMPLE INBOARD B10 ISOLATION VALVE C4065 H493 MAIN STEAM SAMPLE OUTBOARD B10 ISOLATION VALVE 1 C4066 .H494 FEEDWATER-LONGPATH'RECIRC. .B10 ISOLATION C4067 H495 RWCU RETURN ISOLATION VALVE B10 C4068 H496 FEEDWATER-LdNGPATH EECIRC. B10 ISOLATION C4069 H497 RHR, SHUTDOWN COOLING SUCTION B10 OUTBOARD ISOLATION VALVE C4070 H498' RHR SHUTDOWN COOLING SUCTION B10 INBOARD ISOLATION VALVE C4071 H499 RHR SHUTDOWN COOLING RTN & LPCI B10

  • : 1, INJECT A ISOLATION VALVE (M

-H500 RHR SHUTDOWN COOLING RTN E.:LPCI B10 C4072 INJECT B ISOLATION VALVE C4073-H501 RWCU PUMP SUCTION INBOARD B10: ISOLATION VALVE C4074 H502 RWCU PUMP SUCTION. OUTBOARD B10 ISOLATION VALVE C4077 H505' DRYWELL FL. DR. INBOARD B10 ISOLATION VALVE C4078 H506 DRYWELL FL. DR. OUTBOARD B10 ISOLATION VALVE C4079 H507 DRYWELL EQUIP. DR. INBOARD B10 ISOLATION VALVE C4080 H508 DRYWELL EQUIP. DR. OUTBOARD B10 ISOLATION VALVE L C4081 H509 INST. N2 D/W HELDER A ISOLATION B10 VALVE C4082 H510 TIP 1 SOLATION B10 Cd083 H511 TIP PURGE ISOLATION VALVL B10 bkOB4 H512 INST. N2 D/W HEADER B ISOLATION B10 m

(O CLRJi ._2._.s__.. .ma_. ! REG GUIDE 1.97 POINTS FOR PEACH 3 29 MAR 1989 .PAGE 11- . INPUT.NO PT ID POINT DESCRIPTION.... ..........'RG 1.97 PARAMETER...._ VALVE 85

H514 INST..'N2 TORUS ISOLATION VALVE B10 4

"C4086 M515 TQRUS WATER CLEANUP SUCTION B10 j IRBOARD ISOLATION VALVE i C4037-H516 TORUS WATER CLEANUP SUCTION B10 OUTBOARD ISOLATION VALVE .C4088 ..H517 DRYWELL AIR PURGE SUPPLY B10 -OUTBOARD ISOLATION VALVE 'C4089. H518' 'DRYWELL/ TORUS N2 PURGE-SUPPLY B10 OUTBOARD ISOLATION VALVE C4090 -H519 DRYWELL PURGE SUPPLY INBOARD B10 ISOLATION VALVE. C4091 H520 TORUS AIR PURGE SUPPLY OUTBOARD B10 ISOLATION VAIRE C4092 H521 TORUS PURGE SUPPLY INBOARD B10 ISOLATION VALVE C4093 .H522 DRYWELL &. TORUS N2 MAKEUP B10 OUTBOARD ISOLATION VALVE C4094 H523 DRYWELL VENT / INST'N2 SUCTION B10 INBOARD ISOLATION VALVE L i

  • T. ?

C4095 H524' DRYWELL VENT OUTBOARD ISOLATION-B10 VALVE C4096 H525 DRYWELL PURGE EXHAUST INBOARD B105 ISOLATION VALVE C4097 H526 DRYWELL PURGE EXHAUST OUTBOARD B10 ISOLATION VALVE C4098 H527 INST. N2 SUCTION OUTBOARD B10 ISOLATION VALVE C4099 H528 INST. N2 SUCTION INBOARD B10 ISOLATION VALVE C4100 H529 02 SAMPLE INBOARD ISOLATION B10 VALVES C4101 H530 02 SAMPLE GUTBOARD ISOLATION B10 VALVES C4102' H531 CAD SAMPLE INBOARD ISOLATION B10 VALVES .C4103-H532 CAD SAMPLE CUTBOARD ISOLATION B10 VALVES .04 H548 TORUS PURGE EXHAUST INBOARD B10 t'

  • ISOLATION VALVES L

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\\ g-5 7i-%. .'9:f ' H' 54 9 - TORUS' PURGE EXHAUST' OUTBOARD' B10 1p05; ' ISOLATION ' VALVES 4,o. J, <,

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bFC410,69' H550^.TQRUS VENT:INBOARDLISOLATION-B10L 1 =.. VALVES.. ' l s C4107f iH551: TORUS VENT: OUTBOARD < ISOLATION

