ML19350E197
| ML19350E197 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 06/10/1981 |
| From: | Delgeorge L COMMONWEALTH EDISON CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| 2147N, NUDOCS 8106170132 | |
| Download: ML19350E197 (14) | |
Text
.
O One First N'tiorri Pt'za. Chicago. Illinois Commonwealth Edison Address Raply to: Post Office Box 767 Chicago, Illinois 60690 June 10, 1981 Mr. A.
Schwencer, Chief Licensing Branch 2 Division of Licensing U.S. Nuclear Regulatory Commission Wasnington, D.C.
20555
Subject:
LaSalle County Station Units 1 and 2 Supplemental Information Regarding Outstanaing : tem 10 (Q -List)
NRC Docket Nos. 50-373/274 Reference (1):
L. O. DelGeorge letter tn A. Schwencer dateo May 4, 1981.
Dear Mr. Scnwencer:
The purpose of this letter is to supplement the information provicea in Reference (1) relative to the suoject outstancing item.
Encicsec is accitional information ralative to Staff Questions 421.6, 421.7, 421.3, and 421.9 provicea in. response to a request for clarification from Messrs. A. Sournia and W.
Haas of the NRC Staff.
This submittal furtner clarifies the Q.A. program requirements to be appliea curing the operation of LaSalle County Units 1 and 2.
In tne event there are any furthar questions in this regard, please airect them to this office.
Very trul-yuurs,
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L. O. DelGeorge Nuclear Licensing Administrator Enclosure cc:
NRC Resiaent Inspector LSCS 1m NO
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ENCLOSURE 1 (Proposed Revision to Q421.6) e i
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PROPo 5p E G VISt o A)
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AMENDMENT M LSCS-FSAR
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[JgESTION 421.6 "The following items from the 0-list need expansion and/or clarification as noted.
Revise the list as indi-cated or justify not doing so.
1.
Clarify that motor operators for 0-listed valves are included on the 0-list.
2.
Clarify that post-LOCA ECCS leak detection systems are included on the Q-list."
RESPONSE
Table 3.2-1 of Section 3.2 is not a Q-list, but is, as stated in the text, a summary listing of the quality group classifi-cations of various plant structures, systems and components.
Each system for which valves are listed as components, and for which the motor-operators are considered to be Quality Assurance Requirement'I, includes the motor-operators on the valve listing.
Where applicable, an electrical classifi-cation of lE indicates the inclusion of safety-related motor-operato..s under the respective valve listing. +
I ECCS leak detection systems are included in Table 3.2-1 under Listing XL Aa,ro rae exrENT Shod ^'y HAVE BEEN ConTACLLED BY TNC
/0CFie,S*C kppenvi; 8 - QA Pao 9esm. TN/S 3 f57Es AS D/ScossED /N TME LSCS S ER ( N OREG -0579, 5 eCrion S 2,5 71Egn TNG AEqu/RENENTS o f GDC -30 Ann gg I.45. Osong T.ne apenericas wse or rxe puxr, TAESE SYSTEMS ARE G DVED)ED BY ECHMCAL hPGC)F/CRfioM S.k b y
l 4ND THE /NZTRUP1ENTS 'Pl$cu SS G D 7WERE / ^) wa nso87&CT To PERicDsc
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j p E n T/ f t E D IN 0421.6-2
ENCLOSURE 2 (Clarification of Response to Q421.7)
The following adaitional information is provided in the format of Q421.7.
Only those items identified by Messrs. Sournia ana Haas as requiring aaditional. clarification are aiscussen.
1.
Missle barriers protecting safety related equioment
Response
Each missle barri r has.the same Quality Group Classification as tne structure within which it is locatea, ana is not, tnerefore, separately identified in FSAR Table 3.2-1.
7.
Lake screen house Response: The aesign of the lake screen house is described in F5AR Section 3.8.4.1.7.
This structure is not related to safety..Its interface with the ultimate heat sink through the r
CSCS intake is discussed in Section 3.8.4.1.7 ana in response to Q10.7.
Table 3.2-1, Item XLII will be revised as shown on the proposea reviseo page 3.2-16 with the aaaition of a Note (26) to Table 3.2-1 which will read:
Note (26):
Concrete portions of the building, including the portions that contain Category I systems, are designed to withstand Category I loads and modifications to these concrete portions of the building,'if ever required, shall also be designed 4
to withstand Category I loaas.
.(10M).
Otner cable cenetrations (fire stops)
Response:. Fire stops, as is the case for all items falling witnin the Fire Protection System, are classified as non-safety related.
