ML19254E130

Submits Addl Info Requested Re IE Bulletin 79-14, Seismic Analysis for As-Built Safety-Related Piping Sys. Forwards Tabulation of safety-related Piping Per FSAR Table A.g.1

ML19254E130
Person / Time
Site:	Peach Bottom
Issue date:	10/03/1979
From:	Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 7910310129
Download: ML19254E130 (10)

Text

v 4 fx PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 (215)8414o00 O c t ob e r 3, 1979 Re: Docket Nos.: 50-277 50-278 IE Bul?etin 79-14 Mr. Boyce H. Grier, Director Office of Inspection & Enforcement Region I United States Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406

Reference:

(1) Telephone conversation from R. LaGrange and S. Hofsfor (DOR Engineering Branch) t o W. M. Alden, Engineer-In-Charga -

Generation Division / Nuclear Section

Dear Mt. Grier:

This letter is in response to the verbal request (Reference

1) for additional infor stion pertaining to Item 1 in Bulletin 79-14.

1. Piping identified with accessibility code "C" runs between the various structures in the plant and is buried underground. We have reviewed the piping isometrics to specifically identify the piping that is buried and, as a result, have revised the tabulation tha was submitted to the NRC with the 30-day response. The reiised tabulation is attache . The specific piping that i .a buried is as follows:

a. Condensate Service System (1) Piping common to the Unit 2 HPCI, RCIC and core spray pump suctions and on the HPCI and RCIC 1235 238 791oa1o l2 6'

Mr. Boyce H. Grier Page 2 pump discharges from the Unit 2 condensate storage tank to the Turbine Building.

(2) Piping common to the Jnit 3 HPCI, RCIC and core spray pump suctions and on the HPCI and RCIC pump discharges from the Unit 3 condensate storage tank to the tunnel underneath the Recombiner Building. The piping in this tunnel, however, is accessible only when both units are off.

b. High Pressure Service Water System (1) Pump disc'aarge piping to the RHR heat exchangers from the Pump Structure to the Turbine Building.

(2) Piping downstream of the RHR heat exchangers from the Units 2 and 3 Reactor Buildings to the Diesel Generator Building.

c. Emergency Service Water System (1) Pump discharge piping to the Reactor Building cooling water heat exchangers, safeguard equipment roou coolers, and diesel generator coolers between:

(a) the Pump Structure and the Turbine Building, (b ) the Pump Structure and the Diesel Generator Building, (c) the Turbine Building and the Diesel Generator Building, and (d) the Units 2 and 3 Reactor Buildings and the Diesel Generator Building.

(2) Piping downstream of the Reactor Building cooling water heat exchangers and safeguard equipment room coolers from the Units 2 and 3 Reactor Buildings to the Diesel Generator Building.

d. Emergency Cooling System (1) Emergency service water piping downstream of the RHR heat exchangers from the Diesel Generator Building to the Emergency Cooling Tower and to the discharge pond.

1235 239

Mr. Boyce H. Grier Page 3 (2) Emergency cooling pump discharge piping to the reactor building cooling water heat exchangers and safeguard equipment room coolers (connecting to Emergency Service Water piping) from the Emergency Cooling Tower to the Units 2 and 3 Reactor Buildings.

(3) Em rgency service water booster pump discharge piping from the Diesel Generator Building to the Emergency Cooling Tower.

(4) Piping from the Emergency Cooling Tower to the Intake Structure.

2. As a result of the work performed to satisfy the requirements of IE Bulletin 79-04, it was discovered that the CRD return line outside coniainment was not seismically qualified. A seismic boundary anchor was added to the 1 ping and the piping between containment penetration N-36 and the new anchor was analyzed to meet seismic requirements. The piping between the penetration and the anchor was measured to provide 'as-built' dimensions for the reanalysis. The piping on Unit 2 has no supports between penetration N-36 and the new anchor and it passes through one open floor penetration. The clearance through the floor penetration was not measured, however, the movement of the piping during a seismic event will not be significant enough for the clearance t o be a concern. It was verified that there was space between the pipe and the penetration.

The piping on Unit 3 is anchored where it passes th ru a wall close to primary containment penetration N-36. The pising was reanalyzed from the anchcr thru the wall to the new seismic boundary anchor. This piping passes through no other walls or floors and contains only two rod hangers which were reviewed. Neither the Unit 2 or Unit 3 piping contain power-operated valves and there are no welded attachments to the piping except for the seismic boundary anchor which was recently installed. We consider that the elements of IE Bulletin 79-14 have buen satisfied for this piping.

3. Valve weights and valve / operator centers of gravity are taken into consideration by reviewing the information contained in vendor drawings against the input to the seismic calculation.

4. Penetrations are inspected for 'as-built' conditions including the type of penetrations and measurement of clearances.

