ML20084G351
| ML20084G351 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 05/02/1984 |
| From: | Bradley E PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8405070193 | |
| Download: ML20084G351 (12) | |
Text
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PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.19101
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I215 e414000 ano esnanas counss6 CUGENE J. BR ADLEY ASSOCIATE SENER Ab COvMSEL KON ALD BLANKEN EUDOLPH A. CHILLEMI 3, C. K I R K H A LL T. H. M AHER CORNELL PAUL AUERS ACH May 2, 1984
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CEDW A R D J. CU LLE N, J R.
THOM AS H. MILLER. J R.
IREME A. McKENNA assistamv counset Mr. A. Schwencer, Chief Docket Nos.: 50-352 Licensing Branch No. 2 50-353 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Limerick Generating Station, Units 1&2 Information for Quality Assurance Branch (QAB) Concernine SER Open Issue
- 22 (Q-List)
Reference:
Telecon between J. Spraul (NRC/QAB) and J. Arhar (PECO) on 4/18/84.
File:
GOVT 1-1 (NRC)
Dear Mr. Schwencer:
Attached are draft changes to responses to Questions 260.56 and 260.57 and to FSAR Table 3.2-1 which are being made as a result of the referenced telecon.
We trust that this information will assist you in the closeout of SER Open Issue No. 22 The information contained on these draft FSAR changes will be incorporated into the FSAR, exactly as it appears on the attachments, in the revision scheduled for May 1984.
Sincerely, Eu ine
. Bradle JIIA/gra/0419841125 Attachment cc:
See Attached Service List 8405070193 840502 PDR ADOCK 0500035a 00j E
Pm k
cc: Judge Lawrence Brenner (w/o enclosure)
Judge Peter A. Morris (w/o enclosure)
Judge Richard F. Cole (w/o enclosure)
Troy B. Conner, Jr., Esq.
(w/o enclosure)
Ann P. Hodgdon, Esq.
(w/o enclosure)
Mr. Frank R. Panno (w/o enclosure)
Mr. Robert L. Anthony (w/o enclosure)
Mr. Marvin I. Iewis (w/o enclosure)
Charles W. Elliot, Esq.
(w/o enclosure)
Zori G. Ferkin, Esq.
(w/o enclosure)
Mr. Thcmas Gerusky (w/o enclosure)
Director, Penna. Emergency (w/o enclosure)
ManagementeMency Mr. Steven P. Hershey (w/o enclosure)
Angus love, Esq.
(w/o enclosure)
Mr. Joseph H. White, III (w/o enclosure)
David Wersen, Esq.
(w/o enclosure)
Robert J. Sugarman, Esq.
(w/o enclosure)
Spence W. Perry, Esq.
(w/o enclosure)
Jay M. Gutierrez, Esq.
(w/o enclosure)
Ataaic Safety & Licensing (w/o enclosure)
Appeal Board Atctnic Safety & Licensing (w/o enclosure)
Board Panel Docket & Service Fection (w/o enclosure)
Martha W. Bush, Esq.
(w/o enclosure)
James Wiggins (w/o enclosure)
Mr. Timothy R. S. Campbell (u/o enclosure)
Phyllis Zitzer (w/o enclosure)
t a
/
RESPONSE
The Limerick Quality control Program is described in Chapter 17.
FSAR Table 3.2-1 (Limerick Design Criteria Summary) is intended, in part, to provide identification of safety-related structures, systems and components 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 "Q-List."
The Limerick Project Q-List is not part of the FSAR; it is a controlled QA Program document that serves to identify structures, systems and components requiring compliance with Appendix B to 10 CFR Part 50.
The Limerick QA Manual and its implementing procedures prescribe the preparation and maintenance of the Project Q-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.
These nz: :sf:ty structures g
include the steam dryer, shroud head and steam separator
(
assembly, in-core guide tubes and in-core guide tube stabilizers, differential pressure and liquid control lines inside RPV, fuel orifices, and feedwater spargers.
This is consistent among all BWR 4/5/6 designs.