B10 VALVE 1

l ^ t C4171.- - H477-VENTILATION VALVES BOOT SEAL D25 PART 4, 7

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A1093 H060 VENTILATION STACK RAD LEVEL B D4 PART 5/C14 (l)TOBLE GAS) A1094 TO79 UNIT VENT-STACK FLOW E4 PART 7 A1111 F000 CONDENSER PRESSURE A D28 I 'A1112 F001 : CONDENSER PRESSURE B D28 A1113 F002 CONDENSER PRESSURE C D28 LA1164 T081. DRYWELL HIGH RAD. MONITOR CH A C5/El A1173 TO61 DRYWELL HIGH RAD. MONITOR CH C C5/El A1174 T062 DRYWELL HIGH RAD.' MONITOR CH B C5/El A1175 T063 DRYWELL HIGH RAD. MONITOR CH D C5/El A1677 3000 AVG POWER RANGE MONITOR' LEVEL Ch B1 A A1678 B001 AVG POWER RANGE MONITOR LEVEL CH'B1 C l A1679 B002 AVG POWER RANGE MONITOR LEVEL CH B1 E gg.g J '11680 B003 AVG POWER RANGE MONITOR LEVEL CH B1 i B A1681 .B004 AVG POWER RANGE ' MONITOR LEVEL CH B1 - D .A1682 B005 AVG POWER RANGE MONITOR LEVEL CH B1 F A17.13 B018 REhCTOR FEEDWATER INLET FLOW A D1 A1714 B019 REACTOR FEEDWATER INLET FLOF B D1 A1715~ B020 REACTOR FEEDWATER INLET FLOW C D1 A1731 B033 RECIRCULATION DRIVE FLOW Al D30 A1732 B034 RECIRCULATION DRIVE FLOW A2 D30 A1733 B035 RECIRCULATION DRIVE FLOW B1-D30 A1734 B036 RECIRCULATION DRIVE FLOW B2 D30 A1912 M000 OFF GAS' STACK RADIATION LEVEL A C13 E4 PART 6 (NARROW RANGE) A1913 M001 OFF GAS STACK RADIATION 72 VEL B C13 E4 PART 6 .( (NARROW RANGE)

pr.= ;~: 2.... x.- w - _ xa ~ _,... REG GUIDE 1.97 POINTS FOR PEACH 2 '29 MAR 1989 PAGE 2 INPUT NO PT ID POINT. DESCRIPTION..............."RG 1.97 PARAMETER...

M006 REACTOR: BLDG SUMP AREA RAD (ARM E2
. A1018 h

' A1919, M007 ' TORUS COMPARTMENT RAD (ARM #2) E2 I A1920 .M008 HdCI ROOM RAD:(ARM #3) E2 Ai921 M009 RCIC ROOM RAD (ARM #4) E2 A1922 M010.RHR PUMP ROOM D' RAD (ARM #5) E2 A1923-M011 RHR PUMP ROOM A RAD (ARM #6) E2 A1924 M012: CORE SPRAY PUMP ROOM A RAD (ARM E2

  1. 7)

A1925 M013-REACTOR BLDG RECIRC PUMP INSTR E2 R?.CK AREA RAD-(ARM #9) 'A1926 M014 REACTOR BLDG. STEAM FLOW INSTR E2 RACK AREA RAD (ARM #10) A1928 M016 D/W EQUIP ACCESS LOCK /TIP E2 CONTROL AREA RAD (ARM #15) A1929 M017 TIP WITHDRAW AREA RAD (ARM #18) E2 .A1931 M019 NEW FUEL STORAGE AREA RAD (ARM E2

  1. 26) k.932 M020 FUEL POOL AREA RAD (ARM #30)

E2/E7 A1945 M033 CONDENSER WATER BOX #5 EFFLUENTS B2 CONDUCTIVITY A1946 M034 CONDENSER WATER BOX #6 EFFLUENTS B2 ' CONDUCTIVITY A1959 M047 OFF GAS STACK FLOW A E4 PART 8 A1967 .E032 4 KV EMERGENCY BUS 1 D25 PART 3 A1968 E033 4 KV EMERGENCY BUS 2 D25 PART 3 A1969 E034 4 KV EMERGEMCY BUS 3 D25 PART 3 'A1970 E035' EMERGENCY DIESEL GENERATOR El D25 PART 3 VOLTAGE A1971 E036 EMERGENCY DIESEL GENERATOR E2 D25 PART 3 VOLTAGE A1972-E037 EMERGENCY DIESEL GENERATUR E3 D25 PART 3 VOLTAGE A1973 E038 EMERGENCY DIESEL GENERATOR E4 D25 PART 3 VOLTAGE '74 E039 EMERGENCY DIESEL GENERATOR D25 PART 3 CURRENT El 'A--A-um._._m1...._

-. _ _... ~. - .-,-.c.- - ~... n.a. ---x ww...,u. ~,-, __; REG GUIDE 1.97 POINTS'FOR PEACH 2 29 MAR 1989-PAGE 3 INPUT NO PT ID FOINT-DESCRIPTION................ RG 1.97 PARAMETER.... ?3975 E040 EMERGENCY DIESEL GENERATOR D25 PART 3 be.Y - CURRENT E2 l A1976 E041 ENERGENCY DIESEL GENERATOR D25 PART.3 CURRENT E3 A1977 E042 EMERGENCY DIESEL GENERATOR D25 PART 3 CURRENT E4 A1980 E045-4KV EMERGENCY BUS'4 D25 PART 3 A1982 E047 125/250 VOLT DC SYSTEM 1 D25 PART 2 'A1983- 'E048 125/250 VOLT DC SYSTEM 2 D25 PART 2 A1986 F067 CIRCULATING WATER PUMP A D29 DISCHARGE .A1987 F068 CIRCULATING WATER PUMP B D29 DISCHARGE 'A1988 F069 CIRCULATING WATER PUMP C D29 DISCHARGE A3000 H000- RTR WTR LVL A (WIDE RANGE) A2/B4 DELTA-P' A3001 H001 RTR WTR LVL B (WIDE. RANGE) A2/B4 DELTA-P . gy.4 A3002 H002. RTR WTR LVL (FUEL ZONE) DELTA-P A2/B4 A3003 H003 RTR WTR LVL B (FUEL ZONE) A2/B4 DELTA-F A3004 H004 REACTOR PRESSURE A A1/B6/C4/C9 A3005 H005 REACTOR PRESSURE B A1/B6/C4/C9 A3006 H006 DRYWELL PRESSURE A-(WIDE RANGE) AS/B7/B9/C8/C10/D4 l A3307 H007 DRYWELL PRESSURE B (WIDE RANGE) A5/B7/E9/C8/C10/D4 l A3t08 H008 DRYWELL PRESSURE C (NARROW A5/B7/B9/C8/C10/D4 RANGE) A3009 H009 DRYWELL PRESSURE D (NARROW A5/B7/B9/C8/C10/D4 l RANGE) A3010-H010 DRYWELL TEMPERATURE A D7 -A3011 H011 DRYWELL TEMPERATURE B D7 l 'A3012 H012 SUPPRESSION POOL BULK (AVG.) A3/D6 TEMPERATURE A 81 3 H013 SUPPRESSION POOL BULK (AVG.) A3/D6 s TEMPERATUPI B

