ML19320D573
| ML19320D573 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 07/02/1980 |
| From: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| IEB-80-11, NUDOCS 8007210547 | |
| Download: ML19320D573 (18) | |
Text
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PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 R'M "**'
swistos t.oAtrnorr ELactascpm UCTION July 2, 1980 Dochet Nos.: 50-277 50-278 IE Bulletin 80-11 Mr. Boyce H.
Grier, Director Office of Inspection & Enforcement Region I U.S.
Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Dear Mr. Grier:
This is in response to your letter of May 8, 1980,which forwarded IE Bulletin 80-11, and requires a response to items 1,
2a, and 3 of the Bulletin within 60 days of the issue date.
- A response to item 2b of the Bulletin will be forwarded within 180 days of the issue date of the Bulletin.
The actions requested in items 1,
2a, and 3 of the Bulletin, and our responses are listed sequentially below.
Action to be Taken by Licensee:
1.
Identify all masonry walls in your facility which are in proximity to or have attachments from safety-related piping or equipment such that wall failure could affect a safety-related system.
Describe the systems and equipment, both safety _and non-safety-related, associated with these masonry walls.
Include in your review, masonry walls that are intended to resist impact or pressurization loads, such as missiles, pipe whip, pipe break, jet impingement, or tornado, and fire or water barriers, or shield walls.
Equipment to be considered as attachments or in proximity to the walls shall include, but is not limited to, pumps, valves, motors, heat exchangers, cable trays, cable / conduit, HVAC ductwork, and electrical cabinets, instrumentation and controls.
Plant surveys, if necessary, for areas inaccessible during normal 8 0 0 7 e l 0 5pf 4
Mr. Boyco H. Grior Page 2 plant operation shall be performed at the earliest opportunity.
Response
All masonry walls at Peach Bottom Atomic Power Station which are in proximity to or nave attachments from safety-related piping or equipment are identified in Appendix A.
Proximity is defined as being within a distance equal to the wall height, such that wall failure could render the safety-related system inoperable.
Safety-related systems and equipment associated with these masonry walls are also described in Appendix A, together with the wall location, its primary function (shield wall, partition, etc.), and the tentative priority for re-evaluation.
Non-safety-related systems or equipment such as conduits, cable trays etc. attached to these walls have been surveyed and all data related to these systems have been obtained in order to establish imposed loading on masonry walls for use durin-the re-eva3uation analysis.
The information shown in Appendir A was obte.ined by perform $ng a plant survey.
Appendix B lists masonry walls which do not have safety-related systems / equipment either. attached to them or in proximity.
The information shown in Appendix B was obtained either by plant survey and/or by drawing review.
A visual, walk-through verification will be made to confirm the drawing review.
Should this investigation identify any walls which affect safety-related systems or equipment, those walls will be surveyed in detail, added to Appendix A, and included in the re-evaluation program.
2.
Provide a re-evaluation of the design adequacy of the walls identified in Item 1 above to determine whether the masonry walls will perform their intended function under all postulated loads and load combinations.
In this regard, the hRC encourages the formation of an owners' group to establish both appropriate re-evaluation criteria and where necessary, a later confirmatory masonry test program to quantify the safety margins established by the re-evaluation criteria (this is discussed further in Item 3 below).
a.
Establish a prioritized program for the re-evaluation of the masonry walls.
Provide a description of the program and a detailed _ schedule for completion of the re-evaluation for the categories in the program.
The completion date of all re-evaluations should not be more than 180 days from the date of this Bulletin.
A higher priority shocid be placed on the wall re-evaluations consideri,g safety-related piping 2-1/2 inches or g.
.-g g
Mr. 'Boyco H. Grior Pago 3 greater in diameter, piping with support loads due to thermal expansion greater than 100 pounds, safety-related equipment weighing 100 pounds or greater, the safety significance of the potentially affected systems, the overall loads on the wall, and the oppor.2nity for performing plant surveys and, if necessary, modifications in areas otherwise inaccesa.ible.
The factors described above are meant to provide guidance in determining what loads may significantly affect the masonry wall analyses.
Response
The re-evaluation program will consist of a structural analysis of the masonry walls identified in Appendix A using an appropriate re-evaluation criteria which will define loads considered, load combinations and allowable stresses.
The following parameters will be considered in establishing priorities for wall re-evaluation:
a)
Walls which have larger number of safety-related systems on them or in their proximity, i
b)
Walls which are subjected to heavier loading, and c)
Walls which, in terms of height, length and thickness are judged to be more critical than others.
Tentative re-evaluation priorities are indicated for each wall in Appendix A.
. Priority 1 and Priority 2 indicate the walls which wila be analyzed first, followed by Priority 3 and 4 in that order.
The re-evaluation of masonry walls designated as Priority 1 and Priority 2 is expected to be completed by mid or late September, 1980.
Re-evaluation of Priority 3 and Priority 4 masonry walls is expected to be completed by mid or late October, 1980.
A report of the re-evaluation will be submitted by November 4, 1980, as required by the Bulletin.
3.
Existing test data or conservative assumptions may be used to justify the re-evaluation acceptance criteria if the criteria are shown to be conservative and applicable for the actual plant conditions.
In the absence of appropriate acceptance criteria a confirmatory masonry wall test program is required
-by the NRC in order to quantify the safety margins inherent in the re-evaluation criteria.- Describe in detail the actions planned and their schedule to justify the re-evaluation criteria used in Item 2.
If a test program is necessary, provide your commitment for such a program and a
v Mr. Boyco K. Grior Page 4 schedule for submittal of a description of the test program and a schedule for completion of the program.
This test program should address all appropriate loads (seismic, tornado, missile, etc.).
It is expected that the test program will extend beyond the 180 day period allowed for the other Bulletin actions.
Submit the results of the test program upon its completion.
Response
Justification for re-evaluation criteria will be submitted with the re-evaluation report within 180 days of the date of the Bulletin.
Justification will be based on reference to effective codes and established standards of practice related to woncrete and masonry design typically used throughout the industry.
It is anticipated that such justification will be considered appropriate, except as required to determine project unique structural properties such as collar joint strength and any other properties for which test data is not available or cannot otherwise be determined.
Should these unique properties need to be determined by testing, adequate test pc,cedures will be developed as required.
Very truly yours, f
/
ill:~lt-Attachments:
Appendix A Appendix B 1
cc: United States Nuclear Regulatory Commission Office of Inspection and Enforcement Division of Reactor Operations Inspection Washington, DC 20555 l
o COMMONWEALTH OF PENNSYLVANIA :
ss.
COUNTY OF PHILADELPHIA s
S. L.
Daltroff, being first duly sworn, deposes and says:
That he is Vice President of Philadelphia Electric Company; that he has r< sad the foregoing response to IE Bulletin 80-11 and knows the contents thereof; and that the statements and matters set forth therein are true and correct to the best of his knowledge, information and belief.
15 b
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Subscribed and sworn to before me this c/ " day k
of 3
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o ryJPubli ['
usem w.e
. Note Pub'ic. Phils Phil i
y Isalon Empires Jan.M 19&f
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APPENDIX-A*
gwg g,g 7 StMMARY OF MASONRY WALLS (SAFETY PE1ATED)
PEACH BOTTOM ATOMIC POWER STATION UNITS 2 & 3
( SEE PAGE 7 FOR NOTES)
SERIAL WALL Nf MTRIPrYm WhtL'S PRDfJtt N N ENNN SMTIT M2ATED SWFDS 3M
- TuwATIvh l
88 0 WO (I)
BUILDING E11V.
1DCATION N IN III PruCRr!Y t.
I 1
15.1 Fedweste 88-0 &
standby One Treatment shielding 7
standby One Treatment system (Fame Filters 3-91-6 noon and tute) 2 15.2
-DO-
-DO- -DO-7
-DO-3 3
16.1
-DO-
-DO-Beactor Core Ieolation
-DO-None peector Core Isolation Coolias 3;
Cooling Puery Area, that 2 Pump Turbine, ikit 2 e
b 16.2
-DO-
-DO-
-DO., Unit 3
-DO.
None
-DO., thit 3 3
j saraguard metated e tt 3
5 16.3
- DO-
-DO.
waste sludge Tank saan
-n mone 6
32.1
-DO.
116-0 Conaeneste Tank & Pump
-DO-7, 10 pone 3
Boane 7
32.2
- DO-
-DO-
-DO-
-DO.
None
%80V AC Power 3
8 32 3
-DO.
-DO-Condensats Pump Area
- DO-1, 7 BCT & 3CIC 3
9 32.4
- DO-
-DO.
-DO.
-DO.
-Dos
-DO-3 10 32 5
-Do-
-Do-
-DO-
-DO-
-Do-
-DO 3
11 32.10
-DO-
-DO-Filter Holding Pump Soma Shielding.
7 Bone 3
& Fuel Pool Filter Dominera11ser Area 12 32.11
-DO.
- Do-
-DO-
-DO.
some t--
3 13 32.12
- Do-
-DO-
-DO.
-W None s7 3
lb 56.1
-DO-135-0 RW Control Boon & Filter
-DO-6 gone 3
A14 Tank & Pe p Area 15 78 3
-DO-165-0 Redveste Buildina -
~ -DD-17 herg. swgr Filter neueing 3
hn Room 16 25.1 Turbine (Con-116-0 switchgear & Conventional Partition 2, 3, 8 thru'll Righ Pressure and Energency Service Water 2
trol.8tructure)
Chem. Imb Lines and Safeguard Conduite 17 25.2
-Do-
-DO- -DO-2, 3
-DO.
