ML20059B075

Forwards Rev 0 to Updated FSAR for Limerick Generating Station,Units 1 & 2,Vols 1-19.W/one Oversize Encl. Proprietary Vol 7A (App 3B) Withheld (Ref 10CFR2.790)

ML20059B075
Person / Time
Site:	Limerick
Issue date:	08/24/1990
From:	Helwig D PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19307A494	List: ML20059B075
References
NUDOCS 9008280047
Download: ML20059B075 (8)

Text

" 10CFR50.71(e)(3)(1)'

E 10 CFR 50.54(a)(3) c > PHILADELPHIA ELECTRIC COMPANY- 1 NUCLEAR GROUP HEADQUARTERf 955-65 CHESTERBROOK BLVD.

~~

WAYNE. PA 19087 5691 (at s) s40 esso

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. August 24, 1990 1

Docket Nos.-50-352 50-353 License No. NPF NPF r L

U.S. Nuclear Regulatory Commission

. ATTN: Document Control Desk

-biashington. D.C. 20555 30BJECT: Limerick Generating Station Units 1 and 2 Submital of Revision 0 of the Updated Final Safety Analysis Report

REFERENCES:

1) Letter from E. J. Bradley (PECO) to H. D. Denton (NRC), " Amendment No. 35 to the License Application for Limerick Generating Station Units-1 and 2." dated June 30, 1982

2) Letter from G. A. Hunger, Jr.- (PECo) to the b NRC, " Changes to the Quality Assurance Program Gescription for Limerick Generating Station, Units 1 and 2," dated November 22, 1989 Gentlemen:

In accordance with.10 CFR 50.71(e)(3)(1) and 10 CFR 50.4(b)(6), this-letter submits one original and ten (10)' copies of the initial (i.e., Revision 0)

Updated Final Safety Analysis Report (UFSAR) for Limerick Generating Station

(LGS), Units 1 and 2. The enclosed UFSAR also contains a revised Quality Z Assurance Program Description which is being submitted in accc, dance with 10 CFR 50.54 (a)(3). Philadelphia Electric Company (PEco) has been in compliance with r the Final Safety Analysis Report (FSAR) update requirements of 10 CFR 50.71(e) since October, 1986-(1.e., 24 months after receipt of the Unit 1 operating

. license), starting with the submittal of Revision 49 to the LGS, Units 1 and 2

-FSAR by our letter dated June 30, 1987. However, as explained below, the-enclosed UFSAR is a complete and new document, incorporating the information from the LGS, Units i and 2 FSAR, through Revision 58, and including changes i made to the station up to January 1, 1989.

47 900824 Y /Mb N pp2g@CK0500o352 ,

II PDC

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, Document Ctntrol Desk August 24, 1990 g , . , ,

Page 2

. Our letter dated February ll, 1986, as supplemented by our letter dated

' July 28, 1986, requested a schedular exemption from the requirements of 10 CFR 50.71(e) for LGS, Unit 1. Since Unit 2 was still under construction at that time, we requested an exemption allowing the initial UFSAR to be submitted 12 months following the issuance of the Unit 2 operating license. The NRC responded to this request by letter dated December 8, 1987, stating that there was no need for an exemption. This conclusion was based on the determination that the periodic revisions to the LGS, Units 1 and 2 FSAR which we were submitting in accordance with 10 CFR 50.34(b), and our comalteent to include changes to Unit 1 in these FSAR revisions, satisfied the FSAR update  !~

requirements in 10 CFR 50.71(e). Accordingly, we continued to submit periodic revisions to the FSAR during the completion of construction of LGS, Unit 2.

These revisions reflected changes up to a maximum of six months prior to the submittal date and therefore satisfied the requirements of 10 CFR 50.71(e)(4) for Unit 1.

Operating license NPF-83 was issued for Unit 2 on June 22, 1989, and the I last FSAR revision (Revision 58) was submitted to the NRC by letter dated June 29, 1989. This revision included changes made to Unit 1 in accordance with the provisions of 10 CFR 50.59 up to January 1, 1989. Upon issuance of FSAR Revision 58, we initiated preparation of the initial revision of the LGS, Units I and 2 UFSAR as a complete and new document. Submittal of Revision 0 of the UFSAR has been delayed past June 30, 1990, 12 months after submittal of the last FSAR revision, due to the substantial number of sequential tasks that must be accomplished in order to create a complete and accurate UFSAR. 1 We also request that Volume 7A (i.e., Section 38) of the enclosed UFSAR be <

withheld from public disclosure 6s proprietory information in accordance with 10  :

CFR 2.790(a)(4) for the reasons stated in the application and affidavit submitted by Pennsylvania Power and Light Company and cited in the Reference 1 submittal.

This initial UFSAR has been prepared in accordance with 10 CFR 50.71(e) and the guidance provided in NRC Generic Letter 81-06, " Periodic Updating of the j

Final Safety Analysis % ports (FSARs)." dated February 26, 1981, to include the following.

