ML20077F859
| ML20077F859 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 07/29/1983 |
| From: | Bradley E PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8308030091 | |
| Download: ML20077F859 (19) | |
Text
b aP PHILADELPHIA ELECTRIC COMPANY 23O1 MARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 CDW ARD G. 3 AU Km. JR.
(215)841-4000
- '*: ~:lls*:.".'...s.6 EUGENE J. BR ADLEY assecsava seseenak counsak DON ALD BLANNEN RUDOLPH A. CHILLEMI E. C. MI R M H A LL July 29, 1983 T. H. M AM ER CO RNELL PAUL AUERSACH assistant essennak counsa6 EDW ARD J. CULLEN. JR.
THOM AS H. MILLER JR.
$RENE A. McMENN A assistassv causess6 Mr.
A.
Schwencer, Chief Licensing Branch No. 2 Division o f Licensing U.
S.
Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Limerick Generating Station, Units I and 2 Quality Assurance Branch Open Items Re ference :
Letter A.
Schwencer to E.
G.
- Bauer, Jr.,
dated June 7, 1983 transmitting Request for Additional Information File:
GOVT l-1 (NRC)
Dear Mr. Schwencer:
In response to the referenced letter, attached are draft responses to FSAR Questions 260.56 and 260.57.
The information contained in these draft FSAR responses will be incorporated into the FSAR, exactly as it appears on the attachments, in the revision scheduled for August, 1983.
Sincerely,
}
en
~) } ' "';,,1
~
..)_.
[
Eugene J.
Bradley 8309030091 G30729 PDR ADOCK 05000352 PDR A
JTR/gra/57 Attachment Copy to:
See Attached Service List
[
5
+ "'
.g cc: Judge Lawrence Brenner (w/o enclosure)
Judge Richard F. Cole (w/o enclosure)
Judge Peter A. Morris (w/o enclosure)
Troy B. Conner, Jr., Esq.
(w/o enclosure)
Ann P. Hodgdon (w/o enclosure)
Mr. Frank R. Romano (w/o enclosure)
Mr. Robert L. Anthony (w/o enclosure)
Mr. Marvin I. Lewis (w/o enclosure)
Judith A. Dorsey, Esq.
(w/o enclosure)
Charles W. Elliott, Esq.
(w/o enclosure)
Jacqueline I. Ruttenberg (w/o enclosure)
Thomas Y. Au, Esq.
(w/o enclosure)
Mr. Thomas Gerasky (w/o enclosure)
Director, Pennsylvania Emergency Management Agency (w/o enclosure)
Mr. Steven P. 'Jershey (w/o enclosure)
Donald S. Bronstein, Esq.
(w/o enclosure)
Mr. Joseph H. White, III (w/o enclosure)
David Wersan, Esq.
(w/o enclosure)
Robert J. Sugarman, Esq.
(w/o enclosure)
Martha W. Bush, Esq.
(w/o enclosure)
Spence W. Perry, Esq.
(w/o enclosure)
Atomic Safety and Licensing Appeal Board (w/o enclosure)
Atomic Safety and Licensing Board Panel (w/o enclosure)
Docket and Service Section (w/o enclosure)
~#'
V'
-T-m e-
~.y_
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[h e a i;4-= g(W %y 1.IMERICK Recuest for Additional Information m
260.0 Ouality Assurance Branch 260.56 Section 17.1.2.2 of the standard format (Regulatory Guide 1.70) reccires the identification of safety-related structures, systems, and cet;cren s controlled by the QA program. You are requested to supplement and clar-ify Table 3.2-1 of the Limerick FSAR *in accordance with the following:
a.
The following items do not appear on FSAR Table 3.2-1.
Acd tne appropriate item.s to the table and provide a commitment that the remaining items are subject to the pertinent requirerents c' the FSAR operational quality assurance program or justify net dcing so.
1.
Reactor internal structures, other.
2.
Scram discharge volume of CRD hydraulic system.
3.
Biological shielding within the reactor building and control structure.
4.
Fabricated supports such as Unistri.t and Su:erstrut ina-are used to support systems and components icentifiec in Regulatory Guide 1.29.
5.
Item that are within the scope of Regulatory Positiens C.2 and C.3 of Regulatory Guide 1.29.
6.
Radiation shielding'.
7.
Radiation monitoring (fixed and portable).
8.
Radioactivity monitoring (fixed and portable).
9.
Radioactivity sampling (air, surfaces, liquids).
10.
Radioactive contamination measurement and analysis equipment.
11.
Personnel monitoring equipment (internal, e.g., whcle body counter, and external, e.g., TLD system).