2 18 bO.1
-DO.
135-O Sattery Room, thit 2 F;re Restatance 8, 10, 12, 14' Battery Rack, Channele A & C, Unit 2 1
O
.1 Ca N
P
- o
?.
APPENDIX A Sheet 2 of 7 l,
SUMMARY
OF MASONDY NALt.S (SAFETY RE!ATED)
PEACH BOTTOM ATOMIC FOWER STATION UNITS 2 & 3 san Ar.
war.z.
- -wirm m 2.'s enz a r mm suma mmem-sum namm sums /nwxneur zu
. 8BuMAE suurarna NO HO (I)-
30ILDING IIJLV.
- 14) CATION NM
(">
- E EUI nuomm 1 19 40.2 Turbine 135- 0 Switchgear Rom Fire Bestatance 2, 7, 9, 10, 12, 13, 14, 17 1 kr switehaear, Chanrel C & s c 1
3 (Control Unit 2 Channel C, Unit 2 Structure) 20 40 3
- DO.
-Do-
-DO.
-Do-1, 2, 3, 6 thru'Ib,17..
4 kV 8vitetgaar, Channel D, that 2 1
21 k0.4
-DO-
-Do-
-DO, Unit 3
- Do-2, 8, 9, 11, 12,13, 17
-Dc., Channel D, that 3 1
22
, 40.5
-Do-
-Do-
-Do, Unit 3
-Do-3
,j,7,9,10,12,13.
-Do, Channel C, that 3 1
23 40.6
-DO.
-Do-Battery Races, Unit 3
-W 1,8,10;12,14 Battery Rack, Channele A & C, Unit 3 1
24 bO.7
-DO-
-W Battery Boca, that 2
-W 10, 12, 14 Battery Pack, Channele A, B, C, & D, 1
Unit 2 and Fuse Somes Channele A &C.
25 40.8
-DO-
-Do-suite'haear Rom, that 2
-W 7, 10, 12, 14 4 kV avitchsear, Channele A & C, Unit 2 1
26 k0.9
-Do.
-Do-
-Do, thit 2
-W 7, 9 thru'13
-DO, Channele B & D, Unit 2 1
27 40.10
-Do-
-DO-
-DO, thtt 3 8, 9, 10, 17
-DO, Channels 3 & D Unit 3 1
28 bO.11
-DO.
-Do-
-DO, Unit 3
-Do-2, 3, 7 thru'12,14,17
-DO, Channele A & C, Unit 3 1
29
%0.12
-DO-
-W Battery Boom, tkI1t3
-Do-1, 8, 10, 12 Battery Beck, Ctannele A, B, C, & D, 1
Unit 3 end Fuse 3osee Channels a &C 30 40.13
-DO-
-W Battery Boca & Switch-
-Do-6, 8 thru'12, 14, 17 Battery Back, Channele A & C, EC 1
gear. thtt 2 Channel C, Fuse Somes Channels, A & C 4 tY Switchsear, Ctannel C, Unit 2 31 40.1b
-Do-
-Do-
-DO-
-Do-2, 8, 10, 11, 12, 14 Battery pack, Charnele B & D. MCC 1
Channet. A Fuse Brzee Channele B % D.
b kV Switchgear, Channel A, thtt 2 32 40.15
- DO-
-Do-Switchgear soon, Unit 2
-DO-2, 9, 11, 12
% kV switchsear, channel C & D, 1
Unit 2 g
evitch ear Rom, Unit 2
-DD-2, 8 that 1%
k kV switetsvar, Channele A & S, 1
33 40.16
-DO-
-Do-8 g
Channel B, Unit 2 tl lj 34 40.17
-DD-
-DO-suitetwear nom, Unita 2
-DD-2, 8 thru'13 h kV switehaear, Channele D & D, Unite 2 1
&3
&3 e
8 i iC v
q
~
m
PUCH BOTTOM AtopffC POWER STATION (JN!?S 2g 3 SERIAL WALL marr i,2..nifvIrw No NO (t)
BUILDING I DEV
' WM.L'3 FRDSJU N N MMNIN 14 CAT 10N NW NN SAITIT M2A71D inm8S/EMII9eNT Int ITDerATIVE 1
9
(
PKDEM & M UI)
'35keWA1AEWW m om rr
- ,[
35 k0.tB turbine 135-0 switchgear maces, thste a rare pestatance
- - ~
(Control
&3 2, 9, 11, la structure) 4 kr switchgear, Channele a & s, unite 2
& 3, t
switchgear amn, Unit 3 7.~
- !,,e, 36 bo.19
-n
-Do.
-w
],
8, 9, 11, 12, 17
\\
37 40.20
-Do-
-Do-
-n
-Do., Channel. C & D, nCC Channel D,
~
k *'" s that 3 1
s
-E 2, 7, 8, 9, 11 thru' 14 13 40.21
-Do-
-DO s
+
-Do. ' 3Channele A & 's, pcc Chaansi al, Switchgear & Battery Roane, Unit 3 1, 7, 8, 12, 14 1
.k M '
tha t
-W Battery Back, Chamela A & C Fvee Bozee 39 k0.22
-Do.
- DO.
-Do-Channele A &C 1
U, j',
4 kV Switchgear, Channel C, thtt 3 I
'i*
-Do.
4, 8, lo, 11, 12, 14 Battery Raet, Channele B & D. SCC 4,
- [
60 40.23
-Do-
-W Channel A, Euce Bones, Channele B p D 1
{!
'!?
Switchgear Roaa, th1t 2 b kV switchgear, Channel A, tmit 3
',j - J.
-DO-None l.
r,4 41 40.24 b kV Switchgear, Channel D, thit 2 and ff&V Duet 3
. >s
-Do.
-Do-h.:'f( ; ',,.
C i7
-Do., thtt 2
-Do.
h2 60.25
-W
-Do-sone
-Do.
2,;, % v -
-Do, Unit 3 3
- {
-n Bone 3
43 40.26
.m
-n, that 3 K
- i
-Do., that 3 3
-Do.
7 "f f 44 40.27
-h
-W
-Do, thit 2
-Do.
e yone S-.
r7 3
- y..'d. " " ',,
-D0 None 65 40.28
-DO-
-DO-
-DO-4 kV switchgear & DCC Channel A, that 2 3
W<
4 3
7
-Do-None 6
40.29
- Do.-
- DO.-
% kV Switchgear & NCC 3annel B, thit 2
!e,
-DO, Unit 3 b kV Dwitchgear & DCC Channel 3, that 3
(($
3
-DO.
None 7
40 30
-W
-W 5
t 3
19.
-Do.
None i
68.1 4 kV 9witchgear & MCC Channel A, that 3
,s '.,r
-Do-150 0 Cable Spreading Room 3
,p " -
-W 1, 8, 9, 11, 13, 17 a
68.2
-to.
-n
-n Safeguard Troy.
CeD g
-Do.
1 68.3
-w
-Do-5
-W l (<,k,
2
-w 1
1 thru'5, 7.thry'12, 14, 18
-h t,
68,4
-Do-
-Do-
-Do-1
?.
-Do.
I thru'.7. 9 thru'17
-DO-1 68.5
-Do.
-Do-
-W 1
t
- DO-
.)y 3,
shielding mone 2
s v
?
j f7 a
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(-)
s Q
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eq m
in e
N k-s o-
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, ~
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r,
A' f,,.
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APPEFFDIN A Sheet % of 7 SINMARY OF MASONRY WAL1,5 (SAFETY REIATED)
PEACH BOTTOM ATOMIt* POWER STATION UNITS 2 & 3
~
SERIAL WALL IdafL trXRIPrim Wh!L'S PRINJOf WM N LYSm6 M M SAfTIY MIA11D SYSTTMi/10!IPMNr IN TDfratTIVE NO NO (I)
BUILDING IILV.
IDCATION FWCTIW AUM M M III)
N & M (II)
NIW Pstionrn _
53 71.1 Turbine 165-0 Control Room Shielding None Control Panela. Safeguard Traya 2
(Control 8tructure) 5%
%5.1 Beactor.
135-0
!aolation Yalve Ccep.
-DO.
- 2. 3. 5 m) Containment reolation valves and 1
Unit 2 Assoc. Conduite b) CRD Insert and Withdrawal Linee 55 L5.2
- DO.
-DO.
-Do-
- 2. 3. b. 10. 15
.DO-1 56 45.4
-DG-
-DO.
steam Pipe Tunnel
-DO-5, 15. 18 nely on stem. Line "A* and Belated 2
- CaaM to 57 15.6
-DO-
-D0
-Do.
- Do-sone
- 5. 15. 18 2
58 75.6
-Do-165-0
!aolation Yalve Area
-DO-None Contaimeent Isolation Valves and 'conduite b
& IllCU leakage detection temp. element 59 76.6
-00
-DO-Ioad Centers Fire Beeistance
- 9. 10 Electrical Load Center
,b 60 76.7
-DO- -DO-
-DO-None
.DO., 1 thru 7, 9. 10. 15. 17
~
1 61 76.8
-Do-
-DO-
-Do-
-DO-Bone Riectrical Load Center b
62 76.9
-DO-
-DO-
-DO-
-DO.
some
-In. 1 thru 7. 9, 10. 15 1
63 76.10
-DO-
-DO-
-DO-.