1. Provision of an initial UFSAR that is a clean document without change bars or revision numbers.

2. Incorporation of the appropriate portions of PECo responses to NRC FSAR questions into the body of the initial UFSAR.

In addition, the following changes have been incorporated into the initial UFSAR.

1. The Fire Protection Evaluation Report (FPER) for the LGS, Units 1 and 2 was included in Section 9A of the UFSAR.

2. The non-proprietary Design Assessment Report (DAR) for the LGS, Units 1 and 2 was included in Section 3A of the UFSAR.

i,

, Document Control D3sk August 24, 1990-Page 3 3.- The proprietary DAR:for LGS, Units 1 and 2 was included in Section'38 of the UFSAR.

4. The initial UFSAR incorporates a number of editorial changes. These changes were to correct spelling and typographical errors; to correct references to UFSAR sections, tables = figures, or table of contents; to improve grammar or clarity without changing meaning; to move i information to more appropriate locations; or to make certain UFSAR-sections consistent with other UFSAR sections.

5. The UFSAR reflects changes made to LGS, Units 1 and 2. .nder the provisions of 10 CFR 50.59, up to January 1, 1990.

6. The Quality Assurance Program Description (i.e., Section 17.2-of the UFSAR) reflects editorial and organizational changes and also includes changes described in Reference 2. These changes are- i submitted in accordance with 10 CFR 50.54(a)(3) and do not reduce the  ;

cossaiteents in the Quality Assurance Progsas Description previously i accepted by the NRC.

As required by 10 CFR 50.71(e)(2)(i), I certify that to the best of my knowledge, the initial UFSAR accurately reflects information and analyses-submitted to the NRC, or prepared pursuant to NRC requirements since the submittal of Revision 58 to the FSAR, Revision 12 to the FPER, and Revision 11 to the DAD - Also,asrequiredby10CFR50.71(e)(2)(ii).theAttachmenttothis letter identifies changes made under the provisions of 10 CFR 50.59 and included in the enclosed UFSAR. Revision 0, but not previously submitted to the NRC.

If you have any questions, or require further information, please contact us.

Very truly yours,

~

1 Attachment Enclosures cc: T. T. Martin, Administrator, Region 1. USNRC (2 copies)

T. J. Kenny, USNRC Senior Resident Inspector, LGS

l r ,.

ATTACHMENT Page 1 of 5 Changen - made under 10 CFR 50.59 - covered by Revision- 0 of the-Limerick Generating Station, Unite = 1 and 2 Updated - Final Safety Analysis Report, but not previouslyi submitted to the ' NRC, are, identified below.

Modification Number Description 0036 Unit 1,and Common '

Addition of flow control' valves for Perkiomen Creek makeup system..  ;{

1 0194 Unit 1 - Modification to extend and reroute service water high point vents.

1 0208 Unit 1 -

Addition of high and- low differential pressure switches and time delay l relays to the refueling area ventilation 1 system.

0365 Unit 1- Installation of a closed loop seal t

water blower unit.

't 0400 Unit 1 -

Installation of a roof ventilation- 1 exhaust fan for plant heating condensate pump , .

room.

0471 Unit 1 and Common - Relocation of new fuel >

inspection stand. e L

0502 Unit 1 -

Replacement of the atmospheric chlorine detection system and modification of the control room high ' chlorine isolation logic.

0558 Unit 1 - Addition of a redundant' level switch for the high integrity container- fill equipment.

0648 Unit 1 -

Modification - to the cooling tower acid feed system necessary for the installation of the cooling tower treatment system.

0794 Unit 1 and Common -

Upgrades the present ,

emergency evacuation site alarm / announcement coverage inside the power block.

0796 Unit 1 and Common - Revises the control logic for the condensate transfer pumps.

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g Attachment Page'2 of 5

' 0801 Unit 1 - Addition of test connections upstream -.

and -downstream iof- excess- ~ flow- check valves-located in various: systems' instrument sensing!

' lines.

~ 0857 Unit 1:- Extension of- the existing fire suppression deluge systems .for the isophase bus ducts and supporting steel associated with .

the main and auxiliary transformers. '

0863 Unit. 1 - Extension of the- existing fire suppression sprinkler systems for - .the main

~ '

condenser area.

0940 Unit 1 -

Addition of ~ computer monitoring I- capability for suppression pool 1 air l temperature.

0996 Unit 1 - Removal' of reactor enclosure supply and refueling floor supply system: low flow instrumentation.

5007~ Unit 1 - Replacement of feedwater heater level' controllers and revision'of'feedwater-heater level setpoints.

5014: Unit 1 and Common -

Expansion ~'of health 2

physics and related facilities.

5027 Unit 1 -

Addition of visual and audible indication for air lock door and refueling floor hatch.

5060 Unit 1 - Addition Lof unions on the primary ,

containment instrument gas desiccant dryer discharge piping.and modifies power supply.