C =7~ _.:.._m iw_;_A _ .4_ Ja-.a. ...m.. -,,,.. ~. ~.,_.__.._.__.m- -c .4 KEG CU2DE 3.97 POINTS FORIPEACH2 '29 MAR 1989 PAGE 4 i INPUT!NO PT ID: POINT P"3CRIPTION...............'RO 1.97 PARAMETER... ' /7,2014:

H014 SUPPRESSION POOL' LEVEL A (WIDE A4/C7/D5 r

E.:e RANGE) A3015 -H015 SUPPRESSION POOL LEVEL B (WIDE A4/C7/D3 J RANGE) l 1 -A3016 H016 SUPPRESSION. POOL LEVEL A (NARROW'- RANGE) 1 A3017 H017 SUPPRESSION POOL LEVEL B (NARROW - RANGE) A3018 H018 SOURCE RANGE MONITOR CHANNEL A B1 'A3019 H019 SOURCE RANGE MONITOR CHANNEL B B1 A3020 H020 SOURCE RANGE MONITOR CHANNEL A B1 A3021 H021-SOURCE RANGE MONITOR CHANNEL B B1 A3023 H023 VENT STACK' RADIATION (WIDE C14/E4 PART 5 RANGE) ~ i A3024 H024 DRYWELL HYDROGEN CONCENTRATION C C11 A3025 H025 TORUS AIRSPACE HYDROGEN C11 CONCENTRATION A H032 STANDBY LIQUID CONTROL SYSTEM- .D17 'h, 7.026 (SLCS) FRESSURE i A3027 H042 DRYWELL HYDROGEN CONCENTRATION B C11 A3028 H043 TORUS AIRSPACE HYDROGEN C13-CONCENTRATION D "A3029 H044 TORUS AIRSPACE OXYGEN C12/A6 CONCENTRATION A A3030 H045 DRYWELL OXYGEN CONCENTRATION B C12/A6 A3031 H046' DRYWELL OXYGEN CONCENTRATION C C12/A6 A3032 H047 TORUS AIRSPACE OXYGEN C12/A6 CONCENTRATION D, A3033 H050 CONDENSATE STORAGE TANK LEVEL D2 A3034 H051 SUPPRESSION CHAMBER SPRAY FLOW A D3 m .e SUPPRESSION CHAMBER SPRAY FLOW B D3 A3035 H052 A3036 H053 HIGH PRESSURE CQOLANT INJECTION D14 FLOW A3037 H054 REACTOR CORE ISOLATION COOLING D13 FLOW J038 H055 CORE SPRAY FLOW (A&C PUMPS) D15

Tz+44aw aya...- aaa.uw4-~~a:aa:eu.:w;a -.a -.ae.::cz:::1: a=:za kREG GUIDET1.971-6PbINTSTFOR' PEACH 2 29 MAR'J.989 PAGE 5 -. ~ '? ~ fINPUT - NO PT.ID L POINT DESCRIPTION.........'...... ~ RG 1. 97 PARAMETER...- it. 039 'H056." CORE' SPRAY FLOW (B&D PUMPS) D15 43040 j' .H057 STANDBY LIQUID CONTROL TANK D18/D17 .LFVEL. .. j t ' - f 'A3041 H058-RESIDUAL HEAT REMOVAL -'A LOOP- . D 1 9, D 1 6 -- FLOW:(A&C PUMPS) ~j

A3042 H059'~ RESIDUAL HEAT REMOVAL'- B LOOP D19,D16

. FLOW (B&D PUMPS) I ^A3043 H060. RHR HX OUTLET ' TEMPERATURE- (A: D20 1 PUMP)l .j (A30441 -H061. RHR HX OUTLET TEMPERATURE (B -D20-PUMP) 'A3045-H062 RHR HX' OUTLET TEMPERATURE (C D20 PUMP) A3046. H063 _RHR HX OUTLET TEMPERATURE (D D20 1 PUMP) -A3051' H073;.El-D/G(TO E12 BUS CURRENT D25 PART 3'. A3052' H07.4