-DO-2 Electrical Imad Center 4
64 87.1
-DO-180 0 Isolat16e Valvt Compartment shielding sone Containment Ieolation Valves. RWCU 4
Laakage Detection Temp. Element
(
6 i
8 65 1m.8 10-234-0 Refueling
-DO.
6 Bone n
Floor s
66 102 9
-DO-
-DO-
-DO-
-DO-6 None 2
67 bb6.1 Reactor.
135-0 Isolation Velve comp.
-DO-
- 2. 3. 15 a) Conteinment Isoletion valves & Conduite t-Ikilt 3 b) CFD insert and Withdravel Lines 68 k06.2
-DO-
-Do-
-DO.
-DO-2 thru'5. 7. 12
-DO-t s
O s1 CR
.N,
,. APPD3 DIN A ~
Cheet 5 of 7 4,stMMARY OP $4ASONRY WA1.LS (SAFETY DE!ATED)
PEACH BOTTOM ATOMIC POWE1 STATION UNITS 2 6 3 3
SERIAL W!L
"' - rums Wh1L'S PRugaer ~*' N NN SAMY m N/IGIIPPWF De NM pgogIpgTY w WEL (II)
Idem 1L%.
IDCATION RNygg a ATTMMD 10 M (II)
! g NO NO (I)
SUILDING 311V.
PRIORITir 69 406.6 Seactor, Unit 3 135- 0 Steen Pipe Tunnel Shielding Bone peIV on Steen Line "A" and blated Conduite k
70 406.9
-n
.DO.
-DO.
-DO-5, 12 MSIY on Steam Line "A" and Belated Condelte 2
71 606.1o
-DO-
-DO-
-DO-
-DO-3, 5, 10, 12
- DD-1 72 ko9.7
-DO-165-0 Isolation Valve Area
-DO-Bone Contairment !aolatica velve & Associated b
Conduite and NWCU Leakage Detection Temperature Element 73 b10.1
-DO-
- DO-Regenerative Heat Ex.
-DO-5 8one 4
changer Area 74 410.6
-Do-
- Do-Load Center Fire Resistance Bone Electrical Load Centers, 7.10,11 2
-DO, 2,3,5,6,7,10,11,14.15 1
75 410.7
-DO-00
-DO-
-DO-none 76 b10,8
.po-
-DO.
-DO-
-DO-None
-DO,10.12 2
77 410.9
-DO-
-DO-
-DO.
-DO.
None
-DO, 2,3,5,7,10,11,12,14.17 1
78 410.10
-DO.
-DO.
-DO-
-DO-None
-DO,10,11.17 2
79 b12.1
-DO-180-0 Isolation Yalve Compart.
Shielding None Containment Isolation valve and conduite b
ment
& NWCU Leakage Detection Tomp. Element 80 413,10
.D0-231-0 Refueling Floor
.go.
6 b
None 81 413,11 -
-Do-
-DO-
-DO-
-DO-6
-DO-b 82 532.1 B,ergency 158-0 a,ergency Coo 11ag Tower Fire peelstance 4,8 h orgency Cooling veter Ptery and Load 4
8' Coo 11ryt centers' and Panels, MCC Tower l
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'APPDCII "A' Sheet 7'or 7 I ~ 5t204ARY OF MASONEY WA1.LS (SAFETY BEIATED)
PEACH B01 TOM ATOMIC FUWER STATION UNITS M3 37t!$:
../
- ~ ~
I.
Each well le designated by a unicae ember such that the r
first part indicates the Civil / Structural Dreving amber and the seeced part gives the well number on that particular drowing, e.g. well No. b5.2 indientes well seenber 2 on Civil / Structural Drewing No. b5.
II. Safety related systeme are designated as below:
1.
Beector Core Toolation Cooling f pCIC)
' 2.
Reactor Meet Demoval iRNR)
=
3 Core Sprey..
4 High Pressure Coolant !ajection (IGCI) 5.
Primary containment Isolation 6.
Process / Area Bedletion Monitoring 7.
Standby Ces Treetment 8.
Baergency Service Water (BSf) 9 Emergency Diesel Generator
- 10. Safeguard 480 YAC Power (MCC,14)
- 11. Safeguard 4 kV Power
- 12. Sefeguard 125/250 VDC Power 13 Safeguard 120 VAC Fower 14 Safeguard 2h VDC Power
- 15. Contalment Atmospheric D11stion (CAD)
- 16. Reactor Protection Syntam (RPS)
- 17. Befeguard HVAC Systen
- 18. 8 teen 1.cek Detectico System
'6 hwm-6 g=m-e m
S O
O s1 01 NH
atrets as % u t
APPENDIX "B" y
SUMMARY
OF MASONRY WALL (NON-SAFETY RELATED)
PEACH BOTTOM ATOMIC POWER STATION UNITS 2 & 3 ISERIALI l
WALL DESCRIPTION l
(
l NO.
lWALL NO. I BUILDING IELEVATION l LOCATION I
BASIS FOR CLASSIFICATION
(
l i
I i
i 1
(
l 1
l 24.1 1
Turbine i
116-0 i
Valve Operating Area l
Plant Walkdown & Eng. Review
[
l i
I I
I I
{
l 2
l 32.6 i
Radwaste
-DO-ICondensate Pump & Tank Rooms l Engineering Review
(
l l
1 1
I i
~
{
l 3
1 32.7 l
-DO-l
-DO-1
-DO-l
-DO-
[
l i
I I
I
{
l 4
1 ~ 32.s 1
-DO-I
-DO-1
-DO-I
-DO-
[
l i
I I
I I
[
l 5
l 32.9 l
-DO-I
-DO-I
-DO-l
-DO-1 I
I i
i i
l i
I 6
I 61.1 l
-DO-l 150-0 l
Hopper Compartment l
-DO-1 I
I I
I I
I i
l 7
1 61.2 1
-DO-1
-DO-I
-DO-1
-DO-
~
I I
I 1
I I
I I
I 8
1 61.3 i
'DO-l
-DO-1 Radwaste DH&V Equipment I
-DO-1 I
l I
l l
Compartment l
l 1
1 I
I I
I I
I 9
I 61.4 1
-DO-1
-DO-1
-DO-l
-DO-1 I
I I
I I
I l
l 10 1
61.5 I
-DO-1
-DO-1
-DO-1
-DO-l l
l l
1 1
I I
i 11 1
61.6 l
-DO-l
-DO-I
-DO-l
-DO-1 I
I I
I I
I I
l 12 1
61.7 l
-DO-I
-DO-1
-DO-l
-DO-1 I
I I
I I
I I
i 13 1
61.8 1
-DO-l
-DO-I
-DO-1
-DO-I I
I I
i i
l i
I 14 l
78.1 l
-DO-l 165-0 i
Centrifuge Room l
-DO-1 I
I I
I i
l l
l 1
I I
I I
I I
I I
I I
I I
I l
I l
l I
l' h
T-29/2
- 1 C/I M
ewe 46 - s6 v APPENDIX "B"
SUMMARY
'OF MASONRY WALL (NON-SAFETY RELATED)
PEACH BOTTOM ATOMIC POWER STATION UNITS 2 & 3 ISERIALI WALL DESCRIPTION I
l NO.
lWALL NO.
I BUILDING l ELEVATION I LCCATION I
' BASIS FOR CLASSIFICATION I
I I
I I
l l
l 15 l 78.2 l Radwaste i
165-0 l
Centrifuge Room i
Engineering Review I
I I
I I
I l 16 1 45.3 l Reactor, i
135-0 l
Steam Pipe Tunnel l
Plant Walkdown & Eng. Rev.
l l
l Unit 2 I
I l
1 I
1 I
I I
l 17 1 45.5 l
-DO-l
-DO-1
-DO-I
-DO-1 I
f I
I I
i 18 1 75.1 1
-DO-l 165-0 1 Clean Up Recirc. Pump Room l
.-DO-1 I
I I
I I
l l 19 l 75.2 l
-DO-1
-DO-1
-DO-l
-DO-I I
I I
I I
I 20 1 75.3 l
-DO-I
-DO-l
-DO-1
-DO-I I
I I
I I
l 21 1 75.4 l
-DO-1
-DO-1
-DO-I
-DO-1 I
I 1
I 1
I 22 1 75.5 1
-DO-I
-DO-1
-DO-I
-DO-I I
I I
I I
I 23 1 75.7 l
-DO-I
-DO-I
-DO-1
-DO-1 I
I I
I I
I 24 1 76.1 l
-DO-I
-DO-I Regen. Heat Exchanger 1
-DO-1 I
I I
i 1
1 25 I 76.2 l
-DO-I
-DO-I Non Regen. Heat Exch. Room I
-DO-1 I
I I
I I
l 26 1 76.3 l
_-DO-I
-DO-I
-DO-1
-DO-1 I
I I
I I
i '
I 27 1 76.4 l
.-DO-I
-DO-l Transfer Pump Room 1
-DO-1 I
I I
l 1
I 28 1 76.5 l
.-DO-l
-DO-l Backwash Rec. Tank Rocm l Plant Walkdown & Eng. Review I
l i
I I
I O
.T-29/2 Q
01 N
P
APPENDIX*B" SUMMAR[ OF MASONRY WALL (NoN-SAFETY RELATED)
PEACH BOTTOM ATOMIC POWER STATION UNITS 2 & 3 ISERIALI l
WALL DESCRIPTION l
[
l No.
l WALL No. I BUILDING l ELEVATION l LOCATION I
BASIS FoR CLASSIFICATION I
I i
l I
i I
[
l 29 1 76.11 I
- Reactor, i
165-0 I
Transfer Pump Room l
Engineering Review
[
l l
l Unit 2 1
l
[
l I
i l
i i
[
l 30 l 97.1 1
-DO-l 195-0 1
Prefilter & Filter l
Plant Walkdown & En'g. Review l
l l
~
l l
l Compartments l
l l
l l
l 1
1 I
I 31 l 97.0 1
-Do-I
-Do-I
-Do-I Plant Walkdown I
I I
I I
I l
1 l 32 l'97.3 1
-Do-1
-Do-I
-Do-l
-Do-l l
l 1
1 I
I I
i 33 1 97.4 l
-Do-l
-Do-l
-Do-1
-Do l
I I
I I
I I
I l 34 1101.1 1
-Do-l 234-0 1
Refueling Floor I
-Do-1 I
I I
I I
i I
I 35 1102.1 I.