These structures rrr rt ^ lirted Errrrre they are neither required for safe shutdown of the plant nor will their gy failure jeopardize the safety function of other safety-related reactor internals. A-Because the aforementioned components are~not safety-related,3GNE9 are not under 10CFR50 Appendix B.4 Ace. r4cT R--LibTEp At4p iN5ER_T @ D ri g th j
u n
e operations phase, the same design and construction control practices will be applied as were used during the design and construction period.
These controls will provide assurance that any changes to the reactor internals will be of the same high quality as the original work.4 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 m,
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b.2.II.B Table 3.2-1-has been changed to' include the O-t listed drywell and suppression chamber spray
. nozzles.
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b.2.X.E.2 Conduit and cable trays and their supports containing Class IE cables and those whose failure may damage other safety-related items are 0-listed i
as indicated in Table 3.2-1, Item X.E.2.
i i
b.2.X.E.3 Emergency lighting batteries are not Q-listed i
because they perform no safety function.
b.2.X.E.4 Emergency lighting systems are not 0-listed because they perform no safety function.
The safe shutdown of the plant does not depend on the functioning of the emergency lighting system.
However, the control room emergency ac lighting is powered from i
a Class 1E source and the fixtures are seismically mounted.
The raceways from the Class 1E source to the contro1~ room emergency ac lighting fixtures are routed in a seismic Category I structure and are seismically supported.
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The Class IE portion of the power source for the ac l
emergency lighting system was procured and installed to all of the pertinent requirements of 10CFR50, Appendix B.
The failure of the remainder i
of the emergency lighting system is of no consequence because all actions required to attain i
safe shutdown for design basis events take place in j
the control room. NOTE 63 Tb FSAF. TAgut $,PJ i
6% B6E4 Appso To DE6CELBG T)tE. APPtXAstury op locm.50, Aree9% o To THE bTe.ct. Rm M EMe.sd.ENcy t-MRTsN6.
4 During the operations phase, the emergency lighting system will be maintained in good condition as required to perform its intended function.
In the event that rework is required, the same design and 3
construction controls will be applied as were used i
during the construction period.
These controls will provide assurance that any change to the-emergency lighting system will be of the same high quality as the original work.
i
@ houtrise+rtsFM sroncw 'i.'5.L4 9Rolus Tes. tweWM Mp Tes.T i
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i b.2.X.E.7 Electrical-inverters are not Q-listed because they i.
& w # 3 do not; supply power to safety-relatadgloads.
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.' times."7The lighting system provides lighting at all times in areas used during reactor shutdown or emergency.
,n During normal plant operation, all plant lighting systems are energized from the respective unit auxiliary buses and startup buses.
In the event of ac power loss from both unit auxiliary and startup buses, the normal lighting system is inoperable.
The emergency lighting system
- however, remains operable, being energized from the safeguard buses.
The emergency lighting system is provided with the capability for full functional tests to ensure the operability components of the system.,of the automatic switches and other In the event of ac power loss from both unit auxiliacy and startup buses, the standby diesel generators start and energize the respective Class IE buses within 10 seconds.
During the 10-second delay (diesel startup time) the de emergency lighting system remains energized from the station 125V de battery supplies.
This system design ensures continuity of illumination in all indoor and essential operating areas including all emergency access and exit routes.
All emergency ac lighting is automatically isolated from the Class 1E buses on receipt of a LOCA signal.
9.5.3.4 Inspection and Testino Requirements The lighting systems are preoperationally tested.
System
('
operability is demonstrated by use during normal plant operation.
\\
A routine test will be written to simulate loss of offsite ac power to the emergency ac-de lighting automatic transfer switches.
Visual inspection of the lighting system will indicate whether the transfer switches have operated properly.
This routine test will be performed twice a year consistent with available manpower and plant conditions.
9.5.4 DIESEL GENERATOR FUEL OIL SYSTEM The diesel generator fuel oil system provides onsite storage and delivery of fuel oil for at least seven days of continuous operation to all diesel generators with the diesels operating at their full rated load.
The diesel generator fuel oil system is a safety-related system.
9.5.4.1 Desion Bases i
The diesel generator fuel oil system design bases are as follows:
I1 a.