  1. 2iSU TO E12< BUS. CURRENT D25 PART 3

'A3053 H075

  1. 3 SU;.TO E12 BUS CURRENT D25 PART 3 H h..-~b54:H076 ~LE2 D/G TO.E22 BUS' CURRENT D25 PART 3-

'.A3055 : 'H085- #3 SU TO E22. BUS CURRENT-D25'PART 3 A3056' . H086 E3 D/G TO E32. BUS CURRENT D25 PART 3- -A3057 H087,#2 SU-TO.E32 BUS CURRENT D25 PART 3

A3058

.H088 ~ #3SU TO E32 BUS: CURRENT D25 PART 3 "l'A3059 H089-E4 D/G TO E42-BUS CURRENT D25 PART 3 A3060 'H090-

  1. 2 SU TO E42 BUS CURRENT D25 PART 3

-A3061 H091

  1. 3 SU TO E42 BUS CURRENT D25 PART 3

,5A3062' H109-24 VDC BUS PANEL 2AD45 VOLTS D25 PART 2 7A3063 H110 24 VDC BUS PANEL 2BD45 VOLTS D25 PART 2 l LLA3064- . H112-. RBCCW PUMP AREA RAD (ARM #11) E2 Li A3065 'I1115 REACTOR BLDG NEAR PERSONEL D/W E2 > ACCESS- (ARM #16) .A3 0661 H116 REACTOR BLDG SE STAIRWELL ELEV E2 135:(ARM'#17) ..t H119 REACTOR BLDG SAMPLE SINK ELEV E2 AJ067-i- _-_.-.s

p u.sa 4,_x. a ...au_;= __;;-aa; ,.a u.a.a.u,c-, .a .._..-..u_2. -- x __. '. REG. GUIDE 1.97-POINTS'FOR PEACH 2 29 MAR 1989 PAGE' 6 . INPUT NO PT.ID POINT DESCRIPTION............... RG 1.97 PARAMETER... 'l .165 RAD (ARM #21) 028-H120 REACTOR BLDG STAIRWELL ELEV 165 E2 RAD (ARM (22) A3069 H123 F b ROOM ELEV 195 AREA RAD (ARM E2 j

  1. 27)
A3070 H124 STEAM SEPARATOR POOL AREA RAD E2/E3 l

(ARM #28) j A3071 H125 REACTOR REFUEL SLOT AREA RAD E2 I (ARM'#29) A3072 H126 REFUELING BRIDGE AREA RAD (ARM E2

  1. 31)

A3074 H131 SOURCE STORAGE & CALIB ROOM RAD E2' (ARM #45) .A3076 H150 UNIT VENT STACK FLOW B E4 PART 7 A3083 H170 TURBINE BYPASS VALVE POSITION D26 PART 10 A3084 H171 CONDENSER HOTWELL LEVEL A D27 l A3085 H172 CONDENSER HOTWELL LEVEL B D27 l A3086 H173 CONDENSER HOTWELL LEVEL C D27 (r.O 88 H175 VOLTAGE TRANSDUCER TO OUTPUT OF D25 PART 1 20Y50 PANEL A3089 H176

  1. 2 SU TO E22 BUS CURRENT D 25-PART 3 B8fC6

'A3173 H037.DRYWELL FLOOR DRAIN SUMP LEVEL A3181 H030 CAD LIQUID N2 TANK LEVEL D25, PART 6 'A3184 H035 DRYWELL EQUIPMENT DRAIN SUMP B8,C6 LEVEL A3195 H178 LONG TERM ADS N2 SUPPLY A Y l l A3196 H179 LONG TERM ADS N2 SUPPLY B Y A3199 H113 HPCI TURBINE CASING #1 TEMP A3200 H114 HPCI TURBINE CASING #2 TEMP A4022 H022 OFFGAS STACK RADIATION (WIDE C13/E4 PART 6 l RANGE) A4047 H064 RAD WASTE COLLECTOR TANK LEVEL D23 A4048 H065 RAD WASTE SURGE COLLECTOR TANK D23 LEVEL ( '4 9 H066 FLOOR DRAIN COLLECTOR TANK D2J l l L

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,9 REG GUIDE?l,97 POINTS FOR PEACH 2 29 MAR 1989= .PAGE 7-M INPUT-NO-PT ID-POINT DESCRIPTION. '~RG-1.97 PARAMETER... , y _. iA405fr H067.. FLOOR DRAIN SURGE TANK, D23 075/ ' H147,10FFGASESTACK FLOW-B E4 PART-8 i-A40810 1H155 iEMERG SERVICE WATER PRESSURE D22, 21 l A4082 :- H156: EMERG SERVICE WATER PRESSURE D22, 21 A40'92. H234 'EMERG SERVICE' WATER TEMP A-D21,22 i.LlA4d93 'H235 EM2RG SERVICE WATER TEMP B-D21,22- ~A4175; H163 EMERGENCY DIESEL GENERATORS AIR-D25 PART 10: . START SUPPLY B JA4176- 'H165 EMERGENCY DIESEL' GENERATORS AIR D25 PART 10 START SUPPLY.D .A4177 .H167 EMERGENCY DIESEL GENERATORS AIR D25 PART 10 . START' SUPPLY B ^A4178 H169. EMERGENCY DIESEL GENERATORS AIR D25'PART 10 START SUPPLY D: A4186? H162: EMERGENCY DIESEL GENERATORS AIR D25 PART 10 START' SUPPLY A A4187 -H164- ' EMERGENCY DIESEL GENERATORS AIR D25 PART 10 START SUPPLY C 188 -H166.. EMERGENCY DIESEL GENERATORS AIR.xD25.'PART 10 !~ . START-SUPPLY'A LA4189 .H168~'i_MERGENCY DIESEL GENERATORS AIR D2S:PART 10 ' START SUPPLY C a.