-Do-1
-Do-1
-Do-I
-Do-1 I
I I
I I
I I
I 36 l102.2 l
-Do-I
-Do--
I
-Do-1
-Do-1 I
I I
I I
I I
I 37 l102.3 1
-Do-1
-Do-1
-Do-l
-Do-l I
I I
I I
l I 38
-1102.4 l
-Do 1
-Do-I
-Do-I
-Do-1 l
I I
I I
I I
1 39 1102.5 l
-Do-1
-Do-l
-Do-1
-Do-I' I
I I
I I
I i 40 1102.6 l
-Do-1
-Do-1
-Do-I
-Do-1 1
I I
I I
2 l 41 1102.7 1
-Do-1
-Do-1
-Do-1
-Do-I i,.,. n m.,,m.
1 I
l l
I u. &.
.w I 42 _l102.10
..I
._-Do-I.
-Do-I __
_ -Do
_.. _.._ I
-Do-1 I
I I
I I
C
(
T-29/2 g
i
APPENDIX "B" 7
SUMMARY
OF MdSONRY WALL (NON-SAFETY RELATED)
~
PEACH BOTTOM A'tOMIC POWER STATION UNITS 2 & 3 ISERIALI I
WALL DESCRIPTION I
l NO.
lWALL NO. I BUILDING l ELEVATION l LOCATION l
BASIS FOR CLASSIFICATION I
I I
I I
I l 43.
1102.11 i Reactor, 1
234-0 l
Refueling Floor i
Plant Walkdown I
I I Unit 2 I
I i
I I
I I
i l
l 44 l406.3.
I Reactor, i
135-0 i
Neutron Monitoring Room l
Plant Walkdown & E'ng. Rev.
1 I
l Unit 3 I
1 l
l l
I I
I I
l 45 1406.4 l
-DO-I
-DO-I
-DO-l
-DO-
[
l i
I I
I I
l 46 1406.5 l
-DO-l
-DO-l Steam Pipe Tunnel 1
-DO-I I
.I I
I I
l 47 I406.7 1
-DO-I
-DO-l
-DO-l
.-DO-
[
l i
I I
i
-1
(
l 48 1406.8 l
-DO-I
-DO-l
.-DO-l
-DO-
~
[
l i
I I
I i
[
l 49 1409.1 1
-DO-l 165-0 1 Clean Up Recirc. Pump Room l
-DO-
[
l i
I I
I I
(
l 50 l409.2 l
-DO-1
-DO-I
-DO-l
-DO-
[
l i
I I
I I
[
l 51 1409.3 l
-DO-1
-DO-1
-DO-l
-DO-
[
l i
'l l
i I
(
I 52 1409.4 1
-DO-l
-DO-1
-DO-l
-DO-0 i
i i
i i
l I
[
l 53 l409.5 l
-DO-I
-DO-
.I
~
-DO-1
-DO-
[
~~
I I
I I
i l
[
l 54 1409.6
,1
-DO-I
-DO-l
-DO-I
-DO-
[
l i
I I
I i
(
l l 55 1410.2 l
-DO-l
-DO-I Backwash Rec. Tank Room l
Engineering Review
[
1 1
I l
l l
1 0
l 56 1410.3 1
-DO-I
-DO-l Transfer Pump Room l
-DO-0 I
I I
I I
I l
l O
l T-29/2 O
l
%l CR
.N.
Shtot,5 of 6
, APPENDIX "B"
!bOMMNRY OF N SONRY hfALL (NbN-SdFETYRELATED) y
-PEACH BOTTOM ATOMIC POWER STATION UNITS ~2 & 3
- F
~
. -...... _ _.. _. _ _ _.. =
u lSERIALI I
WALL DESCRIPTION l
i NO.
1 WALL NO.-l BUILDING l ELEVATION l LOCATION l
BASIS FOR CLASSIFICATION I.
I I
I I 57 1410.4 I Reactor, i
165 1 I
l Hon Regen. Heat Exch. Room i Plant Walkdown & Eng. Rev.
l l
l Unit 3 l
l l
1 1
I I
l l
l 58 1410.5 1
-DO-I
-DO-l
-DO-l
-DO-1 I
l
-1 I
I l 59 1410.11 l
-DO-l
-DO-l Transfer Pump Room 1
-DO-I I
I I
I I
I 60 1413.1 l
-DO-l 195-0 l
Storage Area l
Plant Walkdown i
I I
I I
I l 61 1413.2 l
-DO-I
-DO-1
-DO-l
-DO-1 I
I I
I i
1 62 1413.3 1
-DO-I
-DO-1
-DO-1
-DO-1 I
I I
i 1
1 63 1413.4 l
1 I
I
~- DO-l
-DO-1
-DO-I
-DO-l I
i 1 64 1413c5 1
-DO-1
-DO-I
,-DO-1
-DO-1 I
i i
i I
I 65 1413.'5 l
-DO-I
-DO-I
-DO-I
-DO-1 I
e i
I I
i l 66 1414.1
?
-DO-I
-DO-I Prefilter & Filter l
Plant Walkdown i Engr. Review I
I i
l l
Compartment I
I i
I I
I I 67 1414.2 1
-DO-I
-DO-I
-DO-l Plant Walkdown i
I I
I I
I I
1 1
I I
l I 68
.1414.3 1
,-DO-1
-DO-I
-DO-I
,DO-
.g 1
I I
I I
I Is 1414.4 1
_-DO-I
,-DO-1
-DO-1
-DO-i I
l l
1 i
I 1
-l 70 1417.1 -- I
--DO-
--l
-234-0 -
-Re f ue l ing Are a --
- - - l - - -- - --
DO-l l
I I
I I
i
,T-29/2 d.
9 C/t i
N 1
e i
o.
.j.,.s
.,. APPENDIX "B"
SUMMARY
OF MASONRY WALL (NON-SAFETY RELATED) j PEACH BOTTOM ATOMIC POWER STATION UNITS 2 & 3
~
ISERIALI I
WALL DESCRIPTION l
l NO.
lWALL NO. I BUILDING l ELEVATION l LOCATION l
BASIS FOR CLASSIFICATION I
I I
I I
I
~
I 71 1418.1 i
- Reactor, i
234-0 i
Refueling Area i
Plant Walkd.own l
I I
Unit 3 I
l l
I I
I I
I I
I 72 1418.2 1
-DO-1
-DO-1
-DO-1
-DO-1 I
I I
I l
l 73 1418.3 l
-DO-I
-DO-1
-DO-I
-DO-l 1
1 I
l r I
+
.I 74 1418.4 1
-DO-1
-DO-l
/T
-DO-I
-DO-I I
I.
I l
l l 75 1418.5 1
-DO-I
-Do-1
-DO-I
-DO-l I
I I
I I
I l 76 1418.6 l
-DO-1
--DO-I
-DO-1
~ -DO-I i
1 I
I I
I
-DO-I
-DO-I I
1
-DO-1
-DO-l l 77 1418.7 I
I l
I 78 1418.8 l
-DO-I
-DO-I
-DO-I
-DO-I I
I I
I l
I 79 1418.9 l
-DO-l
-DO-I
-DO-l
-DO-I I
I I
I I
I 80 1418.12 1
-DO-I
-DO-1
-DO '
I
-DO-1 I
I I
l I
J 1 81 1418.13 1
-DO-I
-DO-l
-DO-I W
-DO-1 I
l i
I I
I*
I I
I I
i
- NOTE:. Based on Engineering review, all masonry walls of Recombiner Building and masonry walls of Radwaste, Turbine, and Reactor Building (Units 2 & 3) not listed'above,
.are non-safety _related.
h.
m.
O M
~
Cn
cSov R fct&
~
PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 SHIELDS L. DALTROFF ELECTRIC PR UCION July 2, 1980 Docket Nos.: 50-277 50-278 IE Bulletin 80-11 Mr. Boyce H.
Grier, Director Office of Inspection & Enforcement Region I U.S.
Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Dear Mr. Grier:
This is in response to your letter of May 8, 1980,which forwarded IE Bulletin 80-11, and requires a response to items 1,
2a, and 3 of the Bulletin within 60 days of the issue date.
A response to item 2b of the Bulletin will be forwarded within 180 days of-the issue date of the Bulletin.
The actions requested in items 1, 2a, and 3 of the Bulletin, and our responses are listed sequentially below.