Therefore, the designation in FSAR Table 3.2-1, Item XXXIII.10 is accurate.
However, as indicatea in response to Question 421.1 and 421.2, the quality assurance program to be applied to the operation, maintenance and moaification of the LaSalle County. fire protection system - incluaing fire stops, t
satisfies the appropriate regulatory criteria.
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2-(21)
Meteorological Data Collection Programs Resoonse:
quality assurance program forThe Commonwealth Edison Company has ha since 1976.
- However, its meteorological monitoring composea'of structuresbecause the meteorological program is'not systems ano components that mitigate the consequenc,es of postulatea accicents andprevent or not " safety-relatec, not all aspects of 10CFR50 Ap is thus apply.
Those aspects of quality assurance germa,ne.penaix 8,
. good meteorological incorporatea into the Program,information for a nuclear power plto been ant have LaSalle County.
This Program is aefineaana will be applicable to t
letter to H. R. Denton aatea January in the L. O. DelGeorge Offsite Dose Calculation System (00CS)19, 1981, concerning the County.
applicable to LaSalle Miru 29) Main Steam Resoonse:
Although the main steam p5 ping anc valves addressea in FSAR Table 3.2-1, Item XXXI parts 1,
2, 4 and 5 and Item XLIII part 3 are not safety-relatea, requirements have been imposea to additional quality
[
design.
i 3.2-1, Notes 7 andThese requirements, which are definedimprove the relia in FSAR Table operation of LaSalle County S.ation for repairs ano8, will continu mocifications.
These subsystems and i
designated as reliability related components will be will come under the control of the Q.A.LaSalle County ano as such at moaification and Program for future repairs.
Table 3.2-1 will ne modified incluce a reference to the Reliabilitity Relateo cesignation to
{
130) RCIC Turbine
Response
Although the RCIC turbine wnich is addressed in FSAR 3
j Taole 3.2-1, Item XII part 9 is not 1
i quality requirements have been safety-related, acoitional reliability of the cesign.
imposeo to improve the cefinea in FSAR Table 3.2-1, These requirements, whicn are t
notes 11 ano 17, will continue to ce appliea curing the operation of repairs anc moaifications.
LaSalle County Station for 4
}
reliability relatea at This component will be designatea as LaSalle County ana as such will come uncer tne control of the Q.A.
una repairs.
Table 3.2-1 will Program for future modifications reference to the Reliability Relatedbe moaifiea to i,ncluae a
aesignation.
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. (32)
Auxiliary Building
Response
The auxiliary building Quality Assurance Requirement, shown in FSAR Table 3.2-1, Item XLII part 10 as Category II, is in error.
This table shall be revised to indicate that this structure meets the Category I quality assurance requirements.
ENCLOSURE 3
'(Clarification of Response to Q421.8)
~
As ino1cated'in the response to question Q421.8 in the FSAR, Items 1, 3, 4, 5,
6,-7, 8, 9,.10 and 11 are not safety relatea.
However, equipment facilities and processes aadress.ed in these items are all controllea by aaministrative controls-in
-conformance with guiaelines outlined in ANSI N18.7-1976 and Regulatory Guide _l.33 as defined in Appendix.B to the FSAR.
-Therefore, although the items listed above are not iaentified in FSAR Table 3.2-1 as Category I (Quality Assurance Requirements),
applicable.Q4A. requirements will be applied to assure their reliable operation.
Adherence to these requirements is subject to periodic surveillance under the Commonwealtn Eaison Quality-_
Assurance Program.
Masonry walls (Q421.8, Item 2) identified as safety related in.the Commonwealtn Ecison review of LaSalle-County against I.E.
Bulletin 80-11 are subject to Category I quality assurance requirements anc will be controllea as such curing the operation phase of LaSalle County-for future-repair or modification.
All masonry walls are not safety-relatec, and cannot be delineated
. generically in FSAR Table 3.2-1.
Therefore, no further change to
- he FSAR is plannea.
Any loaa bearing masonry wall requirea to maintain the integrity of the structure in which it is located is alreaay incluaec_uncer the structure classification in_FSAR Table 3.2 1 Item XLII.
Therefore, those load _ bearing walls in Category I structures will also be classified as Category I anc will nave imposed appropriate quality assurance requirements.
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_ ENCLOSURE 4 (Clarification of Response to Q421.9)
')
l The following aaditional information is proviced in the j
format of Q421.9.
Only those items iaentifiea by Messrs. Bournia i
ana Haas as requiring aacitional clarification are discussed.
j (1)
Plant Safety Parameter Display System i
k
Response
As is inaicated in NUREG-0696 Rev. 2, the SPOS v
equipment need not meet safety-grace or Class lE requirements.