C1142 1M509lNSTRUMENT-AIR HEADER.A-LOW D25 PART 9

. PRESSURE LC1145 M512'" INSTRUMENT. AIR HEADER B LOW D25 PART 9 . PRESSURE

C1199~

M566; RESIN DEWATER FACILITY LINE BREAK C1585 D569 RV2-71A VALVE POSITION D10 INDICATION C1586 'D570- RV2-71B VALVE POSITION D10 I INDICATION fC1587. D571 RV2-71C VALVE POSITION D10 INDICATION .C1588 D572 RV2-71D< VALVE POSITION D10 ' INDICATION c'589 'D573, RV2-71E: VALVE POSITION D10 ( INDICATION i l y m -- l-

,- r m 3 ypi 29 MAR 1989 ~ PAGE 8. REG. GUIDE 1.97-POINTS.FOR. PEACH 2' -(INPUT >No.PT ID FOINT DESCRIPTION................ RGi1.97-PARAMETER... C15d0; JD574, RV2-71F VALVE POSITION D10 m INDICATION' ( _ U.A < D10 2 ,1

C1591?

!D575 :RV2-71G VALVE POSITION ~ I)iDICATION'y .cy C1592 D576. RV2-71H VALVE POSITION D10 g 1 . INDICATION D10 ~ C1593: D577 JRV2-71J. VALVE POSITION-INDICATION: '!C1594 D578 'RV2-71K VALVE POSI' ' ION - D10 .E INDICATION C1595- .D579' RV2-71L: VALVE. POSITION' D10 INDICATION. n. p;:C1596.: .D580 : MAIN STEAM RELIEF VALVE AM D10 POSITION INDICATION SV-A EC1597- - D581 - MAINLSTEAM.' RELIEF VALVE AM D10 ' POSITION. INDICATION.SV-B I.C1801 Z500 CONTROL' ROD SELECT ' B2 l> C1802 Z501-CONTROL ROD' SELECT B2 ,..C1803' Z502 CONTROL' ROD SELECT B2 - j 04 Z503' ' CONTROL ROD SELECT B2 - C1805 2504 CONTROL ROD SELECT B2 1 C1806-2505.'~ CONTROL ROD SELECT B2 p - 4 =C1807 Z506 CONTROL ROD SELECT B2 C1808 Z507 CONTROL ROD SELECT B2 C1810-Z508 CONTROL ROD POSITION XO B2 C1811 Z509 CONTROL ROD POSITION X2 B2 iC1812' 'Z510- CONTROL ROD POSITION X4 B2 .q 4 C18131 Z511 CONTROL ROD POSITION X6 B2- }C1814. 2512 CONTROL ROD POSITION X8 B2 C1815 Z513 -CONTROL ROD POSITION TENS OX B2 C1816 Z514 CONTROL ROD POSITION TENS 1X B2 C1817; Z515 CONTROL ROD POSITION TENS 2X B2 C1818' Z516 CONTROL ROD FOSITION TENS 3X B2 , G)19. - Z517. CONTROL ROD POSITION TENS 4X B2 p: pg L v l: ^ =1.-

pm.:, - + - ~ -. x- .= w -x2. y. <jch ] .c 1 n.. REG. GUIDE'1.97 POINTS FOR PEACE 2 j 29 MAR 1989 PAGE 9 ,7 INPUT NO PT ID POINT DESCRIPTION............... RG 1.97:. PARAMETER... s i fvC3000. !H026 -SRM' PROBE POSITION A B1 i) 01 H027 SRM PROBE POSITION B Bl. ' f C3002 - 'H028 -SIJM; PROBE POSITION C B1 - 1 ]

u.

~C3003 H029 SRM PROBE POSITION D,. Bl~ C3025 H092 REFUEL FLOOR EXHAUST DUCT D24 OUTBOARD ISOLATION DAMPER-1 C3026 E093 REFUEL FLOOR INLET DUCT INBOARD D24 -ISOLATION DAMPER C3 027 '- H094 REACTOR BUILDING EXHAUST DUCT. D24 l OUTBAORD ISOLATION DAMPER ~C3028-H095 REACTOR: BUILDING INLET DUCT D24. . INBOARD ISOLATION DAMPER. I 'C3029 H096 REACTOR BUILDING EQUIPMENT CELL D24 I EXHAUST OUTBOARD ISOIATION 1 1 DAMPER 'C3030-H097 'DRYWELL' PURGE SUPPLY INLET D24 j ' INBOARD' ISOLATION DAMPER C3031 H102' REFUEL FLOOR EXHAUST DUCT D24 INBOARD. ISOLATION DAMPER { 'dU32 i H103- ' REFUEL FLOOR =INIET DUCT OUTBOARD D24 ISOLATION DAMPER-i

C3033.