12.
Instrument storage, calibration, and maintenance program.
- 13. Decontamination facilities, personnel, and equipment.
- 14. Respiratory protection equipment, including testing.
- 15. Contamination control.
16.
Containment isolation barriers listed in' FSAR Table 6.2-17
- 17. Secondary containment structure.
18.
Internal subcompartment structures of primary and secondary containment.
19.
ECCS pump rooms.
20.
Containment overpressure relief system.
- 21. Modifications to the site drainage system (including earthen slopes).
E w'
o I% $) Q ks' h'Q L-[Smj 22.
Foundation support materials (rock, soils, backfill, and concrete fill) for safety-related structures including flood control structures, beams, dikes, and enclosures.
b.
The following items from FSAR Table 3.2-1 need exparsion and/or clarification as noted.
Revise the list as indicated or justify not doing so.
1.
We note that Table 3.2-1 identifies the instrumenta-tion and control (I&C) systems, references tne FSAR section, and indicates whether the I&C is "G-listed" or not. Nevertheless we request that Table 3.2-1 be annotated to verify that all safety-related I&C described in Sections 7.1 through 7.6 of the FSAR plus safety-related I&C for safety-related fluid systems will be subject to the pertinent require-ments of the FSAR QA program.
2.
For the systems shown below, clarify the list in Table 3.2-1 to include the indicated comperents under the pertinent 10 CFR 50 Appendix B quality assurance requirements or verify that they are included as part of the components already listec.
II.B RHR System Drywell and suppression chamber spray nozzles X.E Miscellaneous Electrical 2.
Conduit and cable trays and their supperts containing Class 1E cables and those whose failure may damage other safety-related items 3.
Emergency lighting batteries 4.
Emergency lighting systems 7.
Inverters 3.
Roof scuppers and parapet openings of enclosures are listed under item XII. Provide a commitment that any modifications of these scuppers and openings which affect drainage will be subject to the pertinent requirements of the FSAR operational QA program.
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- c. of NUREG-0737, " Clarification of TMI Action Plan Requirements" (Novenber 1980) identified numerous items that are safety-related and appropriate for OL application and there-fore should be on Table 3.2-1.
These items are listed below.
Add the appropriate items to Table 3.2-1 and provide a commit-ment that the remaining items are subject to the pertinent requirements of the FSAR operational 0A program or justify not doing so.
NUREG-0737 Cl a ri'i ca ti c e Ite-1.
Plant-safety-parameter display censole.
I.D.2 2.
Reactor Coolant system vents.
II.B.1 3.
Plant shielding.
II.B.2 4.
Post accident sampling capabilities.
II.E.3 (system shown as item XI.K in Table 3.2-1, but some components show "N" in the column headed "Q-List")
5.
Valve position indication.
II.D.3 6.
Dedicated hydrogen penetrations.
II.E.4.1 7.
Containment isolation dependability.
II.E.4.2 8.
Accident monitoring instrumentation.
II.F.1 9.
Instrumentation for detection of inade-quate core-cooling.
II.F.2
II.K.3(13) 11.
II.K.3(15)
- 12. Challenges to and failure of relief valves.
II.K.3(15)
I3. ADS actuation.
II.K.3(18)
- 14. Restart of core spray and LPCI.
II.K.3(21)
O
e
[
- a.,.
. t.
NUREG-0737 Clarification Item II.K.3(22)
- 15. RCIC suction.
II.K.3(24)
II.K.3(25)
- 17. Power on pump seals.
._II.K.3(27)
-m
- 18. Coirhon reference' level.
--ADS valve, accumulators, and associated II.K.3(28) p 19.
equipment and instrumentation.
III.A.1.1/III.A.2 Emergency Plans (and related equipment).
20.
- 21. Ecuipment and other items associated III.A.I.2 with the emergency support facilities.
III.D.3.3 RAS
- 22. Inplant I, radiation monitoring.
III.D.3.4
- 23. Control-room habitability.
4 s
ee RESPONSE TO RAI 260.56 1[ d[$
h
RESPONSE
P The Limerick Quality Control Program is described' in Chapter 17.
PSAR Table 3.2-1 (LGS Design Criteria Summa ry ) is intended, in part, to provide identifica-tion of safety-related structures, systems, and c'om-ponents as required by Section 17.1.2.2 of the standard format (Regulatory Guide 1.70).
Such items are identified in Table 3.2-1 as."0-List".
The Limerick Project 0-List is not part of the FSAR; it is a controlled OA program document that serves to identify structures, systems and components requiring compliance with Appendix B to 10 CPR Part 50.