1235 240

Mr. Boyce H. Grier Page 4

5. Measurement's are made to at least one support outboard of the outboard isolation valve.

Very truly yours, l h['"l$'b' M. . Cooney Superintendent Generation Division / Nuclear cc: United States Nuclear Regulatory Commission Office of Inspection and Enforcement Division of Reactor Operations Inspection Washington, DC 20555 1235 241

TAlllli.ATION 01: I'l!ACil BO'lTOM SAFirlY-Iti!I.ATI D l'IPING Plill FSAR TAllll! A.9.1 Page 1 of 6 Accessible (A)/ Inspection Pipin); Description Stross Tsometric No. Revision innecessible (1) Code (See below)

Main Steam System g

c:r-Reactor to Containment Penetration 731 E 799 1 I B N 730 E 756 7 I B 729 E 153 8 I B C m

Containment Penetration to Outboard SK-M-711 A I B Isolation Valve ,

SK-M-712 A I B Drair.s to Containment Penetration SK-M-725 B I B Drains Penetration to Outboard SK-M-725 B I B Isolation Valve Reactor Recirculation System rl Reactor to Recirc Pump Suction 731 T 386 1 I B Nm 730 E 116 7 I B A 153 F 769 5 I 730 C 117 4 I B

B y

Recirc Pump Discharge to Reactor "

1 I B M

g]

CRD Hydraulic System e1 Return Line - Reactor to Containment SK-M-891 B I B U Penetration  %

Return Line - Penetration to Outboard This piping has been "as-built" and reanalyzed within the last Isolation Valve 12 months and therefore does not need to be inspected per Bulletin 79-14 Scram Discharge Volume 6 Headers A A Insert and Withdrawal Lines A,I A,B Inspection Code: A - within 60 days

. B - within 120 days C - cannot be insp :ted (no physical access possibic)

TAllUI.ATION OF Pl!ACll BO'IT0h! SAltliTY-lllil.ATl!D PIPING Pl!R FSAll TAlli,1! A.9.1 Page 2 of 6 Accessible (A)/ Inspection Piping Description Stress Isometric No. Itevision fuae essible (1) Code (See below)

Feedwater Reactor to Containment Penetration SG-6-IS I B m

Containment Penetration to Outboard SG-6-3S I,A B,A Isolation Valve Ln m

Inerting System N Containment Penetration N-2S to 2nd SK-M-709 A A A Isolation Valve SK-M-710 A A A 2-9-4 A A 2-9-9 A ,

A 3-9-4 A A Containment Penetration N-26 to 2nd 2-9-4 A A Isolation Valve 9

Suppression Pool Penetration N-219 to 2-9-9 A A d 2nd Isolation Valw g Residual IIcat Removal System Suppression Pool and Recirculation SG-10-4S A A Q Piping to Pump Suction SG-10-7S A A SG-10-85 A A (d3Ed

~

G;=5)

Pump Discharge to Reactor licad SG-10-9S A,I A,B g Spray SG-10-SS I B Pump Discharge to Containment SG-10-6S A,I A,B Spray llender G Recirc. Piping SG-10-9S A,I A,B Inspection Code: A - within 60 days B - within 120 days C - cannot be inspected (no physical access possibic) 9/13/79

TABULATION OF PEACl! BOTTOM SAFETY-RiiLATED PlPING PliR FSAlt TABLl! A.9. I Page 3 of' 6 Acce:,a ili t o (A)/ Inspectinn i

Piping I)oscrlition Strons isomotric No. Itevision inaccessihin (O Co<le (Sce below)

Pump Discharge to Torus (Test Line) SG-10-3S A A . <r

-::3-Fuc1 Pool Skimmer Surgc Tanks to N SG-10-IS A A IUIR Pump Suction m A

Rl!R Pump Discharge llender To Waste SG-10-2S A A N Collector Surge Tanks -

Standby Liquid Control System Tanks to Pump Suction SK-M-724 (Unit 2) A A A IIISO-11S1 (Unit 3) A A A Reactor Water Clean-up System From RilR Shutdown Cooling Supply llISO-1209 (Unit 2) A I B To Outboard Isolation Valve 111S0-1265 (Unit 3) A I B SG-12-4S I B Reactor Core Isolation Cooling System q

Steam Supply from "C" Main Steam SK-M-774 A I,A B,A N Line to RCIC Turbine SK-M-773 (Unit 3) A A A N SK-13-IS (Unit 2) I,A B,A ' -

@9 Turbine Exhaust to Supprossion. Pool SG-13-2T (Unit 2)

SK-M-979 (Unit 3) B A

A A

A g'

O Pump Suction from Suppression Pool SK-M-756 A A A and Condensato Storage Tank SK-M-767 A A A M SK-M-768 A A A [7 SK-M-770 SG-23-3S A