H104 REACTOR BUILDING EXHAUST DUCT D24'. INBOARD ISOLATION DAMPER. p C3034 H105 REACTOR BUILDING INLET DUCT D24 i OUTBOARD ISOLATION DAMPER .C3035L .H106_ REACTOR BUILDING EQUIPMENT CELL D24 1 EXHAUST INBOARD ISOLATION DAMPER C3036' H108.DRYWELL PURGE SUPPLY INLET D24 OUTBOARD ISOLATION DAMPER 'C3040' H157', INST; N2 A-SUPPLY PRESS D25 PART 9 1 . -C3041' H158 INST. N2 B SUPPLY PRESS D25 PART 9 y ~ C3052-H180 MAIN STEAM INBOARD ISOLATION B10 VALVE A 1 "C3053- !H181 MAIN STEAM INBOARD ISOLATION B10 -) . VALVE B j C3054 H182' MAIN STEAM INBOARD ISOLATION B10 VALVE C . (' )55 H183-MAIN STEAM INBOARD ISOLATION B10 VALVE D 4 i L __.____.__m..___

y= =, 9-w ; az aux.

u. -

ym ). 29 MAR l1989 'PAGE 10 h_;REGCUIDE1.97EPOINTS-FOR.~ PEACH 2l INPUT-NO PT ID POINT DESCRIPTION............... RG 1.97 PARAMETER.... p '?'156 H18'4 MAIN STEAM OUTBOARD ISOIATION D10 ' i hp .VALyn A- .C3057-H185 'MSIN STEAM OUTBOARD' ISOLATION. B10 VALVE B C3058 H186 MAIN STEAM OUTBOARD ISOLATION B10 VALVE C 'C3059-H187 MAIN STEAM OUTBOARD ISOIATION B10 VALVE D 'C3060 -H188 MAIN STEAM. DRAIN INBOARD B10 ISOIATION VALVE C3061 H189 MAIN STEAM DRAIN OUTBOARD B10 ISOLATION VALVE C3062 51190 RECIRC. LOOP SAMPLE INBOARD B10 ISOIATIO1; VALVE

  • C3063

-H191 RECIRC. LOOP SAMPLE OUTBOARD B10 ISOLATION VALVE C3064 H192 ' MAIN STEAM SAMPLE INBOARD B10 ISOLATION VALVE

C3065 H193 MAIN STEAM SAMPLE OUTBOARD B10 ISOLATION VALVE

. g; .C3066 H194 FEEDWATER-LONGPATH RECIRC. B10 ISOIATION C3067 H195 RWCU RETURN:ISOIATION VALVE B10t C3068 H196 FEEDWATER - LONGPATH RECIRC. B10 ISOIATION C3069 H197-RHR SHUTDOWN COOLING SUCTION B10 OUTBOARD ISOLATION VALVE C3070 H.9 8 RHR SHUTDOWN COOLING SUCTION B10 INBOARD ISOLATION VALVE C3071 H199 RER SHUTDOWN COOLING RTN & LPCI B10 INJECT A ISOLATION VALVE C3072 H200 RHR SHUTDOWN COOLING RTN & LPCI B10 INJECT B ISOLATION VALVE 03073 H201 RWCU PUMP SUCTION INBOARD B10 ISOIATION VALVE C3074-H202.RWCU PUMP SUCTION OUTBOARD B10 ISOLATION VALVE H203 RHR HEAD SPRAY INBOARD ISOLATION B10 [ m075 VALVE

mr7[=~ a pg :2 ;;;w:. _p z.a.x_x. - ~ [ W REG' GUIDE.1;97 POINTS'FOR PEACH 2.

29--MAR 1989.

PAGE.11 h ; INPUT NOf PT ID ' POINT DESCRIPTION.......... '..... ' RG 1. 97 PARA + ,. ii. biC3076 H204 RHR. HEAD SPRAY OUTBOARD B10 -ISOLATION VALVE f,p l (7(C3077; LH205. DRYWELL FL..DR. INBOARD B10 ~ IjiOLATION VALVE C307'8 < H206 DRYWELL'FL. DR.- OUTBOARD B10 ~ 1 - ISOLATION VALVE , KC3079' H207 DRYWELL' EQUIP. DR.LINBOARD 'B10 h ISOLATION : VALVE l cy_ x /; C3080 H208 'DRYWELL EQUIP. DR. OUTBOARD B10 ISOLATION VALVE I C3081 H209L INST. N2 D/W HEADER!A ISOLATION B10 VALVE t C3082: H210 TIP ISOLATION .B10 j

C3083 H211 TIP PURGE ISOLATION VALVE B10

[(C3084 ,H212L INST. N2 D/W. HEADER B ISOLATION B10 ' VALVE ._.i C3085 H214 INST. N2 TORUS ISOLATION VALVE B10 TORUS WATER CLEANUP SUCTION B10-b LC3086 H215 INBOARD ISOLATION VAVLE o. ;n.- H216-TORUS WATER CLEANUP SUCTION B10 1 ;J87' OUTBOARD ISOLATION VALVE IC3088'- H217 DRYWELL AIR PURGE SUPPLY B10 OUTBOARD ISOLATION VALVE g~,. 4

C3089 H218 DRYWELL/ TORUS N2 PURGE SUPPLY B10 OUTBOARD ISOLATION VALVE

'C3090 H219 DRYWELL PURGE SUPPLY INBOARD B10 ISOLATION VALVE C3091 H220 TORUS AIR' PURGE SUPPLY OUTBOARD B10' ISOLATION VAVLE 'C3092 H221 TORUS PURGE' SUPPLY INBOARD B10 ' ISOLATION VALVE C3093 H222 DRYWELL & TORUS N2 MAKEUP B10 OUTBOARD ISOLATION VALVE 'C3094 H223 DRYWELL VENT / INST N2 SUCTION' B10 INBCARD ISOLATION VALVE iC3095' 'H224 DRYWELL VENT OUTBOARD ISOLATION B10 VALVE M 096" H225 DRYWELL PURGE EXHAUST INBOARD B10 ISOLATION VALVE

y9m=.p:.w.4.ma.. a w+ :;=aw+.:=.w. ~ : -.

a a.
..+.,.