The Limerick OA Manual and its implementing procedures prescribe the preparation and maintenance of the Project 0-List and define the quality assurance controls that are to be applied to items listed therein.
The information requested for each item identified in question 260.56, as each applies to Limerick, is provided as follows:
a.1 The reactor internal structures, other, is listed in Table 3.2-1 Item I. A.6 and are not 0-listed since they are"$$$"hequired for safe wes TroPARDG E shutdown of the plantme sourf p, acri.u op.rrhsa u, wiw w rist. Fait.uRc : eery wco a.2 The Scram Discharge volume of the CRD hydraulic system is listed in Table 3.2-1 Item I.C.3 and is 0-listed as indicated.
a.3 The biological (primary) shield is 0-listed and is listed in Item XII'.B.7 of Table 3.2-1.
No modifications to shield walls were necessary as a result of the TMI shielding study.
All of the shield walls identified as a result of the plant shielding study are in the reactor enclosure and control structure and are 0-listed.
These walls are included in Items XII.A and XII.D of Table 3.2-1.
i a.4 Table 3.2-1 has been changed to include fabrica-ted supports used to support safety related systems and components.
lL- 'rsMC Xil. A.4, Xit.B.9, Xit.D.7, Xn.F.'4 Ado Xil 01 *E
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a.5 The items that are within the scope of Regulatory Positions C.2 and C.3 of Regulatory Guide 1.29 are designated by Note (8] in Table 3.2-1.
p a.6 No modifications to shield walls were necessary as a result of the TMI shielding study.
All of the shield walls identified as a result of the plant shielding study are in the reactor enc'losure and control structure and are 0-listed.
These walls are included in Items XII.A nnd XII.D.fof Table 3.2-1.
A A
a.7 This is not a " structure, system or component" requiring entry in Table 3. 2-1.
Control and calibration of radiation monitoring (fixed and portable) are provided by procedures that are responsive to the appropriate portions of the Quality Assurance Program described in Section 17.2.
a.8 This is not a " structure, system or component" requiring entry in Table 3.2-1.
Control and calibration of radioactivity monitoring (fixed and portable) are provided by procedures that are responsive to the appropriate portions of the Quality Assurance Program described in Section 17.2, a.9 This item is not'a " structure, system or compo-nent" requiring entry in Table 3.2-1.
Control of radioactivity sampling (air, surface, liquids) is provided by procedures that are responsive to the appropriate portions in the Ouality Assurance Program described in Section 17.2, a.10 This item is not a " structure, system or component"
~
requiring entry in Table 3.2-1.
Control of radio-active contamination measurement analysis is provided by procedures that are responsive to the appropriate portions of the Quality Assurance Program described in Section 17.2.
a.ll This item is not a " structure, system or component" requiring entry in Table 3.2-1.
Control of personnel monitoring (e.g., whole body counter) and external (e.g., TLD system) is provided by procedures that are responsive to the appropriate portions of the Quality Assurance Program described in Section 17.2.
4
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! DZ l.. i m a.12 This item is not a " structure, system or component" requiring entry in Table 3.2-1.
Control of instru-ment storage, calibration and maintenance is provided by procedures that are ' responsive to the app [opriate portions of the Ouality Assurance Program dcscribed in Section 17.2.
a.13 Decontamination equipment and facilities are not s a f e ty-re lated.
Decont amination piping and valves are a part of the "Ligaid Radwaste Management Systems --
Piping and Valves" no described in Table 3.2-1.
Personnel decontamination is not a " structure, system or component" requiring entry in Table 3.2-1.
Control of personnel decontamination is provided by procedures that are responsive to the appropriate portions of the Ouality Assurance Program described in Section 17.2.
a.14 This item is not a " structure, system or component" requiring entry in Table 3.2-1.
Control of respiratory protection, including testing, is provided by procedure that are responsive to the appropriate portions of the Quality Assurance Program described in Section 17.2.
a.15 This item is not a " structure, system or component" requiring entry in Table 3.2-1.-
Contamination control is provided by procedures that are responsive to the appropriate portions of the Quality Assurance Program described in Section 17.2.
a l6 Containment isolation barriers listed in FSAR Table 6.2-17 are listed by system er iel..g ;;;1at;;..
y
- nt irm:nt ;:nc t;;ti..; in Table 3.2-1 and are 0-listed, a.17 Secondary containment structure is 0-listed as indicated in Table 3. 2-1 Item XII. A.