Action to be Taken by Licensee:
1.
Identify all masonry walls in your facility which are in proximity to or have attachments from safety-related piping or equipment such that wall failure could affect a safety-related system.
Describe the systems and equipment, both safety and-non-safety-related, associated with these masonry walls.
Include in your review, masonry walls that are intended to resist impact or pressurization loads, such as missiles, pipe whip, pipe break, jet impingement, or tornado, and fire or water barriers, or shield walls.
Equipment to be I
considered'as attachments or in proximity to the walls shall include, but is not limited to, pumps, valves, motors, heat j
exchangers, cable trays, cable / conduit, HVAC ductwork, and i
l electrical-cabinets, instrumentation and controls.
Plant surveys, if necessary, f or areas inaccessible during normal
r Mr. Boyco.H. Grior Page 2 plant operation shall be performed a*.
the earliest opportunity.
Response
All masonry walls at Peach Bottom Atomic Power Station which are in proximity to or have attachments from safety-related piping or equipment are identified in Appendix A.
Proximity is defined as being within a c stance equal to the wall height, such that wall failure could render the safety-related system inoperable.
Safety-related systems and equipment associated with these masonry walls are also described in Appendix A, together with the wall location, its primary function (shield wall, partition, etc.), and the tentative priority for re-evaluation.
Non-safety-related systems or equipment such as conduits, cable trays etc. attached to these walls have been surveyed and all data related to these systems have been obtained in order to establish imposed loading on masonry walls for use during the re-evaluation analysis.
The information shown in Appendix A was obtained by performing a plant survey.
Appendix B lists masonry walls which do not have safety-related systems / equipment either attached to them or in proximity.
The information shown in Appendix B was obtained either by plant survey and/or by drawing review.
A visual, walk-through verification will be made to confirm the drawing review.
Should this investigation identify any walls which affect safety-related systems or equipment, those walls will be surveyed in detail, added to Appendix A, and included in the re-evaluation program.
2.
Provide a re-evaluation of the design adequacy of the walls identified in Item 1 above to determine whether the masonry walls will perform their intended function under all postulated loads and load combinations.
In this regard, the NRC encourages the formation of an owners' group to establish both appropriate re-evaluation criteria and where necessary, a later ccnfirmatory masonry test program to quantify the safety margins established by the re-evaluation criteria (this is discussed further in Item 3 below).
a.
Establish a prioritized program for the re-evaluation of the masonry walls.
Provide a description of the program and a detailed schedule for completion of the re-
. evaluation for the categories in the program.
The completion date of all re-evaluations should not be more than 180 days from the date of this Bulletin.
A higher priority should be placed on the wall re-evaluations considering safety-related piping 2-1/2 inches or
Mr. Boyco H. Grior Page 3 greater in diameter, piping with support loads due to thermal expansion greater than 100 pounds, safety-related equipment weighing 100 pounds or greater, the safety significance of the potentially affected systems, the overall loads on the wall, and the opportunity for performing plant surveys and, if necessary, modifications in areas otherwise inaccessible.
The factors described above are meant to provide guidance in determining what loads may significantly affect the masonry wall analyses.
Response
The re-evaluation program will consist of a structural analysis of the masonry walls identified in Appendix A using an appropriate re-evaluation criteria which will define loads considered, load combinations and allowable stresses.
The following parameters will be considered in establishing priorities for wall re-evaluation:
a)
Walls which have largcr number of safety-related systems on them or in their proximity.
b)
Walls which are subjected to heavier loading, and c)
Walls which, in terms of height, length and thickness are judged to be more critical than others.
Tentative re-evaluation priorities are indicated for each wall in Appendix A.
Priority 1 and Priority 2 indicate the walls which will be analyzed first, followed by Priority 3 and 4 in that order.
The re-evaluation of masonry walls designated as Priority 1 and Priority 2 is expected to be completed by mid or late September, 1980.
Re-evaluation of Priority 3 and Priority 4 masonry walls is expected to be completed by mid or late October, 1980.
A report of the re-evaluation will be submitted by November 4, 1930, as required by the Bulletin.
3.
Existing test data or conservative assumptions may bc ased to justify the re-evaluation acceptance criteria if the criteria are shown to be conservative and applicable for the actual plant conditions.
In the absence of appropriate acceptance criteria a confirmatory masonry wall test program is required by the NRC in order to quantify the safety margins inherent in the re-evaluation criteria.
Describe in detail the actions _ planned and their schedule to justify the re-evaluation criteria used in Item 2.
If a test program is necessary, provide your commitment for such a program and a
u Mr. Boyco.H. Grior Page 4 schedule for submittal of a description of the test program and a schedule for completion of the program.
This test program should address all appropriate loads (seismic, tornado, missile, etc.).
It is expected that the test program will extend beyond the 180 day period allowed for the other Bulletin actions.
Submit the results of the test program upon its completion.
Response
Justification for re-evaluation criteria will be submitted with the re-evaluation report within 180 days of the date of the Bulletin.
Justification will be based on reference to effective codes and established standards of practice related to concrete and masonry design typically used throughout the industry.
It is anticipated that such justification will be considered appropriate, except as required to determine project unique structural properties such as collar joint strength and any other properties for which test data is not available or cannot otherwise be determined.
Should these unique properties need to be determined by testing, adequate test procedures will be developed as required.
Very truly yours, f
^
&l"}fl Attachments:
Appendix A Appendix B cc: United States Nuclear Regulatory Commission Office of Inspection and Enforcement Division of Reactor Operations Inspection tshington, DC 20555
COMMONWEALTH OF PENNSYLVANIA :
ss.
COUNTY OF PHILADELPHIA
\\
S.
L.
Daltroff, being first duly sworn, deposes cnd says:
That he is Vice President of Philadelphia Electric Company; that he has read the foregoing response to IE Bulletin 80-11 and knows the contents thereof; and that the statements and matters set forth therein are true and correct to the best of his knowledge, information and belief.
,,f
,f L -j -
Subscribed and sworn to before me this c/ " day of
,\\
o ry Publi
~b s _.
~
ZABETH M.8 Not Public, Phila., Phil y
ission Empires Jan.341982
APPENDIX'As ggg g gg 7
SUMMARY
f r MASONRY NALLS (SAFETY RE1ATED)
PEACH SOTTOM ATOMIC POWER STATION UNITS 2 & 3
( SEE PAGE 7 FOR HoTES)
SERIAL NALL m f- - xiri-h-Whil.'S PRDfJtt M IEIA N SY!MD S M N 3AyTIT M2ATED SV!nD6/EGIIpeft 3M indrargyt; l
No No (I)
SUILDING 311V.
IDCATION PWCTIGI ~
ATTAOIED TO M (II) pggg3MITY W MIL (II)
IE-Evng a r3Gi PtuCRIW l
1 15.1
'Beaveste 88-o &
Standby one Treatment Shielding 7
Standby one Treatment System (Fame, Filters 3
91-6.
ama and Duete) g 2
15.2
-W
-Do-
-Do-
-Do-7
-Do-3 3
16.1
-W
-Do-Benetor Core Isolation
-Do-None Beactor Core Isolation Coolig 3
Cooling Pump Area, Unit 2 Pump hrbine, that 2 4
16 2
-Do-
- Do-
-Do, Unit 3
--Do-Non.
-Do.thtt 3 3
i 5
16.3
-Do-
-Do-N ete sludge Tank noom
-W None seresuard meisted Conduit 3
6 32.1
-Do-116-0 Conaeneste Tank & Puep
-Do-7, lo pone 3
aoose 7
32.2
-Do-
-Do-
-Do-
-Do-None le80T AC Power 3
8 32.3
-Do-
-Do-Condeneste Pump Area
-Do-1, 7 BGT & DCIC 3-9 32.4
-Do-
-Do-
-Do-
-Do-
-Do.
-Do-3 10 32.5
- Do-
-Do-
-Do-
-Do-
-Do-
-Do-3' 11 12.10
-Do-
-Do-Filter Hold.ing Peep Rooma Chielding.
7 Bone 3
& Fuel Fool Filter Dominera11ser Area 12 32.11
-Do-
-Do-
-Do-
-Do-None 1-*
3 13 32.12
-Do-
-Do-
-Do-
-Do-None i -7..
3 14 56.1
-Do-135-0 Fw control noom & F11ter
-Do-6 pone 3
Aid Tank & Ptemp Area 15 78.3
-Do-165-0 Redeste su11 ding -
- -Do-17 aners, swer Filter up** ins 3
5 FanBm 16 25.1 Turbine (Con-116 0 Switchgear & Conventional Partition 2, 3, 8 thru'll Righ Pressure and Bnergency Barrice Water 2
trol.8tructure)
Chem. Imb Lines and Safeguard Conduite i
2, 3 l
17' 25.2
-Do-
-Do.
-Do-
-Do- '
-Do.
2 i
18 leo.1
-Do-135-o Bettery Room, Unit 2 Fire Beatstance 8, 10, 12, 14 '
'B6 ttery Rack, Channele A & C, Unit 2 1-0 5
O O4 G1 NP
,,4
,m
.'APPEN0!X A*
Sheet 2 Ef 7 1*[
SUMMARY
FF MASONRY WALT.S (SAFETY RFt.ATED)
PEACH BOTTON ATOMIC POWER STATION UNITS 2 & 3 saprAz.
war.r.