{
It is acknowleoged that this equipment is subject to L
unavailaDility goals which at some future cate may be subject technical specification requirements.
Tnerefore, it is to
. premature to aad this item to any quality listing.
- However,
.upon finalization of technical specification requirements, this equipment will be subject to periooic surveillance uncer the Commonwealth Ecisen Quality Assurance Program.
(2)
Reactor Coolant System Vents
Response
These components are accressea in FSAR Table 3.2-1, item 11 part 11 ano are subject to Category I quality assurance requirements.
(4)
?ost-Acciaent 5ampling a
Resoonse:
Unlike some items ciscussec in NUREG-0737 for which quality assurance requirements were icentified, explicitly none are imposea for this item (II.B.3).
This system was aesignea anc installed as non-safety relatea, not subject to the Category I quality assurance requirem?rts.
However, the operation of this equipment is subject to aaministrative controls ana thereby is subject Commonwealth Ecison Quality Assurance Program.to surveillance under the technic 11 specification requirements in this area is alsoConformance with subject to Q.A. surveillance.
No change to the FSAR in tnis area is judged to be necessary.
(12)
Challenges to and failure of relief valves Resoonse:
The safety / relief valves which are the subject of tnis item are aadressed in FSAR Table 3.2-1 Item II part 2 ano are suoject to Category I quality assurance requirements.
Mooifications to sucn safety-relatea components or reauce S/RV challenges shall also be subject to Category I systems to quality assurance requirements.
I
4 4 (17)
Power on pump seals
- Response:
Mocifications to safety related components or systems to aaoress Item II.K.3(25) in NUREG-O'37, if required, shall also be subject to Category I quality assurance requirements.
This issue, as discussed in FSAR Appendix L (Item L.34.16) is under review by the BWR Owners Group ana has not yet_ led to the aefinition of_any requirea modification (s) applicable to LaSalle County.
(20)
Response
In accordance with the requirements of 10CFR50.54(t),
tne Commonwealtn Eaison Generating Station Emergency Plan (GSEP) applicable to LaSalle County Station shall oe subject to an i r.a e p e n de n t annual audit by the Commonwealth Edison Quality Assurance Departaent.
Actions shall be taken for evaluation and correction of a'l auait finaings (see GSEP Section 8.5; L. O.
DelGeorge letter to H. R. Denton aated March 27, 1981, transmitting GSEP Rev. L aated April 1981).
(21)
Emergency Suoport Facilities
Response
NUREG-0696 Rev. 2, whid provides criteria for tne aesign ana operation of these Emergency Support Facilities (including instrumentation), does not require the imposition of 10CFR50, Appendix 8 criteria.
In fact, where-quality requirements are addressed, i.e.,
seismic design, class lE
' versus non class lE, the lesser requirement is uninformly appliea.
However, it is acknowledged that these facilities will be requirec to satisfy stringent unavailability goals and will be subject to technical specification surveillance.
Upon implementation of those technical soecifications, surveillance unaer the Commonwealth Edison Quali*y Assurance Program will be imposed auring the operations phas of LaSalle County Station to further assure a level of reliability consistent with the criteri_ delineated in NUREG-C696.
(22)
Implant 1 2 radiation monitoring Resoonse:
Unlike some items discussed in NUREG-0737 for wnich quality assurance requirements were identified, none are explicitly imposea, for this item (III.O.3.3).
This equipment was classified as non-safety relateo, ano, therefore as of this time, has not been subJectea to the Category I requirements of the quality assurance program.
However, the operation of this equipment is subject to aaministrative controls ana will be sucject thereoy to surveillance uncer tne Co. nmo nwe a l tn Eci son Quality Asse ance Program.
This is consistent with the response to Q421.8, Item 3.
e
LSCS-FSAR Proposea Amendment Table 3.2-1 (Cont'd)
(26) Concrete portions of the builaing, including the portions that contain Category I systems, are aesignea to withstana Category I loads ano future maaifications to these concrete portions of the building, if ever required, shall also be designea to withstana Category I loads.
(27) The system or component is consiaerea RELIABILITY RELATED and will come under the control of the Q.A. Program for modifictions and repairs.
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a
TABLE 3.2-1 STRUCTURES, EQUIPMENT, AND COMIONENT Cl.ASSIFICATIONS QUAI.ITY (4a)
QUAI.ITY (4b)
SEISMIC (5) GHouP ASSURANCE ELDCTRICAL (4c) PURCilASE PHINCIPAI. COMPONENT @
IJtATION ( 3) CATEGOHY Ct.ASSIFICATION HFOUIHEMENT CI.ASSIFICATION DATE( 2)
COMMENTS I.