Internal subcompartment structures of primary a.18 and secondary containment are 0-listed as indicated in Table 3.2-1 Items XII.A and XII.8.
r-Q- u s tiro An o a
The ECCS pump rooms are rr'jer' t; the GA. usmir;-
a.19 f
-- ^ - - '
cove red in Table 3. 2-1 Item XII. A. S.
a.20 Limerick does not have a containment over pressure relief system.
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3
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=e/~ et 2 a.21 Site grading is not 0-listed and is not a " structure, system, or component" that should be included in Table 3.2-1.
Site grading cannot adversely impact safety-related equipment because it is designed to direct the storm water flow caused by local Intense precipitation away from safety-related equipment and structures such as the reactor enclosure, control structure, diesel generator enclosure, and the spray pond.
The flooding scenarios caused by pro-bable maximum precipitation and runoff patterns are described in FSAR Section 2.4.2.3.
a.22 The foundation support materials (rock, soils, back-fill, and concrete fill) are not 0-listed and de AEC not X structureT systemf or component that should S
mee be included in Table 3.2-1.
The foundation support material for safety related structures can-not adversely impact the safe operation of the plant due to the following:
1)
All seismic category 1 structures are founded on competent bedrock except portions of buried piping, one valve pit and the buried diesel oil tanks.
The competency of the bedrock to provide satisfactory foundation support is discussed in Section 2.5.4.2.1 and in the response to Question 241.16.
2)
Seismic Category 1 structures not founded on bed-rock are supported by either Type 1 backfill or natural soil.
The engineering properties and tests performed for the backfill and in-situ soil are discussed in Sections 2.5.4.5.Nundation 4 and 2.5.4.2.2, respectively.
!n ;dditi:n, soils underClying safety related structures are discussed in the response to Question 241.17.
l l
3)
The static stability of all seismic category 1 structures is discussed in Section 2.5.4.10.
Table 3.2-lk :,:Treu Tf5: r 5 hanged I
~
- e indicate that safety-b.1
.related instrumentation and controls described in Sections 7.2 through 7.6 are subject to the Appendix B OA program and are qualified to appropriate standards.
cst A M E D b.2.II.B Table 3.2-1 has b,een cir rified to include the Q-USTED l
Drywell and suppression chamber spray nozzles.
1
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j b.2.X.E.2 Conduit and cable trays and their supports containing Class lE cables and those whoso failure may damage other safety-related items are 0-listed as indicated in Table 3.2-1 Item X.E.2.
l 8
f b.2.X.E.3 Emergency lighting battories are not 0-listed'9r8' f but rre ru'j::t te t'r rpp ep-!-t~ ;"-fity
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mt _
m m m-m Emergency lighting sy tems are not 0-listed M b.2.X.E.4 but
~ L ;- - - :.; th: 2ppr r
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. pircr:nts.
Thi: ir dirco:: d i-th:
r^ep-^c^-
011:ti n 4?0.ff,
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b.2.X.E.7 Electrical inverters are non-O since they do not supply power to safety related loads.
This is indicated in Table 3.2-1, Item X.E.7.
j b.3 The roofs of 0-listed enclosures are capable of supporting the weight of water that could be trapped inside the parapet, if the scuppers should fail.
The scuppers and parapet openings are therefore not classified as 0-listed, as indicated in Table 3.2-1, Item XII.
c.1 bsponse to this TMI issue is still under evaluation)
I Any modifications to Limerick will be evaluated to determine if they should be 0-listed.
Table 3.2-1 Lwill be modified as appropriate.
c.2 The various reactor coolant system vent paths are 0-listed.
They are designated in Table 3.2-1, as follows:
The RPV head vent is a subset of " reactor vessel appurtenances, pressure retaining portions",
Item I.A.3.
^
The main steam relief valves with their ADS f unction are a subset of " Piping and valv'es, reactor coolant pressure boundary *, Item I.B.4.
c.3 No modifications to shield walls were necessary as a result of the TMI shielding study.
All of 2Erbe sof9uev&4r no uogge,,
[~TN EES P D s: is noT S-Lisren em see.wiu.u.x mwsarwi sfn a sesw w Twe scusesc th Ac o
ceNotTrowfus wNs W 8edM To TNr spp A,ao 4,r,g pAfq' seg.uAu o,P A SAf:ETf 1ttD.ATEP (N3 W M CrJTATic8J
- gyg, co h gy p Alt C S-ULTO, A s teAMtATd"t tre T/Ed LS-I ITEN g,
DE b (M* d.I.C.)
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the shield walls identified as a result of the plant shielding study are in the reactor enclosure and control structure and are 0-lifted.
Thqso walls are included in Items XII. A.%nd XII.D.%f Table 3.2-1.