A A

W A

44 Inspection Code: A - within 60 days B - within 120 days C - cannot be inspected (no physical access possibic) 9/13/79

TAllllLATION 01: Pl!ACil 110TTOM SAI:l!TY-It!!!.ATl!!) Pil'ING l'!!R 1 SAR TA131.li A.9.1 Page 4 of 6

_ Piping Description Accessibic (A)/ Inspection Stress isomotric No. Revision inaccessible (1) Code (See below)

Pump Discharge to Feedwater Piping SG-13-35 (Unit 2) A,I Suppression Pool, and Condensate A,B SK-FI-757 (Unit 3) A A A Storage Tank (including Reactor SK-M-758 (Unit 3) A m Water Clean-up Regenerative A,I A,B SG-12-2T I IIcat Exchanger) B C M

RCIC Pump Suction to Torus Water N SK-F1-1000 A ~

Clean-up Pump Suction A Core Spray Cooling System Pump Suction from Suppression Pool SG-14-2T A and Condensate Storage Tank A SK-Ft-1010 A A S K-Ff- 1011 A A SG-14-SS A A Pump Dic:harge to Reactor Vessel SG-14-IS I B Sparger and to Suppression Pool SG-14-4S A A SG-14-6S I,A B,A SK-M-750 A A A SK-M-755 A A Radwaste System Drywell Sump Pump Discharges krf SK-M-741 A A A Q:a Outside Containment SK-F1-742 A A A t= ==

liigh Pressure Coolant Injection System g

Steam Supply from "B" Main Steam SK-M-772 A A A Line to !!PCI Turbine SK-M-771 A A,I A,B SG-23-IS A A Turbine Exhauet to Suppression Pool SK-M-753 SG-23-2S A A A

A A

Q nspection Code: A - within 60 41ays B - within 120 days C - cannot be inspected (no physical access possibic) ,

TABULATION OF PEACII BOTTOM SAFETY-RELATED PIPING PER FSAR TABLE A.9.1 Page 5 of 6 Accessibic (A)/ Inspection Piping Dnscription Stress Isometric No. Revision Inaccessibic (I) Code (See below)

Pump Suction from Suppression Pool and Condensate Storage Tank SK-M-770 SG-23-3S A A A

A A

[g Pump Discharge to Feedwater Piping, SK-M-766 A A A C Suppression Pool and Condensate SK-M-769 A A A A Storage Tank SG-23-4S A,I A,B ]

liigh Pressure Service h'ater System Pump Dischargo to RHR IIcat Exchangers SK-M-714 A A,I A,C SK-M-715 A A,I A,B,C SK-M-716 A A A SK-M-717 A A A SK-M-718 A A A SK-M-719 A A A R11R llcat Exchangers to Discharge Pond SK-M-721 A A,I A,C and Emergency Coolir System SK-M-722 A A,I A,C SK-M-723 A A,I A,C Condensate Service System 4 From Condensate Storage Tank to IIPCI, 111S0-2751 A A,I A,C M RCIC nnd Core Spray Pump Suctions ' '

S From IIPCI and RCIC Pump Discharges Unnumbered Sketch A,I A,C To Condensato Storage Tank dated 3/12/69 Inspection Code: A - within 60 days B - witin 120 days C - cannot be inspected (no physical access possibic) U 9/13/79 d foM

T!9111.AT10N OF Pl!ACil ROTTOM SAFliTY-illii.ATlil) PIPING Plift USAR TABl.l! A.9.1 l' age 6 of 6 Accessibic (A)/ Inspection Piping Description Stress Isometric No. Revision Inaccessibic (1) Code (See below)

Emergency Service Water g

-ce Diesel Generator lleat Exchangers SG-33-IS A,I A,C N Supply and Return SG-33-2S A,I A,C LO Emergency Service Water Pumps SK-M-727 A A,I A,C Discharges ~

Supply to Reactor Building Cooling SK-M-729 A A,I A,B,C Water Heat Exchangers and Safeguard SK-M-730 A I B,C Equipment Room Coolers SK-M-731 A A,1 A,C SK-M-732 A A A SK-M-733 A A -

A SK-M-734 A A A SK-M-735 A A A SK-M-736 A A A SK-M-737 A A A SK-M-738 A A,I A,C SK-M-739 A A,I A,C Emergency Service Water Piping in SK-M-784 A A A ,M Diesel Generator Building SK-M-785 A A A ,c q~

SK-M-786 A A A g id Emergency Cooling System  ;

c=2 Emergency Service Water Booster Pumps SK-M-1005 A,I A,C (cM Discharge ,g Cooling Water to Emergency Cooling SK-M-790 A A,I A,C y Cooling Towers SK-M-791 A A A ,, ,)

Emergency' Cooling Water Pump Dischargo SK-M-787 A A,I A,ge

'N U Ib Inspection Code: A - within 60 days B - within 120 days C - cannot be inspected (no physical access possible) 9/13/79