Reactor System 1.
Reactor vessel PC I
A I
NA 11-70/4-71 See 5.2.1-1 2.
Heactor vessel support skirt PC I
HA I
WA 11-70/4-71 3.
Heactor vessel appur-tenances, pressure retaining portions PC I
A I
NA 7-74 4.
CHO housing supparts PC I
NA I
HA 11-71 (15) 5.
Heactot internal structures, engineered 5
salety features PC I
NA I
HA 12-72 6.
Core support structures PC I
HA I
NA 11-73 0
(15K%kh'!
7.
Other internal structures F
(i.e., dryers, separators) PC II NA II HA 6-71 y
8.
Control rods PC I
NA I
NA 1-71 (15) z w
9.
Control rod drives PC I
NA I
HA 9-71 10.
Power range detector
""{")
hardware PC I
B I
NA 6-74 (IS) 11.
Fuel assemblies PC I
HA I
HA 5-70 (15)
((([I 12.
Reactor vessel stabilizer PC I
NA I
NA 2-72 4
13.
Reactor vessel insulation PC II NA II NA 3-76 g-mmg II. Nuclear Boiler System 1.
Instrumentation condensing
("(()
chambers PC I
B I
NA 8-75 (10) 2.
SRV and MSIV air accu-mulators PC,RB I
C I
NA 9-74 (16'
$)d3 3.
Piping, main steam within
@o C""")
the reactor coolant pres-sure boundary (HCPB)
PC,RB I
A I
NA 8-74
@g
---mm 4.
Piping, feedwater within Mu the RCPB PC,RB I
A I
NA 9-74 (9) k
"]33m 5.
Piping, feedwater within outermost isolation valve RB I
B I
NA 9-74 (9) c)
P
e TAHl.E 1.2-1 (Coa
-3 OllAI.ITY (4. )
Otl AI. lTY (412)
SEISMIC (5) GROUP ASSURANCE El.UCTR ICAl,(4c)
PURCHASE PRINCIPAI. COMPoNFNT(l)
IDCATION ( 3 ) CATEGOHY CI.ASSIFICATION HEQtilHEMENT Cf.ASSIFICATION DATE(2)
CONMENTS Rct~C3 e.~d ti. Valves,HCP 1,oundary isola-taon 6 valves within contain.PC,Ris I
A I
IE 12-73 7
Valves, return test line to condensate storage His Is I
IE 12-73 8.
Valves, other Hit I
H I
IE 12-73 9.
Turbine HH I
E NA 10-70 (11) (17) (15)(g7 10.
Electrical and instrument mudules with a safety funct. HH,A I
NA I
3E (15)
II.
C.a b l e, with a safety functiun I
N%
i lE 10-75 12.
Water leg pump motor HH I
NA I
lE 6-74 XIll. Vuel Service Dju i g. men t 1.
Fuel preparatson machine Hil I
NA I
NA 10-72 (15)
J.
General purpose grapple Hil i
NA I
HA 1-73 (15) xlv.
Huaetor vessel Service ppa i pmen t g
cn Steamline plugs HH I
NA I
NA 4-7]
(15)
Q w
2.
Airyer anil separator sling Htt i
H4 I
H%
4-75 (15) 4 e
1.
Ilead strongback HH I
NA I
NA 11-75 (15) va a>
lc XV.
In-Vessel Service 3 uipment 1.
Control no.1 grapple HH I
NA I
NA 8-75 (15)
XVI.
He l ue l i tiq Djts i gnen t, l.
Hefueling platform His NA I
NON lE 11-73 j
g 2'.
Itefueling bellows, acactor cavity PC I
NA II NA 1-76 iQ l.
New fuel anspection stand RB 11 NA 11 NA 1-73 (15)
XVII. Stot a je Djuigment 1.
Fuel storaqe racks HH I
NA I
NA 10-7)
(15)
$' MN 2.
Hefective fuel storage M
container His i
NA I
HA 12-75 (15)
E 1.
Spent fuel pool, dryer /
lE f sep. pool, tx well HH I
HA I
HA E g q
ftf
%:a:
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a TAHIL 3.2-1 (Cont'd)
OHAIITY(4a)
Oll Al.ITY ( 4 b)
SEISM I C ( 5 )
GHistlP ASSif R ANCI:
EI.ECTRICAI (4c)
Pl!HCilASE PH i t3C I PAI. COMi'ONENT (1) 1.OCATI ON ( 3 ) CATI:GoHY Cl.ASSIFICATION HEOHIP. MENT CI.ASSIFICATION DATE(2)
COMMENTS
- t. l X.
