ML20083D706
| ML20083D706 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 12/23/1983 |
| From: | Bradley E PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8312280220 | |
| Download: ML20083D706 (14) | |
Text
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PHILADELPHIA ELECTRIC COMPANY 23O1 M ARKET STREET P.O. BOX 8699 PHILADELPHI A PA.19101 7k
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EUGENE J. BR ADLEY assocente es.esmas counset DON ALD BLANMEN nupOLPM A. LMILLEMS E. C. MI R K H A LL DCCember 23, 1983 T. H. M AMER CORN ELL PAUL AUERBACH assistant emmenaL counssk EDW AMD J. CULLEN, JR.
THOM AS H. MILLER, J R.
IRENE A. McMENN A assaevanT couNsEb Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Limerick Generating Station, Units 1 and 2 Quality Assurance Branch SER Open Item #22
Reference:
A. Schwencer to E. G. Bauer, Jr., letter dated September 12, 1983.
File GOVT l-1 (NRC)
Dear Mr. Schwencer:
The attached draft FSAR page changes are provided in response to your letter dated September 12, 1983 (referenced) and are intended to close SER Open Item #22.
The changes address only those unresolved items related to RAI 260.56.
The revised response to RAI 260.57 has been previously transmitted to you in FSAR Revision 26, November, 1983.
The information contained on the attached draft page changes will be incorporated into the FSAR, exactly as it appears on the attachments, in the revision scheduled for January 1984.
Sincerely,
/
Eug e. Bradley KAH/gra/1219831130 Attachment Y[
Copy to: See Attached Service List 1
I i
L 0312280220 831223 PDR ADOCK 05000352 E
r (w/o enclosure) ocs Judge Iawrenco Brennor
(
)
Judge Peter A. Morris
(
)
Judge Richard P. 0010
(
)
Troy B. Conner, Jr., Esq.
(
)
Ann P. Ilodgdon, Esq.
)
(
Mr. Frank R. Ibmano
(
)
Mr. Robert L. Anthony
)
(
Mr. Marvin I Iawis
)
(
Ms. Phyllis Zitzer
)
(
Charles W. Elliott, Esq.
)
(
Zori G. Ferkin, Esq.
)
(
Mr. Tiuras Geruck'/
)
(
Director, Pennsylvania unenjuncy maajunent hjess y
)
(
Mr. Steven P. liershey
)
(
Angus Izne, Esq.
(
)
Mr. Joseph 11. Whito, III
)
t David Wersan, Esq.
u
)
t Robert J. Sugarman, Esq.
)
(
Martha W. Bush, Esq.
(
)
Spence W. Perry, Esq.
)
(
Jay M. Gutierrez, Esq.
)
Atomic Safety and Licensing Appeal Daard f
(
(
)
Atomic Safety and Licensing Board Panel
)
(
Dockot and Servico Section O
e M
e 0
w-
RESPONSE
The Limerick Quality Control Program is described in Chapter 17.
FSAR Table 7.2-1 (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
=tandard format (Rogulatory Guide 1.70).
Such items arc identified in Table 3:2-1 as "Q-List."
The Limerick Project 0-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 i
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 app' lied 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 liste Table T 2-1,-Item _I.A.6 and are s nce they gp are neither required'for_.sde-shu down of the plant, nor will their 4ere TiRipardize the safety-function of TMf6
^
~
~
otMa ety-related reactor internals.
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 biclogical (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.
l a.4 Items XII.A.6, XII.B.8, XII.D.5, XII.F.4 and XII.G.2 of Table 3.2-1 have been changed to include fabricated supports used to support safety-related systems and components.
260.56-5 Rev. 23, 08/83
L LGS FSAR a.20 Limerick does not have a containment over pressure relief system, 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 in 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 probable maximum precipitation and runoff patterns are described in FSAR Section 2.4.2.3.
_ ADD th) h T*
G a.22 The foundation support materials (rock, soils, backfill, and concrete fill) are not 0-listed and are not structures, systems or components that should be included in Table 3.2-1.
The foundation support i
material for safety-related structures cannot adversely impact the safe operation of the plant due to the following:
1.
All seismic Category I 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.
1 2.
Seismic Category I structures not founded on bedrock are supported by either Type I backfill or natural soil.
The engineering properties and tests performed for the backfill and insitu soils are 1
discussed in Sections 2.5.4.5.4 and 2.5.4.2.2, respectively.
Foundation soils underlying safety-related structures are discussed in the response to l
Question 241.17.
)
i 3.
The static stability of all seismic Category I structures is discussed in Section 2.5.4.10.
I AI7D lbMEET'O--
i l
b.1 Table 3.2-1, Item IX indicates that safety-related I
instrumentation and controls described in Sections 7.2 through 7.6 are subject to the Appendix B QA Program and are qualified to appropriate standards.
I
~
l Rev. 23, 08/83 260.56-8 l
LGS FSAR b.2 II.B Table 3.2-1 has been changed to include the Q-listed drywell and suppression chamber spray
- nozzles, b.2 X.E.2 Conduit and cable trays and their supports containing Class 1E cables and those whose failure may damage other safety-related items are 0-listed l
as indicated in Table 3.2-1, Item X.E.2.
l b.2.X.E.3 Emergency lighting batteries are not 0-listed because they perform no safety function.
b.2.X.E.4 gen gt
_sy_s.tems are not 0-1isted her mnge they perfOr
.7 G 5dfely fundtion.
"~
b.2.X.E.7 Electrical inverters are not 0-listed because they do not supply power to safety-related loads.
This is indicated in Table 3.2-1, Item X E.7.
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.
f c.1 The SPDS is not Q-listed because supplement 1 to NUREG-0737 specifically states that the SPDS is not safety-related (Section 4.1.c).
The sensors, isolators and signal conditioners which provide input to the SPDS and are part of a safety'related instrumentation or control system are 0-listed, as indicated in Table 3.2-1, Item IX.
c.2 The various reactor coolant system vent paths are 0-listed.
They are designated in Table 3.2-1, as follows:
l The RPV head vent is a subset of " reactor vessel appurtenances, pressure retaining portions," Item I.A.3.
l 260.56-9 Rev. 23, 08/83 c
LGS FSAR The main steam relief valves with their ADS function are a subset of " piping and. valves, 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 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 l
XII.A.5 and XII.D.4 of Table 3.2-1.
)
I e4 The post-accident sampling system (PASS) is not 0-listed, with the exception of its interfaces with 0-listed systems, as shown in. Item XI.K of Table 3.2-1.
Ac0 s NSES'f E c.5 A safety relief valve acoustic monitoring system that meets the. requirements of NUREG-0737 and Regulatory l
Guide 1.97, Rev.
2, will be installed before fuel loading.
Table 3.2-1, Item IX.E.3 reflects the system
- design, c.6 The containment hydrogen recombiner system, including YNh the associated containment penetrations, is 0-listed as shown in Item VII.C.3 of Table 3.2-1.
c.7 Containment isolation valves are 0-listed as listed in Table 3.2-1.
c.8 Accident monitoring instrumentation has been designed using the guidance provided in Regulatory Guide 1.97, Rev. 2 (Section 7.5).
The Category I and Category II instrumentation has been classified as 0-listed and is listed in Table 3.2-1, Item IX.
c.9 No additional instrumentation was identified as a result of this required study, and therefore, no changes to Table 3.2-1 are necessary, c.10 There were no modifications made as a result of this item.
l 9
Rev. 23, 08/83 260.56-10
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