To provide onsite storage of fuel oil for the diesel generators for at least seven days of continuous operation and to allow for subsequent refilling l
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Rev. 24, 09/83 9.5-28 l
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It.S FSAR RAFT GUESTION 260.57 (Section 3.2-1)
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... are not included in the
'Q' List." Justify or eliminate this practice.
RESPONSE
Those structures, components, and systems necessary to ensures the integrity of the reactor coolant pressure boundary a.
(RCPB),
b.
the capability to shut down the reactor and maintain it in a safe shutdown condition, c.
the capability to prevent, or mitigate the consequences of, accidents that could result in potential offsite exposures comparable to the guideline exposures of C.
10CFR100 are classified as 0-listed and are in accordance with the quality assurance requirements of 10CFR50, Appendia B.
The 0-listed boundaries for piping systems terminate at the outermost containment or system isolation valve.
The piping downstream of this boundary is not required to ensure items a, b, or e above and is therefore not required to be 0-listed.
However, in order that failure of the non-O-listed piping not affect the 0-listed piping or the isolation valves, the non-0-listed piping is designed to seismic Category I requirements up to and including the first point in the system that can be treated as an anchor to the plant structure except as indicated in part c of the discussion on Regulatory Guide 1.29 in Section 3.2.1.
Stress analysis, support design, and design control for this non-0-listed piping, classified as seismic Category IIA, is carried outinthesamemannerasitisforgiens.
g 4
The pertinent quality assurance rec,uirements of 10CFR50, Appendia 3, are considered to be atequately met for the seismic Category IIA piping as indicated in Section 3.2.1, part d.
The design control and construction control practices that were used during the design and construction phase will also be applied during the operations phase to ensure that the same stringent requirements are maintained.for any changes to seismic y, Category. IIA. piping. M Acornog sys,gg, cATgAon.f,5,N. m lg@V.
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TAB;.E 3.2 1 (Page 1 of 36) 143 CEFIGM CRITEPIP TU
."M)PV
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QUALITY SOUR CE GROUP PRINCI P AL OF 1hCA-CLASFI-C00E1 DND SFI Sw!C 0-FSAP SUPPLY TION FIC ATI O*'
STANDAWDS CATEGORY LIST IICf"./CQ5fCHU* f to 1 IIC2;F..[JJ!.
.L232
_LJJ2...
..L132...
L5J2..
[f.l!. 22"5ft'I!
! 3:13 A. Ents19t.IYI123 4,5 1
Feacter vessel GE C
A III-1 I
Y (7) 2.
Feacter vessel suoport skirt GE C
III-1 I
Y
[ 49]
l 3.
Coactor vessel appurtenances, GE C
A III-1 I
Y oressure retairting portions 4.
CRD (control rod drive) housing GE C
MF STD I
Y
( 53 )
I s upport s Peactor internals, engineerst GE C
KF ETD I
Y I
safety features t
6.
Deact or internals, other GE C
(Y
[ 8 ),( M,}
MF STD II M
t 7.
Contrc1 rode GE C
MF STD I
I O.
Core support st ructure GE C
atr STD I
Y 9.
Power range detector hardeare GE C
9
!!!.2 I
Y
- 10. ruel ase.obles CE e
mr sTD I
Y
- s. FJsitat.7211st.gyntes 4,5 1.
Vessels, level instrumentation GE C
A
!!!.l I
Y
[9]
condensing chanters 2.
Vessels, air accurulators P
c C
III-3 I
Y 3.
Piping, relief valve discharge P
C C
III-3 I
Y
[46]
4 Piping and valves, reactor coolant GE/P C,R A
!!!-1 I
y
[7][9](40) cressure bour*dary (RCP A)
Mechanical components, instrumentation GE C
P MF STD I
Y
[11 )
with safety function 6.
Electrical modules, with safety GE C,5,CS -
IEEE-123, Y
[ 11 ), [ 12 )
function 344 7.