-.,a ,#p s:n _ > w itN' & IUjREGiGUIDE 1.9ffPOINTS FOR:PBACH21 29.: MAR 1989^

PAGE 12.r d

E l% INPUT,NO-PTLIDzPOINT: DESCRIPTION.............. 1RG 1.97 PARAMETER...' 'i p/C3097/ SH226: DRYWELL' PURGE EXHAUST OUTBOARD B10. T ".Md ' ' '. ISOLATION LVALVE. 4 4 b : tih ~

B10-I;.: C3098'

'H227-l INST.;N2" SUCTION OUTBOARD-L.. IyOLATION VALVE [j 1 -C30991 -H228! ; INST. N2 SUCTION INBOARD-B10- --ISOLATION VALVE' x w iC310 H229;./O2[SAMPLEIINBOARD ISOLATION.- B10 VALVES 1 n ' C3101'- H230' 02 SAMPLE OUTBOARD ISOLATION

B10 VALVES

.*;C3102 ~H231-CAD SAMPLE-INBOARD ISOLATION B10 VALVES

C3103-H232. CAD SAMPLE OUTBOARD ISOLATION

.B10 . VALVE C51041 .H248 TORUS PURGE EXHAUST'INB ARD-B10~ . ISOLATION, VALVES C310'51 H249 TORUS PURGE EXHAUST OUTBOARD B10 ~ a -ISOLATION. VALVES- .i iC3106 .H250 TORUS VENT INBOARD. ISOLATION-B10. VALVE. [. %...:.- 07-H251!: TORUS VENT OUTBOARD ISOLATION B10 '. VALVE -

C3171' J
H177-VENTILATION VALVES BOOT SEAL D 25-LPART 4, 7

l PRESSURE p- ..y t i E a

ATTACHMENT 7 EXISTING PBAPS TELECOMMUNICATIONS NETWORK

n y :a w..: - a.-. -. - - \\ ,w b

.?

l 1: ATTACH MENT COMMUNICATIONS PATHS i VIA DELTA CENTRAL OFFICE PEACH BOTTOM ~ EOF (EXISTING) DELTA C.O. A SINGLE AERIAL CABLE BETWEEN 120 PUBLIC TRUNK LINES DELTA AND RED LION 24 PRIVATE PECo TRUNK LINES RED LION C.O. 1 l PUBLIC SWITCHED TELEPHONE NETWORK l l INFORMATION PROVIDED BY GTE j I 1

q ATTACHMENT 8 I COATESVILLE EOF TELECOMMUNICATIONS NETWORK l

s. S E A E C I N ~ H I N E P L AT K L I S AC E O. I R K C D N M D I A U O I C VF L R G W F I T N H O T S O P 4 L S 2 E H CE N IL N TL BL E I AA U K N P R N O P 4 U 4 t H S T E ) L D R L P 1 N N L E T I . S I E L O E VF V L O S O S O. E C E P E C T E I T T O TA A R S O D AE O P CE C E CL C IL N ( H I L BL I C NI U T K P U V N I 8 U W S M 6 R E T S S 1 E MT N N S C O I E OA I L N L T T I TG CO K R N O. N & L B U OI C FH C U T G S R A N P A T O W L 8 4 1

7-- l ATTACHMENT 9 LETTERS OF CONCURRENCE FROM GOVERNMENTAL AGENCIES f l

pl,.. T V' ~" ~ "N .a p QN,.. 1l e aq RECEIVED d3 COMMONWEALTH OF PENNSYLVANIA 1 u DEPARTMENT OF ENVIRONMENTAL RESOURCES b ISO 9 PEN NSYLVANI A, Post Office Box '2063 Harrisburg, Pennsylvania 17120 F. E.WElGAND Bureau of Radiation Protection l (717) 787-3479 i I Frank Weigand Director, Emergency Prepared' ness Section3 Nuclear Support Division ~ Philadelphia Electric Co. 2301 Market St. Philadelphia, PA 19101 Dea'r Mr. Weigand: In accordance with your request of February 14, 1989, enclosed'please find your form indicating my acceptance of the location of a joint EOF for Peach Bottom and Limerick, at Coatesville. Please call if questions arise. Sincerely, i) Marcaret A. Reilly, C ief Division of Environmental Radiation I = _ _ _ _ _ _ - - _ _ _ _ _ _ _ - _ _ _ _ _.

p52-

2
:x: z ;;.i

.. -.~a-. w. a., -a--..=... -..:~...--.~.~..--.:---

.: =--

,. L4B-15-!89 15257; ID:PE CORP ElERG PREP TEL NO2215-842-5114

  1. 246 P03 f

t jh s iI y"v. .'. 'c p s,.. ~" I understand that Philadelphia Electric Company (PECo)' is planning an Emergency Operations Facility (EOF) at _ Coatesville, Chester County Pennsylvania, that will serve'the Limerick Generating Station and Peach Bottom Atomic Power . Station. It will replace the current EOF's located at Philadelphia Electric's Plymouth Service Building and the Unit 1 ' Administration Building at Peach Bottom. PECo has coordinated this: proposal-with our agency and, based upon these discussions, I concur with the location chosen for the EOF. NO# N NAME: SIGNATURE: GA.L /4'N v. W-01 AT/OO TITLE: OV/66 AGENCY: A DAIAUCE W i m

i A.krr./ . RECElVED. ^ ' g y,lY' FEB 241989 S1 ate Or M:.av'^"o ' DEPARTMENT OF PUBLIC SAFETY AND CORRECTIONAL SERVICES . r.,. :, F.E.WEIGAND WILLIAM DONALD SCHAErER t DAVID MCMILLION 00ve ngo* j DIRECTOR

MELVIN A STEINDERG /.