=n. m,rarmm mu.'s PRrwatt
- - mmm SAmY MIATTD SYSTEME/tGJIPteft IN ttNERr:M uO no (r) suit.oruc nEv.
roCAT10m rwerzm A2wan so m:2. (rr) nomm e mu. (II)
- -f razop m 19 40.2 Turbine 135- 0 Switchgear Roam Fire Resistance 2, 7, 9, 10, 12, 13, 14, 17 1 kV Suitetwear, Channel C, & Ig:C 1
3 (Control Unit 2 Channel C, Unit 2 Structure)
^
20 40 3
-DO-
-DD-
-Do-
-DO-1, 2, 3, 6 thru' Ib' 17.
k kV switchgear, Channel D, thtt 2 1
21 40.4
-Do-
-DO-
- %, Unit 3
-DO-2, 8, 9, 11, 12,13, 17
-DO., Channel D, that 3 1
22
, 40.5
-W
-DO-
-Do, Unit 3
-DO.
3
,j,7,9,10,12,13,
-D0, Channel C, that 3 1
23 40.6
-DO-
-n Battery soon Unit 3
-DO-1,8,10;12,ik Battery asek, Channela A & C, Unit 3 1
24 40.7
-DO-
-DO-Battery Room, thtt 2
-DO-10, 12, 14 Battery Raek, Channels A, B, C. & D.
1 Unit 2 and Fuse Boxes Channels A &C.
25 40.8 '
-DO.
-DO.
switc'hdear Roam, that 2
-DD-7, 10, 12, 14
% kV Seitchgear Channele A & C,' Unit 2 1
26 40 9
-DO-
-DO-
-DO., tha t 2
-DO-7, 9 thru'13
-DO., Channels B & D, Unit 2 1
27 40.10
-DO.
-DO-
-DO, that 3
-DO-8, 9, 10, 17
-DO, Channela B & D, Unit 3 1
28 40.11
-DO-
-DO-
-DO, Unit 3
-DO-2, 3, 7 thru'12,14,17
-DO, Channels A & C Unit 3 1
29 kO.12
-DO.
-DO-Battery Room, that 3
-DO-1, 8, 10, 12 Battery Back, Channele A, B, C. & D.
1 Unit 3 and Fuse Boxes Channele A &C 30 40.13
-DO-
-DO-Battery Roca & Switch-
-DO-6, 8 thru'12, ik,17 Battery pack, Channela A & C, EC 1
gear, thit 2 Channel C, Fuse Boxes Channels, A 4 G 4 kV Switchgear, Channel C, Unit 2 31 40.14
- DD-
- DO-
-DO-
-DO-2, 8, 10, 11, 12, 14 Bettery Rack, Channels B & D, MCC 1
Channet. A. Fuse Boxes Channels B 4 D.
4 kV 8vitchgeer, Channel A. Unit 2 32 40.15
- DO-
- DO-Switchgear Rocus, Unit 2
-DO-2, 9, 11, 12 4 kV Switchgear, Channels C & D, 1
Unit 2 g
33 40.16
-DO-
-DO-Switchgear Rocas. Unit 2
-DO-2, 8 thmu' 1%
k kV Switchgear, Chann Is A & B, 1
Channel B, Unit 2 l
34 40.17
-DO-
-DO-evitchgear Room, Unite 2
-DO-2, 8 thru'13 4 kV Switchgear, Channels D & D, Unita 2 1
8
&3
&3 l
n.
e,-
1 I
C C<
U
@F
PEACH BOTTOM ATOMIC POWE7 STATION UNITS 2 &
3
~EiIAL WALL' N'- TE-~,ut'Mm MO NO (!)
SUIT. DING E11V !
MM2.'S PRDfJg WM UNMI t
I4 CATION ND3 n,,*
N N BYSI M M N IN M AT M l
I I
' 35 b0,18 Turbine 135-0 PRIOR 2TY
- f.. '
(Control Switchgear Rom, thite 2
.. ~ * '
Fire Resistance 2, 9, 11, 12
&3 i
- *l.
Structure) h kV Switchgear, Channele B & S, Unite 2 i.
.+ r.
& 3, 1
f l
36 bo.19
-DO.
-W Switchgear poem, Unit 3
- >,,. [
-h 8, 9, 11, 12, 17 tt' 37 40.20
- DO-I
-W, Channele C & D, MCC Channel D, j.
-W
-DO-y thtt 3 1
-h
{p At',
2, 7, 8, 9, 11 thru' lb D
, b0,21'.'..Q ;,
-DO,3Channele A &'3, M % Channel 3,
-Do-Switchgear & Battery thtt Roane, Unit 3 1, 7, 8, 12, 1b 1
-W
{G,* -(
r' Battery Rock, Channele A & C, Fuse BoEen
- , i.
39 b0.22
-DO-
.s Channele A AC 1
y + %f -
-n
-w b, 8, 10, 11, 12, Ib b kV bwitchgear, Channel C, Llhtt 3
-n
'. )
r Battery Rack, Channels 8 & D, MCC gf, ho bO.23
-DO-
-W Channel A. Buee Bones, channele B p D 1
l b kV Switchgear, Channel A, tha t 3 l
Switchgear Roaa, that 2 7
-DO-S1 bo.24 b kV evitchgear, Channel D, thit 2 and
- h.,.:
None p
H&V Iuct 3
-DO-F ^,".I7
-h e7
-DO, Unit 2 1
h.3,
-W b2 bo.25
-W
-DO-None
-w
-DO, Unit 3 3
OP
-.5?
-n None 43 40.26
-Do-
-n, thit 3
-DO, tha t 3 N ~ t -e
-n
-DO.
3 sone y, ' f.,
Lb bO.27
-DO.
-n
-DO, thtt 2 3
feg-
-DO-a-
e
-DO-None i5 b0.28 4 kV evitchgear & Mcc Channel A, that 2
-w
-DO.
-DO.
3
'?
-Do, Unit 3 b kV avitchgear & Mcc Channel 3, that 2 b' A."s.
'e
-DO.
sane 6
40.29
-DO-
-DO.
3
.a
-po.
None g
7 bO.30
-DO.
-DO-
-DO.
4 kV avitchaear & N:C Channel a, unit 3 p-3
. y
-DO.
None 3
68.1
-DO-150-0 Cable 8preading Roan 4 kV avitchgear & N:C Channel A, thit 3 L,. -
i 3
('(A.<
F #. '
-W 1, 8, 9, 11, 13, 17 68.2
-DO-
-DO.
-DO-Safeguard Troya
- .4,. )
1
-W 1
68 3
-DO.
-n
-DO-
- W i..s 5{
I
-DO-2 68.4 1 thru'5, 7. thry'12,14,18
\\
.w,
-DO-
.e
-DO-
-W
-DO-1
, f-
-DO.
1 thru'.7, 9 thru'17 68.5
-DO
-DO-
- DO.
I
- DO.
t [4,J Shielding Mona
-DO-(
2 5
lt:
-u' t;,-
- f
~
(e.-
t,. jay b
'f
$m ILb 8
f-. -*p
$x i
s l 2 s*.p p.
C
.d(
o-
- .N e}
k. l4,.,
w 6
$j..
l N
!1 P
s i k
,, m 7. c.g.
o A N. ' lT ? ;
3 3
p ynq d w.[zA. 3., }-}1. 3, pu '.%r:. dier ~., b, 'tQ^N
.e
.x-
..;d
,s b
(
APPENDiM"A
' Sheet b af 7
.f tMMARY OF MASONRY WALLS (SAFETY RE1ATED)
PEACH BOTTOM ATOMIC POWER staff 0N UNITS 2& 3
~
SERIAL WALL WF TETRIPfffM Wall'S PRIMfJtt SAfuY M2M12) SYSnMi/IEUIIMNT SAfMT Mu2U) SYUrtMi/IENIPteNF IN DNTRTIVE ItNCTIO4 ATT G 2) M NAIL (II) pgogIMITY & WALL (II)
N EVN13t104 NO NO (I)
BUILDINF.
122V.
IDCATION PRIOR 11Y 53 71.1 Turbine 165-0 Contal Rocue Shielding None Control Ihale, Defeguard 7reys 2
(Control
. Structure) 5%
45.1
- Reactor, 135-O' Isolation valve Comp.
-go.
2,3,5 m) Containment Isolation valves and 1
Unit 2 Assoc. Conduite b) CRD Insert and Withdrawal Lines 55 45.2
-Do.
-Do.
- Do-
-DO.
2, 3 k', 10, 15
-DO-t 56 h5.4
-Do-
-DO-Steen Pipe Tunnel
-Do-5, 15, 18 kelv on steam Line "A" and Related 2
- Conduite s
57 45.6
-Do.
.00-
-Do-
- Do-None 5, 15, 18 2
58 75.6
-DO-165-0 Isolation valve *.ea
-Do-None Containment Isolation Valves and'conduite b
& RWCU lenhage detection temp. element 59 76.6
- Do.
-Do-Load Centere Fire Ree1 stance 9, 10 Electrical Load Center b
60 76.7
-DO.
-DO-
-Do.
-DO-None
.Do, 1 thru 7, 9, 10, 15, 17
~
1 61 76.8
-D0-
-D0-
-DO-
-DO-None Electrical Load Center 4
4i ns 62 76.9
-DO-
-DO-
-Do-
-DO-some
-Do,1 thru 7, 9,10,15 1
8 6')
76.10
.'DO.
-W
- Do-.