A A'
c.4 The post-accident sampling _ system (PASS) is not 0-listed, with the exception of its interfaces witn 0-listed systems, as shown in Item XI.K of Table 3.2-1.
c.5 A safety relief valve acoustic monitoring system that meets the requirements of NUREG-0737 and Regulatory Guide 1.97 Rev. 2 will be installed before fuel loading, Table 3.2-1, Item IX.E.3 geftecT5 id:ntific: the system design.
'dd.
1:n:1 infern:ti;r in dire werd ir th: :::pener de O_ cation 121.E.
c.6 The containment hydrogen recombiner system, j
including the associated containment penetra-tions, is 0-listed as shown in Item VII.C.3 l
of Table 3.2-1.
- dditirn:1 inf :::ti:r e-compliance oit' "Un:C 0737 i: pre"ided in ihm
_::: pen:: t: Osesticr $9^.55.
c.7 containment isolation valves are 0-listed as shown in Table 3.2-1.
Additicr inf:;a;ti r cr cc pli;n ;. i t h """ e c n ' ? ' i : prr.id:d ia thm. o s e ;.. :: : t: 0 ;; Lim...
t21.5 :nd 150.25.
c.8 Accident monitoring instrumentation has been designed using the guidance provided in Regula-IML tory Guide 1.97, Rev. 2 (Section 7.5). % coa y
instrumentation has been classifi i
as 0-listed and is listed in Table 3.2-1 1
Item IX.
- d di t ie. 21 f.. f ; iT..; t i r r i: ; r"id:d 1
i- ^ r :;:rr: tr 0;;;t i... 421.3.
c.9 No additional instrumentation was identified as j
a result of this required study, and therefore no changes to Table 3.2-1 are necessary.
i c.10 irf..~ :=: ft: thi: i t z., i: p:.idad.... L;
^.. ; ;. s.. 421.;
%cge, ystAT. w wed,*tf-iot Ms M
M Q.r%On of % h.
.f:
RCIC ;;difieaL2ea-ni;.
I l
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P.w m,
,- r-;:ac:rm f
- r
!a f e U #.
d c.11
- o f m..r.,... fa. J.i:. ; ;.- i: 77._d;d ir. th;. m e c : r. : e Cus Lawn 421.L.
Items associated with the HPCI
.wand RCIC isolation are 0-listed and in Table 3.2-1 Item II.A.10 and II.D.7 for RCIC and HPCI, rfspectively.
c.12 The safety relief valves are 0-listed and are included in Item I.B. 4 of Table 3. 2-1.
"The,fT weXt.
DO pond modifications made as a result of this TMI item.
c.13 f orma tion Ior this item is provided in the respons3 to Question 421.5.
Table 3.2-1 will not be affected modifications made as a result of this TMI item.j c.14 No changes to the core spray or LPCI system logic were necessary as a result of this TMI item, and therefore no changes to Table 3.2-1 are required.
-' f f i t i n ci
...:...c tier ir prr"'d^d
- *- ^ ~ ; r. : :
4-tc Ou::ti 121.5; c.15 0..f..: tier f: r thir
't--
1: pr:.If:d i-
'ba
-^
r^-
r te0.__.o..
421.5.
Items associated with the RCIC suction modification are 0-listed and in Table 3.2-1 Item II.A.10, c.16 The HPCI and RCIC unit coole rs are 0-listed, as shown in Item VII.B.5 of Table 3.2-1.
No modifications W e # E. m O.dC, as a result of this TMI item.
c.17 No modifications to the recirculation pump seal cooling design were necessary as a result of this TMI item, and therefore no changes to Table 3.2-1 are required.
t c.18 Reactor vessel water level instruments are all re-ferenced to the same point.
No changes in instrumenta-tion are required, and Table 3.2-1 is unchanged, c.19 The ADS valves, accumulators and instrumentation are 0-listed and are included in Item I.B of Table 3.2-1.
No modifications to this table are required as a result of this TMI item.
c.20 This item is not a "s'tructure, system or component" requiring entry in Table 3.2-1.
Control of this Jg g A
RWW orc THis TM '
2
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7.
i
~
G-3. C f; f1 I~fi'3 b 8 Li ld u _. ~
d activity is provided by appropriate procedures.
Chapter 17 describes the Quality Assurance Program coverage of procedural controls.
c.21 Response to this TMI study is still under evaluation.
Any modifications to Limerick will be evaluated to determine if they should be,0-listed.
Table 3.2-1 will be modified as appropriate.
c.22 fesponsetothisTMIstudyisstillunderevaluatiol Any modifications to Limerick will be evaluated to determine if they should be 0-listed.