Standtsy C.as Tr ea t ment System 1.
Piping,end valves hil I
h I
IE 9-74 2.
SGTS equipment train His I
H I
lE 4-76 3.
Elect ica1/mechanica1 modules, with a safety function itis, A I
HA I
IE 4-76 4.
Cable, with a safety Iunetion Hu,A I
NA I
IE 10-75 5.
Instr. and Controls pig, A I
O I
gg 9-74 l
XXX.
Pr inary Contain3 ment vent i la t_ ion an.1 Ventilat ion water tjysy n 1.
All com; tie n t s, except contair, ent isolation py valves nd penetration piping PC, Hit II HA II NON lE en P
2.
Valves, containment 8,3 y
isolation His I
il 1
IE 12-73 y
e 3.
Piping, penetration l'C, it u I
11 I
HA 9 74
- o N
XXXI.
Power Conversion System t
1.
Mann steam piping lie-tween outermost iso-Q lation v.alves up *.o turtaine stop valves Ril,T,A I
D+
II NA 9-74 (7) (g J 2.
Main steam branch piping to tirst valve closed or capable ut automatic O
..ctuation T,HB,A I
Dt II NA 9-74 (7) (g7 3.
Main steam branch piping after the tarst closed valve or valve capable i.
N.
of autornatic actuation T
Il D
II NA 9-74 l
2
,,mmes 4.
Main turbine bypass i :n 0 piping up to bypass
! "y g T
valwe T
I De II NA 9-74 (7) (,27 ' Qt.
5.
Farst valve that is
/* Hm p
' 3,y either normally closed II(
P capable of automatic on closure in branch pip-ing connected to main steam and turbine by-pass piping T,HB I
D*
13 1E 6-73 (8) (L7
f
=
TABLE 3.2-1 (Cont'd) 9 QUALITY (4a)
QUALITY (4b)
SEISMIC (5) GROUP ASSURANCE ELECTRICAL (4c) PURCHASE PHINCIPAL COMPONENT (1)
IDCATION ( 3) CATEGORY CLASSIFICATION REQUIHDtENT CLASSIFICATION DATE(2)
COMMENTS XLII. Civil Structures (22)k 1.
Reactor building RB I
NA I
NA (22)(
2 2.
Lake screen house L
NA NA II HA 3.
Radwaste building RW MA NA 14 NA (22) 4.
Auxiliary building A
I HA A
NA (22) 5.
Turbine building T
NA NA II NA (22) 6.
Off-gas filter building F II NA II NA (22) 4 7.
Steam tunnel A
I HA I
MA (22) 8.
River screen house O
II NA II NA (22) 9.
Diesel-generator building RB I
HA I
NA (22) j Auxiliary Spillway O
NA NA II NA (22) 10.
11.
Cooling Lake Embankment O I
HA II HA (22) 12.
Submerged CSCS Pond O
I HA I
HA (22) 13.
Isiological Shield PC I
NA I
HA (22)
]
XLIII. MSIV I.eakage Control System
)
1.
Piping, within RCPB h
isolation valves RB I
A I
NA 9-74 m
.y 2.
Piping, other upstream 4
system lines RB I
B I
NA 9-74 m
e 3.
Paping, downstream sys-tem from steamline con-l T
nection to first valve RB I
D+
II NA (7,8) 4.
Piping, other downstream j
system lines RB I
B I
NA 9-74 i
Q 5.
A I
lE 12-73
}
6.
Valves, other RB I
15 I
lE 12-73 N
7.
Heater RB I
HA I
lE 5-76 j
8.
Blowers RB I
B I
IE 11-75 i
9.
Electrical modules with a safety function RB I
NA I
lE g
10.
Cables, with a safety 4
)
function RB I
NA I
lE 10-75
@ XLIV.
Clean Condensate System i
- R M i
'*RA i
1.
Condensate storage tank O II D
II NA 12-73 0
j (3g8 2.
Transfer pungs and T
II D
II 1 ;
motors T
II D
II NON lE 11-72 j
3.
Piping, within outermost vu 5
isolation valve RB I
B I
NA 9-74
- I th
- ~ tf I
4.
Piping, other RC,RB,A,T,RW,F II D
II NA 9-74 4-
]
5.
Valves, isolation RB I
B I
NA 12-73 6.
Valves, other PC,RB,A,T,RW,F II D
II NA 9-74 i
-- ~ -, -
.-