Quenchere and quencher supports P
C C
III-3 I
Y e, cga.E31eulls.traite 4.6.1 Class 1 1
1 Contrcl rod drives CE C
III-1 I
Y ADou rt e nance 1
l' 2,
Ivydraulic control unit including GE P
MF STD 1
Y
( 14 1 scrae accumulators O Pet:r to 19otes at the end rif this tatlo.
p,,. 20/05/03 l
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145 PSAR TABLE 3.2-1 (Cont'd)
(Page 19 of 38)
QUALITY SOURCE GROUP PAINCIPAL OF LOCA-CIASSI-CODES AND SEISMIC Q-PSAA SUPPLY TION FICATION STANDAADS CATEGORY LIST SYSTEM /COMPChENT[40)
SECTION f 11*
_[,,2,,],,8 f318 f 418 f 518 Li1*,,,,
CQNKENTS 323, 344
- c. aneineerea safet, Peatures De e.3 Baullaant 1.
125 y and 125 v/250 V station batteries P
Y
[45]
l and racks, battery chargere 32J, 344 2.
sector control center and P
(43)(45]
l distribution panels, G
32J, 344 including prctactive r lays C.
120 Y Yital AC Swatas Bouinment 4.3
{
i 1.
120 V distributton pnele P
(43)(45) l 323, 344 -
D. Electric cables f or safety-related 8.3 l
Esuitemat 1.
5 kV penser cables P
ALL IEEE-279 t -
Y (12)(45]
l
=
308,323,343 2.
600 v poser cables, P
ALL 2EEE-279, Y
(12](45]
l including all ec power cables 308,323,393 3.
Control and instrumentation cables 7/GE ALL IEEE-279, Y
(12](45) l 308,323,303 i
E. Miscellaneous Electrical M $.3 Are $.S*
1.
Primary containannt enclosure P
c IEEE-317, 1 Y
(4S]
l
=
olectrical penetration assemblies 344, 3es/
zzz-NC 2.
Riceway systems, safety-related P
ALL IEEE-344
'I Y
[ 41) ( 45 )
l 3.
bergency lighting betteries P
ALL NF STD 11 3
4 Emergency lighting systems P
ALL NF STD 22 N
h
=
Emergency communicatione systems P
ALL NF STD II N
=
6.
leotore, non-eafety selated P
ALL NSEA-MG-1 II N
=
- 7, 21verters P
ALL NF STD II N
42 4.
V:1ve operators
=
=
40 F. fif nite power swatens 4.1 P
NF STD II 3
=
i i.
Sev. 19, 12/02 I
-'Ubn b. :546-q n-
DRAFT "s 's-TABLE 3.2-1 (Cont'd)
(Page 38 of 38)
(51) Equipment is qualified in accordance with the conformance statements made in Section 7.6.
(52)The original design and installation was to ASME Section III, Class 3.
(53)The basis for classification of non-ASME Section III equipment as Quality Group C is given in Section 3.2.2.e.
(54)The basis for classification of non-ASHE Section III equipment as Quality Group C is given in Section 3.2.2.h.
(55)Short welded sections of ANSI B31.1 piping in the turbine stop valve seat drains, stop valve leakoffs, governing valve leakoffs, casing drains, ring drains, chest drains, and turbine shaft seal leakoffs that cannot be hydrotested will be in-service tested to ANSI B31.1 requirements and the welds will be surface examined.
(56)The basis for classification of non-ASME Section III equipment as Quality Group C is provided in Section 3.2.2.1.
(57)The basis for classification of non-ASME Section III equipment as Quality Group C is provided in Section 3.2.2.j.
(58)This piping was purchased and constructed to Quality Group C requirements and was subsequently upgraded to Quality Group B by volumetrically examining all circumferential welds over two inches using radiography.
Visual examination will be performed in-service in accordance with the In-service Inspection Program.
(59)The containment spray nozzles are fabricated to manufacturer's standards.
In-service inspection requirements will be consistent with Quality Group B requirements.
(60) Spray pond nozzles and junction boxes were designed and built to ASME III, Class 3 requirements, except that they were not N-stamped by the manufacturer.
No manufacturer had an N-stamp at that time.
(61) Engineered safety features (ESF) also include those systems in Chapter 6 and Table 6.1-1.
Although RCIC is not an ESF, it is listed in this subsection because, although not required to mitigate the consequences of an accident, it may be used.
ADp I MSEET.S M
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Rev.-30, 03/84'
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