Table 3.2-1 Qill be modified as appropriate.
c.23 The only modification required in response to this TMI item was to add a supply of potassium iodide for control room personnel.
Table 3.2-1 is not affected by this change.
l1s ; pest.di560 tet Sgt"7' od I. I 3,
S & ftosto inETHoP: se N o t
PROCEDL4ET kitts. BC IMPLEMEntVD /+1 RESP M To TNtt T M Z'
/Td>1 This item is not'a " structure, system or compo-nent" requiring entry in Table 3.2-1.
Control of radioactivity sampling is provided by procedures that are responsive to the appropriate portions in the Ouality Assurance Program described in Section 17.2.
c 8
a f
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2 IJS FSa.p TABLE 3.2-1 (Cont'dl-(Page 3 ef 38)
CUAI.ITY SOURCE GROUP PRINCIPAL OF LOCA-CLASSI-CODES AND.
SEISMIC Q-FSAR SUPPLY TION FICATION STANDARDS CATEGORY LIST SYSTEM /COMPOHg_NT [ 40 )
gggIION __[jj!_
_[2]*
_[JJ*
__[4j*___
[}j*
[gje_ CO33FtrH 2.
RCIC barometric condenser GE R
D B31.1 II N
3.
Piping and valves, RCPB P
C A
III-1 I
Y
[7] [ 9] [48]
4 Piping within outermost containment P
C D
B31.1 I
Y
[ 48 ]
l isolation valves, discharges te suppression pool 5.
Piping and valves, other safety-related P
R B
III-2 I
Y
[9] [48]
6.
Portion of piping for RCIC P
R D
B31.1 I
Y
[55]
turbine drains 7.
Deleted 8.
Pumps, RCIC condensate and GE R
D MF STD i
II N
i condenser vacuum 9.
B III-2 I
Y
Y
[ 11 ], [ 12 ]
safety function 344, 279 B. Eggjdgal_ Heat Pegal System 5.4.7 1.
Heat exchangers, primary (process) side GE R
B III-2/TEMA C I
Y I
2.
Heat exchangers, secondary GE R
D VIII-1/
I Y
(service water) side TEMA C 3.
Piping, reactor vessel head spray P
C B
III-2 I
Y
[48]
line, beyond first isolation valve 4.
Piping, RCPB P
C A
III-1 I
Y
[7 ] [9 ] [48]
5.
Pioing, containment spray line P
C g#
III-3 I
Y
[48][$$]
(inside containment) 6.
Piping and valves, other safety-related P
R B
III-2 I
Y
[48]
7.
Valves, isolation GE/P
.C,R A,B III-1,2 I
Y
[7]
8.
Pumps GE R
B III-2 I
Y 9.
Motors, pump GE R
NEPA-M3-1.
I Y
- 10. Mechanical componentss GE R
B MP STD I
Y
[ 11 1
Y
[ 11], [12]
function 344, 279 I
Y
[
- 11. Comicamps Spany pJo3ps.gv P
O
~
>4F srp C.
C2I*_SDIav Syggg_m 6.3 1.
Piping and valves, RCPB P/GE C
A III-1 I
Y
[7] [9] [48]
2.
Piping and valves, other safety-P R
B III-2 I
Y
[9] [48]
related 3.
Pumps GE F
B III-2 I
Y NEMA-M3-1' I
Y 4.
Motors, pump GE R
5.
Electrical modules, with GE R,CS IEEE-323 :
I Y
[ 11 ), [ 12 ]
safety function 344, 279 j D. High-PIgggure gggjaDI_ID_12G1190__(UfCl)
SYgtem
- 6. 3
^
1.
MF STD I
Y
[ 17 ]
2.
Piping and valves, RCPB P
C A
III-1 I
Y
[7] [9] [48]
3.
Piping and valves, other safety-P/GE R
B III-2 I
Y
[9] [48]
l related
{
Fev.
/0f/83
r b
f v
l-
}
1 I
U
+
I
)t l
.?
{
l tf 4
f Ej1_.
--_.,_.._.~A
.. - ~ ~ - -.~. -
(Page 22 of 301.
TABLE 3.2-1 (Cont'd)
QUALITY SOURCE GPOUP PPINCIPAL OF IDCA= CIASSI-CODES AND SEIS* TIC 0-FSAR SUPPLY T:CN FICATION STANDAPDS CATEGORY LIST
]
EHIEEC9t!ECUEM I401 IECIIDS __L1J2_ _L2J2.L232_
LtJf._
L51*
LtJ* C9tRIEEII J. U!igggtD EYf199_ADA_990eratot.EsttKDel HY$IQ920.Evnteg 1.