-DO-2 Electrical load Center 4
64 87.1
-DO.
180-0 Isoletten Valvt Compartment shielding pone Containment Isolation valves, RWCU 4
Leakage Detection Temp. Element i
65 102.8
- Do-234-0 Refueltas..
-n 6
None 4
., 6 Floor e
66 102.9
-Do-
-DO-
-lo.
-DO-6 None 2
67 kb6.1
- Reactor, 135-0 Toolation valve Comp.
-Do-2,'3, 15 m) Contatrument Isolation velves & Conduite 1'
IAsit 3 b) CRD insert and Withdrawal Linee 68 406.2
-Do-
-Do-
-Do-
-DO-2 thru'5, 7, 12
-DO-1 e
a l
OO s1 Cit
.N<
q v
M
^
vW
,. APPEtIDIX'A Sheet 5 a f 7
- . SUMMA"Y (P #4ASONRy pat.LS (SAFETY RELhTED)
- . PEACH BOTTOM ATOMIC POWER STATION UNITS 2 & 3 SERIAL WALL tetrl MPnm 9*
WhlL'S PRDfJN '-
SAFEIT N2A21D SYS!Dti/DQUliTDir 3Artty ;g2A113 g/yggypfNP IN TDf!RTINE li.NCTim
- .. ATTAOED TO WhtL (II)
{ g pgogggTy y wgJ, (II) mg ;
NO NO (I)
BUILDING IIEV. l IDCATION PRIORI 1Y eb e
69 bO6. 6 -
Reactor, thitt 3 135-0 Steam Pipe Tunnel Shielding None MSIT on Steam Line "A" and Related Conduite 4
70 406.9
-DO-
-W
-DO-
-DO-5,12 MS!Y on Steam Line "A" and Related Condaite 2
71 406.10
-Do-
-DG-
-DO-
-DO-3, 5, 10, 12
-W 1
72 40).7
-DO-165-0
!aolatiors Valve Area
-DG-None Contatriment Isolaticsi Valve & Associated ',
4 Conduite and RWCU Leakage Detection Temperature Element 73.
klo.1
-DO-
- Do-t Regenerative Heat Ex-
-DO-5 Non*
4 changer Area 74 b10.6
-DO.
-DO-Load Center Fire Resistance pone Electrical Imed Centere, 7,10,11 2
1
-to, 2,3,5,6,7,10,11.14,15 1
75 410.7
-DO.
-DO.
-DO.
-n none 76 bio,8
-DO-
-DO.
-DO-
- DO-None
-DO, 10,12 2
77 410.9
-Do-
-W
-DO-
-DO-None
.DO, 2,3,5,7,10,11,12.14,17 1
70 410.10 -DO-
-DO-
-DO-None
-DO ' 10,11,17 2
79 412.1
-DO.
180-0 Isolation Yalve Compart.
Shielding None Containment Ieointion Valve and Conduits.
b ment
& RWCU Leakage Detection Temp. Element s
80 418.10
-DO.
23te-C Renneling Floor
-Do-6 b
None 81 418.11-
-DO.
-D0
-DO.
-D0 6
.n 4
82 532.1 Imergency 158-0 neergency cooling Tower Fire Reelstance 4,8 Imergency Cooling water many and Load b
Cooling Centers' and Panels, EC Tower Oq 01 LO H'
.a
'e p-
=e(
.=
g g
e
l f
l l.
- ?h 9B o I
- fi N
O11Nw sU VNI
=
E w
IFR R
t 4
b 4
t o
e r
91Em N
I 7
N r
. e g
6 C
n t
i C
p ee I
P i
h S
SI e
r l
DU e
e t
T n
a S
a Y
P W
DM S
d ec n
i T
a v
2&
r A
s 2
r e
e e
S s
t f
y n
Y e
c t
n C
T o
e o
f d
D s
D.
A a
re S
o n
t a
N M
NI I
I 3
I
)
"E 2
T N
TA S
I T
E I
R N
e e
n n
Y I
N o
o T
N N
N E
O F
I 8
8 A
T d
A i
T F
S A
S e
O L
R e
X L
E r
c t
n T
A W
J a
W t
D W
O.
DN N
s RI i
E s
SN P
P R
C e
P N
I R
o o
D O
A O
M D.
'L e
D S
O r
A T
M t
'M A
W y
F M
O OT Y
T r
R O
e A
B wo M
T M
H U
C gn S
A N
i E
O l
P I
o T
o A
C C
y m
D c
a I
n o
h.
e o
R s
t u
r p
l e
m i
e u
r m
P m
i V
o o
0
- A O
r 8
2 D
r M D.
5 1
m 1
1
~
re t
ae G
wr N
y u
gc I
c D
ng e n o
iu o L
sir tr D.
D I
rl e at U
e ow lS S
h oo u
t CT cp rm iu cP
)
L (I L
2 3
1 2
AO 2
2 6
6 WN 3
3 8
8 w
5 5
C C ~
L A
IO RN 3
4 5
6 E
8 8
8 8
S
' APPDlIII 'A' Sheet 7'of 7
.L
'SLAe4ARY OF MASCHT t'ALIA (SAFETY REIATED) 4-PEACH COTTOM ATOMIC POWER STATICiJ UNITS 2&3 NOTM t.
P '
Each well le designated by a unique number such that the 9
first part indicates the Civil / Structural Drawing number and
+
the second port gives the well number on that particular drawing, e.g. well No. 45 2 andleates vall-member 2 on Clett/ structural Drawing No. b5.
II. Safe *,y relat.ed systems are destynated as below 1.
Reactor Core Isolation Cooling f RCIC)
' 2.
Reactor Heat Removal (RHR) 3 Core Sprey.,
b.
High Pressure Coolant Injection (HFCI) 5.
Primary Containment Isolation 6.
Process / Area Radiation Monitortr4 -
7.
standby Gee Treetsent 6.
Energency r * **ee Water (EN) 9 Emergen y k.el Generator 10.
Bareguard bt. VAC Power (MCC, LC)
- 11. Safeguard b kV Power
- 12. Dereguard 125/250 VilC Power 11 Safeguard 120 VAC Power Ib. Sereguard 2b VDC Power
~
- 15. Containment Atmospheric Dilution (CAD)
- 16. Reactor Protection System (RPS)
- 17. Safeguard HVAC Systen
- 18. Stees. Leek Detection Byates S
- w-w oes,,,.
r,-
D4 Cn if FS'
=
APPENDIX "B" y.., 1, r......
SUMMARY
OF MASONRY ~ WALL (NON-SAFETY RELATED)
PEACH BOTTOM ATOMIC POWER STATION UNITS 2 & 3 s
y ISERIALl l
WALL DESCRIPTION I
.(
I NO.
lWALL NO.
l-BUILDING l ELEVATION l LOCATION l
BASIS FOR CLASSIFICATION
(
i
(
.l.
I I
I I
I
(
l-1 l
24.1 1
Turbine I
116-0 i
Valve Operating Area-l Plant Walkdown & Eng. Review
{
I I
I I
I i
0 l
2 1
32.6 i
Radwaste I
.-DO-ICondensate Pump & Tank Rooms l Engineering Review
(
l I
I I
i 1
C 1
3 1
32.7 l
-DO-I
-DO-I
-DO-1.
-DO-
[
.I I
I I
I I
.[
1 4
1 32.8 l
-DO-1
-DO-I
-DO-I
-DO-l 4
I I
I I
I I
O
'l i
l 5
1 32.9 l
-DO-1
-DO-l
-DO-I
-DO-1
'l I
I l
l I
l 6
1 61.1 1
-DO-l 150-0 l
Hopper Compartment I
-DO-1 I
I I
I I
I l
l 7
l 61.2 1
-DO-I
-DO-I
-DO-1
-DO-
~
l I
I i
i l
I I
i I
8 l
'61.3 1
-DO-'
l
-DO-I Radwaste DH&V Equipment I
-DO-l l
l l
1 l
Compartment I
I I
I I
I l
i I
I 9
I 61.4 1
-DO-1
-DO-1
-DO-l
~DO-1 I
I I
I I
I l-I 10 1
61.5 l
-DO-I
-DO-I
-DO-1
-DO-
.I I
I I
I I
I l'
i l 11 1
61.6 l
-DO-l
-DO-I
-DO-l
-DO-1 I
I I
I I
I I
I 12 1
61.7 l
-DO-l
-DO-1
-DO-I
-DO-I l
l l
l l
1 I
i 13 1
61.8 1
-DO-I
-DO-I
-DO-l
-DO-I i
i i
i i
i 1
-1 i
I 14 1
78.1 1
-DO-l 165-0 1
Centrifuge Room 1
-DO-l 1
I I
I I
I I
l l
1 I
l l
I i
I I
I I
I i
1 l
I I
I l
I i.
h T-29/2 s1 Cn s
M
APPENDIX "B"
~
SUMMARY
OF MASONRY WALL (NON-SAFETY RELATED) 9 PEACH BOTTOM ATOMIC POWER STATION UNITS 2 & 3 f
ISERIALI i
WALL DESCRIPTION l
I NO.
IWALL NO.
I BUILDING l ELEVATION l LOCATION l
' BASIS FOR CLASSIFICATION
_ l l
. 1 l
l l
i 15 l 78.2 i Radwaste i
165-0 l
Centrifuge Room i
Engineering Review I
I l
l 1
I 1-16 1 45.3
-l
- Reactor, i
135-0 l
Steam Pipe Tunnel l
Plant Walkdown & Eng. Rev.