[ o oovis g ~*j O$ HOP LL RODINSON sacat taav MARYLAND EMERGENCY MANAGEMENT AND CIVIL DEFENSE AGENCY P SUDBROOK LANE. EAST PIKESVILLE, MARYLAND 21208 (301) 486 44?? TTY FOR THE DE AF. 484 4083 February 21, 1989 Mr. Frank Weigand, Director Emergency Preparedness Section Nuclear Support Division Philadelphia Electric Company 2301 Market Street P.O. Box 8699 . Philadelphia, Pennsylvania 19101 =

Dear Mr. Weigand:

' Reference -your letter of February 14, 1989 requesting accep-tance' confirmation of the Coatesville location for the new Emer-gency Operations Facility (EOF) and news media center for the PBAPS. The State of Maryland concurs with your proposal and our formal concurrence is enclosed as requested. If you should have any questions, please contact Ed Tremper at-(301) 486-4422. Sincerely, I. h 3 MC ILL' ION - N ~ Director 'I DM:EOT:sif

Enclosure:

a/s 1 1

-. ~,, L ry%,, y-c _I understand that Philadelphia Electric Company (PECo)fis~planninganEmergencyOperationsFacility(EOF)at Coatesville, Chester County. Pennsylvania, that will serve the Limerick Generating Station and Peach Bottom' Atomic Power 5 -Station. It'will-replace the current EOF's located at Philadelphia Electric's Plymouth Service Building and the Unit 1 Administration Building a't Peach Bottom. PECo has coordinated this proposal with our-agency and, based upon these discussions, I' concur with the location chosen for the E0F. .NAME: DAVID MCMILLION SIGNATURE:. l l l l TITLE: DIRECTOR AGENCY: MARYLAND EMERGENCY MANAGEMENT AND CIVIL DEFENSE i l ADDRESS: 2 SUDBROOK LANE, EAST PIKESVILLE, MARYLAND 21208 g{. February 21, 1989 l l l L-

-m i,, + x u si LFederal Emergency Management Agency j 7, g i a, 1 f. Region III Liberty Square Building (Second Floor) j 105 South Seventh Street - j . =, 4~ 1;. Philadelphia, PA 19146 -l q ( \\ m- 'Mr.'Ron Harper. , Philadelphia Electric Co. -2301 Market Street P'.0.. Box 8699' i. ~ Philadelphia, PA 19101l l w

Dear Mr. Harper:

Thank~you for-the courtesy of allowing me to review the: floor ~ . plans-for your proposed nuclear emergency operations facility 'and news center. To my knowledge, there is no requirement that FEMA review or approve.such construction. _The plan appears, at' this time, to be adequate to meet the JIC guidance as ' set ' forth in NUREG 0654/ FEMA REP-l'and subsequent FEMA revisions and instructions. Sincerely, l f k Hugh Laine Public Information Officer 4 w-__

ry 7- - c l p;ECEIVED D.R 11989 i F.E 73!GAND I I understand that Philadelphia Electric Company (PECo)'is planning an Emergency Operations Facility (EOF) at I Coatesville, Chester County Pennsylvania, that will serve the Limerick Generating Station and Peach Bottom Atomic Power Station. It will replace the current E0F's located at Philadelphia Electric's Plymouth Service Building and the Unit 1 Administration Building at Peach Bottom. PECo has coordinated this proposal with our agency and, based upon these discussions, I concur with the location chosen for the E0F. f r NAME: '1 ct A / SIGNATURE: Joseph LaFleur Director TITLE: AGENCY: Pennsylvania Emergency Management Agency ADDRESS: s x 3321, Harrisburg, FA 17105-3321

p g.7.w + .a + m __. # .._ - m.- ... A.:-._u._ _._c. m _ _ - g % $:;e,x, lFEB-15 '8916:08"? ID:PE CORP Et1ER PREP: TEL HO:215-841-5,114 ft249 P03 n-p ff:' h 9- ~ ): . I understand that Philadelphia Electric Company .(PECo)fisplanning.anEmergencyOperationsfacility--(E0F)at- ]' Coatesville,'Chester County Pennsylvania,;that will serve the ,~ *, Limerick Generating. Station and Peach Bottom Atomic Power i m Station-It will replace.the' current EOF's located at I . Philadelphia' Electric's Plymouth Service Building-and the Unit 1-i m .l Administration. Building at Peach Bottom. PECo has' coordinated this' proposal with our; agency and, based upon these discussions, I concur with the. location ~ chosen for the EOF. kE i q j r ls l ~ :l ,} NAME:. Roland G. Fletcher j j ) SIGNATURE: ./ J l J .o if TITLE: uministrator.: center for naainimical Health 1, -l-AGENCY: Maryland Department of the Environment ADDRESS: 2500 Broening Highway, Baltimore, Maryland 21224 m___._____________.___-._--.__._._._ - - _ _ _. -. _ _ _ _}}

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