Vessels P
R,0 D
VIII-1 N
2.
Piping P
R.T.R. D B31.1 II N
O.PW 3.
Valves P
R.T.
D B31.1 II N
R,0
= U2108CGif9D1_ESWEllGS IYS19e 11.5.5 t
Sample coolers GE R
D VIII-1 IIA N
l 2.
Sample line root valves P
R B
III-2 I
Y (46]
l 3.
B31.1 IIA /II N
t 4
System tubing and other valves P.GE R,CS NF STD IIA /II N
l KII KUCLQ2VEZ3
[33]
A. EfestgL Enclosu[3 and 231331189.8gg3 3.8.4 P
R B
ACI/AISC 1
Y 1.
Poof scuopers and parapet openings P
R kCI/%ISC II N
2.
Pressure resisting dcore P
R MF STD I
Y j'
3.
Missile barriers for safety-related P
R ACI/AISC I
Y equipment 4
Spent fuel pool liner P
R AISC I
Y 5.
Safety-related masonry walls P
R
' N 6.
F6I..te tt e J 5 pp.,t, 3.e sqaty.e tl*tal 3*7*3/*3 P R
ACI/CBC I
Y Afst/Atti 1
y B. 211StELC9DIA1DGt01 5 Tit s u4 c.g. ds 3.8.1 P
C B
ACI/AISC/
I Y
r-III al9 1.
Access hatches / locks /dtors P
C 2
III-2 I
y g-2.
Liner plate P
C B
III-2 I
Y 3.
Peretraticn assemblies P
C E
11I-2 I
Y r-4 Vacuum relief valves P
C B
III-2 I
Y t.
5.
Downcomers P
C B
III-I I
Y 6.
Downcomer bracing P
C AISC I
Y f
I.
Biological (primary) shield P
C ACI/AISC I
Y L"
A 6.
retricated supports jer se, et.ttIst*d
'37 3/340 5P
(.
ust./Attt 1
y L"
C. IHKhl0t_ED.E1999Et *7 '*, h M* **"il 3.9.4.1 P
T ACI/AISC II N
[
D. CentKgl.gtKycture 3.8.4.1 P
CS ACI/AISC I
Y 1.
Roof scuocers and parapet openings P
CS ACI/AISC II N
2.
Pressure ressating doore P
CS NF STD I
Y 3.
Missile barriers for safety-related P
CS ACI/AISC I
Y ezuloment 4
Safety-related masonry walls P
CS ACI/UBC I
Y 45 Fokeisatedsgarsyer16{ity-r edad 5
P cs Ape / Alit 1
y sys u s - 4 c.
- g. - w Re.. it, e2/ei
f ',,
[ \\
f f
t c,f.
s.
a
)
(
- h. t
[*,
f
,g, ].-'
f.
.t 4
y I
t y D
l b
, fi s
)
s., ) ^ -
I 1
<]".-..
s m
a
'p 1
TABLE 3.2-1 (Cont'd)
(Page 23 of 38),,
CoALITr SOURCE GPOUP PRINCIPAL OF IDCA-CLASSI-CCDEO AND SEIS*f1C Q-FSAR SUPPLY TION FICATION STANDAPDS CATEGORY LIST EISIKEC9!!E9EET T*01 HCII9tf._LUt_
_L231 _L231.
__L131___
LS1*
Lt32_ E95!mrII AcI/AISC IIA N
[18]
A. P_ aire. fit.and_911 gen _Zos19surs 3.8.e.1 P
PW I. QAtatl-9totIA19t.Enclosurt 3.8.4.1 P
G ACI/AISC I
Y 1.
Soof scucpers and parapet openings P
G
=
ACI/MSc II N
2.
Missile barriers for safety-related P
G ACE /AISC I
Y equionent 86cje.ted wjp..m.nsonry esalls M./'(3 l*4 P Gi Safety-related P
G ACI/DBC I
Y 3.
detaEN96I^h*[sL315Is'fu't}gt.reld ed A
4.
t s g.r s g
Aggc/AIg1 I
y 3.9.4.1 P
S ACI/AISC I
Y J.
1.