I I
I Unit.2 l
l 1
l 1
1 I
I l
a l 17 1 45.5 l
-DO-I
-DO-1
-DO-I
-DO-I I
I I
I I
i 18 l 75.1 l
-DO-l 165-0 i Clean Up Recirc. Pump Room I
.-DO-I I
I I
I I
i l 19 l-75.2 1
-DO-I
-DO-1
-DO-I
-DO-1 1
I I
I I
I I.20 1 75.3 1
-DO-1
-DO-I
-DO-I
-DO-I-
l l
1 1
I u
l 21 1 75.4 1
-DO-I
-DO-I
-DO-1
-DO-1 I
I I.
I 1
1 l
l 22 1 75.5 l
-DO-1
-DO-1
-DO-l
-DO-1 1
I I
I I
I J
l 23 1 75.7 1
-DO-I
-DO-I
-DO-I
-DO-j i
I I
I I
!j l 24 1 76.1 1
-DO-l
-DO-l Regen. Heat Exchanger i
.-DO-I l
i I
I I
I I
l 1 25 1 76.2 1
-DO-I
-DO-I Non Regen. Heat Exch. Room l
-DO-4 I
I I
I I-I I 26 I 76.3 l
-DO-I
.-DO-l
-DO-l
-DO-1 I
I I
I I
h 1 27 l 76.4 l
.-DO-1
-DO-l Transfer Pump Room l
.-DO-d i
I I
I I
I d
l 28 1 76.5 l
. --DO -
1
-DO-I Backwash Rec. Tank Room l Plant Walkdown & Eng. Review i
I I
I I
I I
g)
(
i
.,T-29/2
.]
til F
N P
i
APP'ENDIX""B"
SUMMARY
OF MASONRY WALL (NON-SAFETY RELATED)
PEACH -BOTTOM ATOMIC POWER STATION UNITS 2 & 3 ISERIALl l
WALL DESCRIPTION l
[
l NO.
l WALL NO. l BUILDING l ELEVATION I LOCATION I
BASIS FOR CLASSIFICATION I
I I
I I
I I
O l 29 l 76.11 1
- Reactor, i
165-0.
l Transfer Pump Room i
Engineering Review
[
l l
I Unit 2 l
l 1
0 1
I I
I I
I O
l 30 1 97.1 l
-DO-l 195-0 l
Prefilter & Filter l
Plant Walkdown & En'g. Review 0
l l
~
l l
l Compartments 1
0 I
I I
I I
l 0
1 31 l 97.2 l
-DO-l
-DO-I
-DO-l Plant Walkdown O
I l
l l
l l
I i 32 l'97.3 1
-DO-1
-DO-l
-DO-I
-DO-0 I
I I
I I
I L
l 33 I 97.4 l
-DO-1
-DO-I
-DO-l
-DO l
I.
I l
l I
I i
l 34 1101.1 1
-DO-l 234-0 i
Refueling Floor I
-DO-1 1.
I I
I I
l l
l 35 1102.1 1,
-DO-I
-DO-1
-DO-I
-DO-1 I
I I
I I
I 36 l102.2 l
-DO-1
-DO-l
-DO-1
-DO-l l
l l
1 I
I I
I 37 1102.3 1
-DO-I
-DO-l
-DO-I
-DO-l 1
1 I
I I
l l
l 38 1102.4 l
-DO I
-DO-l
-DO-I
-DO-l i-1 I
l l
l l
1 l 39 l102,5 I
-DO-1
-DO-I
-DO-I
-DO-l 1
I I
I I
I I
l 40 1102.6 l
-DO-l
-DO-l
-DO-I
-DO-l I
l 1
l l
I 1
l 41 1102.7 I
-DO-1
-DO-I
-DO-1
-DO-
{
I I i,.. nn u; au-
- t.,
l w
.as..
u.,
,.s l
l l
l l 42._l102.10
..I
._-DO-I
-DO-
..I_
_. _ _. -DO
_....._____l.___..,_.
-DO-1 I
I I
I I
I I
e T-29/2 V
.311U U L.
"t UL U APPENDIX "B" m-
SUMMARY
OF MASONRY WALL (NON-SAFETY RELATED)
~
PEACH BOTTOM ATOMIC POWER STATION UNITS 2 & 3 l
ISERIALI I
WALL DESCRIPTION I
{
l NO.
IWALL NO. I BUILDING IELEVATION 1 LOCATION I
BASIS FOR CLASSIFICATION l
i I
i l
l l
l 43 1102.11 1 Reactor, l
234-0 i
Refueling Floor l
Plant Walkdown l
I I
I unit 2 l
l l
~
[
l i
I l
l l
l I 44 1406.3 l Reactor, i
135-0 l
Neutron Monitoring Room l
Plant Walkdown & E'ng. Rev.
1 I
l
~
l Unit 3 l
l l
l l
l l
1 I
I I
I 45 1406.4 l
-DO-1
-DO-l
-DO-I
-DO-
{
l i
I I
I I
1 I 46 1406.5 1
-DO-1
-DO-I Steam Pipe Tunnel 1
-DO-(
l i
I I
I I
(
l.47 1406.7 l
-DO-I
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I 48 1406.8 l
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l 49 1409.1 1
-DO-l 165-0 I citsn Up Recirc. Pump Room 1
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l 50 1409.2 1
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l 54 1409.6
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l 55 1410.2 1
-DO-1
-DO-l Backwash Rec. Tank Room l
Engineering Review.
[
l l
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l 56 1410.3 l
-DO-I
-DO-l Transfer Pump Room 1
-DO-
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l i
I l
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T-29/2 O
s1 Cn N
s
Shrot 5 of 6 j....
-APPENDIX "B"
dUMMNRY OF N SONRY hfALL NdN-SNFETYRELATED)
-PEACH BOTTOM ATOMIC POWER STATION UNITS ~2 & 3 i..
ISERIALI l
WALL DESCRIPTION 1
3 i., ;
4.
I NO.
lWALL NO. I BUILDING l ELEVATION l LOCATION l
BASIS'FOR CLASSIFICATION I
I I
I I
I f
l 57 1410.4 l Reactor, l
165-0 i Non Regen. Heat Exch. Room i Plant Walkdown & Eng..Rev.
l l
l Unit 3 l
l l
l i
I I
I I
l-58 I410,5 1
-DO-1
-DO-l
-DO-1
-DO-1 I
I I
I l
l 59 l410.11 1
-DO-1
-DO-l Transfer Pump Room 1
-DO-l l
l 1
I l
I 60 1413.1 1
-DO-l 195-0 l
Storage Area l
Plant Walkdown I
i l
l l
l l 61 l413.2 1
-DO-1
-DO-l
-DO-1
-DO-1 I
i l
l l
l 62 1413.3 l
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-DO-1 I
l l
1 l
l 63 1413.4 l
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I I
I I
I 64 1413.5 l
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l l
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I 65 1413.6 l
-DO-1
-DO-l
-DO-I
-DO-1 I
I I
I I
l 66 1414.1 1
-DO-1
-DO-l Prefilter & Filter l
Plant Walkdown & Engr. Review l
'l l
l l
Compartment l
l l
1 I
I l
l 67 1414.2 1
-DO-1
-DO-l
-DO-l Plant Walkdown I
I I
I I
l I
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I IL 1414.3 l
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n.
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g g
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- - -- l 234-0
-l
- I -Refueling Area --- -
l--
-- - - - - - -- --DO - -
1 i __,
l' I
I l
,T-29/2 O
g 4
Cn
<9
,1
- 3....,
p
,y. APPENDIX "B"
[
SUMMARY
OF MASONRY WALL (NON-SAFETY RELATED)
PEACH BOTTOM ATOMIC PO'iBR STATION UNITS 2 & 3
~
~.'
lSERIALl l
WALL DESCRIPTION l
I NO.
l WALL NO. I BUILDING l ELEVATION I LOCATION I
BASIS FOR CLASSIFICATION
.I I
I I
I I
l 71 1418.1-
.I Re ac tor, l
234-0 1
Refueling Area l
Plant Walkd.own I
l I
Unit 3 l
l l
1 1
I I
I i
1 72 l418.2 1
-DO-I
-DO-I
-DO-I
-DO-1 I
I I
I I
.I 73 1418.3 l
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-DO-I I
I l.
I Ii 1 74 l418.4 l
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-DO I
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.I :
I I
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.. 75 1418.5 1
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-DO-l
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l 1
l 1
f l 76 1418.6 l
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l I
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I
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l I
i 1
1 I
l
-DO-l 77 1418.7 l
- DO-l
--DO-1
-DO-I l 78 1418.8 l
-DO-I
-DO-l
-DO-1
-DO-I I
I I
I l
l 79 1418.9 l
-DO-l
-DO-l
-DO-
-DO-l l
l I
i I
I 80 l418.12 1
-DO-1
-DO-1
-DO -
1
-DO-I I
I I
i 1
l 81 1418.13 1
-DO-1
-DO-1
-DO-1 4.'
-DO-I l
l l
1 I
I*
I I
I I
l
- NOTE:. Based on Engineering review, all masonry walls of Recombiner Building and masonry walls of Radwaste, Turbine, and Reactor Building (Units 2 & 3) not listed'above,
.are non-safety _related.
3,
~
O g
M m
N M
.