.5061 Unit 1 - Modification, provides redundant-instrument air for the traversing incore probe drive mechanism.

- 5062- Unit 1 -

Mcdift atien provides vent .

connections for the primary containment instrument gas receivers.

5063 Unit 1 -

Modification provides reactor i enclosure cooling water for the primary containment instrument gas compressors and aftercoolers cooling.

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. Attachment Page 3 of 5

- 5065 Unit 1 - Rerouting of the preheater tubeside vent for the. gaseous- radweste' recombiner-  ;

system.

r

- 5108- Unit Modification ~ to the process radiation .;

monitoring rack.

5119 Unit'l ~and Common Addition- of permanent 3 ozone injection piping to the floor drain collection tank.

5133 Unit 1- Modification to the residual heat -

removal pump compartmenc unit coolers piping- 1 o and valves. l 5145 Unit 1 and- Common -

Control rod drive  !

- decentamination and- temporary repair .

facilities.. ]

5203 Unit 1 -

Addition of high level switch to.

condensate storage tank.

J i

5282 Unit 1 -

Relocation. of the high pressure d condenser vacuum sensor / transmitter. l l

5291 Unit 1 -

Addition of remote manual valve operators.

5301 Unit 1 -

Turbine enclosure- equipment compartment exhaust system filter bypass.

5323 Unit 1 - Replacement of the water treatment building normal waste sump discharge piping.

5551 Unit 1 - Modification provides various steel attachments to the existing steel structure in I the control structure and reactor enclosure areas to support special maintenance activities.

5561 Unit 1 -. Identification of additional detail to the instrument air system drawings.

5660 Unit 1 - Addition of pitot tube taps in ' the l

-circulating water condenser supply lines. l l

5704 Unit 1 and Common - Modification provides a new source of water for site dust control from l the spray pond makeup line.

Attachment Page of 5  :

5705 Unit 1 and- common - Addition of air conditioning units for the: counting room.

5716 Unit 1 - Modification revises residual heat-removal system annunciators.

5725 ~ Unit 1 and- Common ~ - Modification reroutes a sample sink drain from an oily waste drain to ,

a normal waste drain. -

-5729 Unit 1 - Prov' ides permanent heat trace for the f spray pond sump pump _ discharge lines.

5732 Unit 1 -

Addition of a high differential' pressure alarm to the c .iensate system.

5780 Unit 1 -

Modification revises recirculation ~

pump control logic.

5819-1 Unit 1 - Relocation of alternate power supply for static inverter.

l 5844 Unit 1 - Addition of new' office enclosure on ,

L the turbine operating deck. I 5910 Unit 1 - Modification deletes the rod sequence  ;

l control system and revises' the rod worth minimizer system low power setpoint. ]

5962-2 Unit 2 -

Addition of protection against control complex fires and resultant faults for reactor core isolation cooling control and

! indication circuits in the remote shutdown panel.

5972-2 Unit 2 - Replacement and setpoint change of the 4kV bus degraded grid undervoltage relays. -

5989 Unit 2 - Designation of core spray injection valve as essentia' for safe shutdown. ,

5994-2 Unit 2 -

Addition of an emergency manual transfer switch for the reactor core isolation cooling steam supply inboard containment isolation valve.

5995-2 Unit 2 -

Addition of an emergency shutdown switch at the remote shutdown panel for the L high pressure core spray system.

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Attachment Page 5 of 5 l

5998-2 , Unit 2,- Addition of a disconnect switch in-the reactor water cleanup systen.- ,

L

- 6026-2 Unit 2 - Addition of e. control rod drive water sample and analysis system.

p 6031-2 Unit 2 Replacement .of undervoltage relays '

for 480V load center c.ircuit breakers..

! 9033 Unit 1 and Unit 2 -

Modification provides i y duplication of various process' computer analog i signals from common . plont equipment for - the plant monitoring system.

9034 Unit 1 and Unit 2 -

Modification provides duplication- of various process computer ,

digital signals from common plant equipment ' ~

for the plant monitoring system.

9044 Unit 1 and Unit 2 - Relocation of the tie-in i of- the service water line to the backup  !

service air compressor. ,

9048 Unit 1 and Unit 2 - Addition of drains to condensate and- refueling water storage systems. ,

9051 Unit 1 and Common -

Addition ' of a sample-  !

bypass line for the north stack effluent 'L monitoring system.

P 9058 Unit 1 and . Unit 2 -

Addition of Unit 2 '

refueling. area' limit switches- within the-reactor enclosure.

9067 Unit 2 - Relocation of yard fire hydrent and 4 post indicator valve.

9075 Unit 1 and Unit 2 - Transfer of the service water / emergency service water control power.

1 9076 Unit 1 and Unit 2 -

Addition of a local control for the emergency service water pump motor.

9080 Unit 1 and Unit 2 - Addition of control room-traffic barriers.

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