Roof scuocers and oaracet openings P
S ACI/MSc II N
m, A. Ssbu b'* T
- b (* 1K.usidtstragt tggt.te.14 3 3.g3,ie,3 p 5
Aisc/Attg g
y
%p d*
y I..
y H
11 P
SP ACI/AISC II A
P 7
I. Eart19eto.ru8stgigucturg P
PP ACI/AISC II N
a, a r-J. Catsulating.Weter Puso Structugg P
CW ACI/M SC II N
- d. husilietY-Bsilts.gnelosur.3 P
=
ACI/AISC II N
L
!; {
L. Lutl.911.Itansfer Enc 192ngs P
F ACI/AISC II N
I M. Wettt_Itts1 Pent Ens.19suts P
W
=
FCI/MSC N
g.L ACI/AISC II N
A Stragt.Ittaisant_Enclotut1 P
(. Edelnan1Ea119n_Du1141Dg P
A ACI/AISC II N
=
x!!!
EEMI_E9BD A. Esod 3.9 P
S I
Y
[341 [35]
- s. Eyppggi_g91sEDg 3.8 P
S ACI/AISC 1
Y
[ 36]
C. Qrstiler_Structutt 3.8 P
S ACI/AISC I
Y
- u. FetaY-retruth_E191ng 9.2 P
S C
III-3 I
Y
[38}
E. $sil_D9019n11S_Linits:
2.5 P
S N
eod Ds11 G9r F. UDK91D19tst 90sttit_ItEs19610g P
S
=
=
N 19904e1190s ostelt_ Des 41111.
E r elstn & Gn4.Itt ostLDes h 11114_an t E911 A Yet Rev. 17, 02/83
145 FSAR TABLE 3.2-1 (Cont'd)
(Page 38 of 38)
(54]The basis for classiffeation of non-ASME Section !!!eq
[55]Short welded sections of ANSI 331.1 piping in the turb leakoffs, casing drains, eing drains, chest drains, and turbine shaft seal Isakoffs that cannot be hydrotested wil' be in-service tested to ANSI 331.1 requirements and the welds 4
~~l will be surface esarined.
156]The basis for classification of non-AS E Section !!! equ 157]The basis for classification of non-ASME Section II h d eat.)
Eggs -rbis r:Fa$ was rare 4***d cad c asfr ded Uh
- d * * *d**[***h
- f P Q f)
Group C
- $"Ir* ***f"
' ~
val'es+r;<-ety eaam.4;3 *!t 07 l
Quali+y Group
., _ m, m. ; a, c,.
.u.
(sekaed
.n serv.se in a s n e,g y:s al s.a m.,4..,
a.st be
,;+A 4 A. ' I, >e< <.c
- r a sper.4.oa Pr,3 rom.
-~
N Cop 5-datb4 N
21 Nt
_f ddccied. -b m4cfan.'s siuA4,
)
)-
.r
.s v au-us m %
ce3wcuu G wm.
n fu be. mea %at whh Qecdikg Grup E l
yleeme.nts. -
pm r
s..
~
V:f b ::
(.
U LL U
L v+wed%y _
)
k Rev. /, 0[/83
e COesTio4 260.57I Section 3.2-1 of the Limerick FSAR states that items which extend beyond a seismic restraint "to the first point in the system which can be treated as an anchor to the plant structure... art not in.
cluded in the 'Q' List." Justify or eliminate this practice.
RESPC41%E-
- nose structures, components, and systema necessary to ensures a.
The integrity of the reactor coolant pressure boundary (RCPB).
w,
.g j
b.
The capability to shut down the reactor and maintain it in a safe shutdown conditions.
c.
The capability to prevent, or mitigate the censequences of, b
I accidents which could result in potential offsite exposures F
comparable to the guideline exposures of 10CTR Part 100.
T
]
m...
are classified as Q-listed and are in accordance with the quality assurance 4
requirements of 10CIlt Part 50, Appendix B.
ne Q-listed boundaries for pipina systems 4sc Aabe, et4 Mootteved MMaek CD sysitva nois4*sen ogWe
- The piping downstream of this boundary is not required to ensure items a, b or e above and is therefore not required
((~..._
^
l to be Q-listed. However, in order that failure of the non-Q-listed piping not af fect the Q-listed piping or the isolation valves, the non-s
{
Q-listed piping is designed to Seismic Class I requirements up to and
, j including the first point in the system which can be treated as a
~
L anchor to the plant structure except as indicated in 6R: tion 3.2.1
,, Stress analysis, support design and design control for % th non-Q-listed piping, classified as Seismic Class IIA, is carried out in the same manner as it is for Q items.
The pertinent quality assurance requirements of 10Cf1t50, Appendix B are considered to be adequately met for the Seismic Class IIA piping as indicated in Section 3.2.1, part d.
par + 0 4 4he,dscusui.
W '$\\.
aRqMeyGak\\.?,s i
A Q?
Q
.?
l mgsq
~-m.. n
_ _ _