ML20235A105
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UNITED STATES f.,*
ATOMIC ENERGY COMMISSION WASHINGTON, D.C. 20545 i7d'
+, #'dris RECEIVED e
ADVISORY COMMiiit. c1 REACTOR SAFECUARC3 U.S A.E.C.
Docket No. STN 50-447 ore 7 1974 DEC 9 1974 N
PM William R. Stratton 3
3 3IA 8 I Chairman, Advisory Committee j
j' on Reactor Safeguards U.S. Atomic' Energy Commission Washington, D. C.
20545 GENERAL ELECTRIC STANDARD SAFETY ANALYSIS REPORT (GESSAR)
Sixteen copies of the following Category A documents concerning the subject facility are transmitted for review by the Committee:
SUPPLEMENT NO. 1 TO THE SAFETY EVALUATION REPORT The enclosed Supplement includes Section 7 and 8, which relate to Instrumentation and Control, and Electric Power, respectively. These sections were not included in the SER transmitted by our letter dated November 13, 1974. An updated list of staff concerns is also included.
Copies of Supplement No. 1 will be forwarded to the applicant and to the Public Document Room.
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~ 7 J n F. Stolz, Chief iphtWaterReactorsProjectBranch2-1 j rectorate of Licensing I
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1 RECEIVED ADvisony COMMITTEE ON Revised 12/6/74 OR SAffGUARDS g,3 4,g,g, NOV 5 M74 DEC 9 19 74 AM kJh Ig10J3121,2,3J MTus
_ SECTION STAFF CONCERN 4
4 1.
3.2.1 We will require the applicant to dplicantdoesnot 3.2.2 commit to the seismic and quality conform.
only unresolved classifications of the liquid and part is_ seismic gaseous radwaste treatment systems class of gaseous
, per Appendix B of our SER, system 2.
3.5 We will require specific velocities Applicant does not for the' assumed tornado missiles, conform.
Amdt. 25 should We do not agree with GE's analysis resolve this.
that many missile velocities are zero.
3.
3.6 We will require to pre N.le GE has not yet provided specific critr eb that g61 be sufficient information to 4
N g.ste pip p3reak the staff.
j used to post o
- 2 types + b k for 1
locations piping r. sing th g. rea
.gh containment.
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- 4.. 3.8.3 We are requir.ing the drywell to be Applicant opposes this,
structurally proof tested and leak requirement.
tested at the design pressure of the drywell.
Prior to Am b GE has provided this 5.
4.3.4 transientr d.e. ment 2' N all affected 15.1 ndacej9'ntshadnot information in Amendment o
been ane 8 dd b', b using the new 21 and our review is net Ictiv's curve (D curve).
yet complete. We will scram report in a supplement to the SER. (12/6/74) 6.
4.3.7 GE has not r pided eno-.descrip s We will pursue this tion of tF si physics S.alytica] 9-with GE as a post-FDA methods ge have tbv., presente p9 item.
comps
.,ons of me ured reacepe D
dat. /ith the e.ytical r aictions.
7.
4.4 Prior to Amendment 3#3.,6 had ne' Amendment 19 provided analyzedGESSARs'go%TGETAB,,he this information. We we had not co-Shed our gd,.'ew of will report the results S
GETAB.
gS of our review in an SER supplement. (12/6/74)
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SER SECTION STAFF CONCERN STATUS 5.2.2 We will require GE to commit We need a commitment
'to perform a surveillance from the applicant.
x program on the new.. safety /
l relief values for the BWR/6 and periodically report the results of that program.
9.
5.4.5 We require the RHR system GE feels that they to be single failure proof can achieve a cold-as required by GDC 34 of shutdown even if a
single failure occurs in the RHR system.
i 10.
6.2.1.4 We have not had t4 to complete We will reg.c our our review of t'3 suppression resulte d an SER g
40 s
pool makeup s.em since GE has sup ge ent.
only recer e, submitted this g
informs' a.
11.
6.2.1.5 As a result of GE',dincreasing GE is working on this l
the design drywe's4 external item and we will report pressure, the eher and size further in an SER vacuum breakr should be reduced supplement.
to reduce F potential sources i
of bypass.eakage In addition s I
GEneedstofur4a r justify Fp*
o don-assumptions +,e j used in t o
5 tainment v % m breaker epilysis, i
12.
6.2.1.7 We will require GE to provide GE says the results of all the assumptions used in these analyses will be the containment subcompartment ready by January 31, pressure analyses as well as 1975.
provide the results of those analyses.
13, 6.2.1.8 We will require further dis-GE is working with us cussion of how potential post-to resolve these con-LOCA steam bypass of the sup-cerns. We expect to be pression pool is prevented.
able to report on The identity of all potential resolution of this in paths needs to be addressed as an SER supplement.
well as periodic surveillance of those paths.
..a i
r SER SECTION STAFF CONCERN
' STATUS i.
6.2.3 We will require a pressure GE needs to provide fuel b1dg. is analysis of the fuel building further analysis to only item and ECCS and RWCV pump rooms demonstrate that t demonstrate that these negative pressure is needing pressure ana ysis.
areas remain at a negative maintained.
pressure of 1/4" w.g. following a LOCA.
15.
6.2.4 If GE wishes to purge the GE needs to provide 11.3.1 containment continuously, added information
.they will have to. provide with respect to
-additional information their proposal.
s related to filtration of the discharged flow and the design of equipment to isolate the flow.
16.
6.3.1 We will requ! 3 GE to perform GE has not done the ECCS analys' assumir the tv 5 analysis assuming LPCI pumpr te dive'S.d to t*fi two LPCI pumps are l'
spray mo<'
fter a g > minuts?
diverted.
I delay t emonstrhethat[e.e v
T'eptab!.ty perfo' nee and c
of t*
ECCS is nst adve-ely affs.ted.
17.
6.3.1 We will require GE to provide GE has not provided the post-LOCA manual actions to a satisfactory assure that there are no unde-response to date, Sirable Consequences resulting including Amendment 22.
from improper operator actions.
Information needed is listed in Section 6.3.1.
18.
6.3.2 We will require an analysis that GE has recently provided shows that the consequences of a such analyses. We will LOCA with a recirculation loop report on this in an valve closure will not cause the SER supplement. A=end-peak clad temperature to exceed ment 21 analysis is not acceptance criteria values.
acceptable.
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7-9 7.1,1 of GESSAR identifies some of the major areas of design I
changes.
Since a preliminary design of the instrumentation for the engineered safety feature systems is not yet available, our review has been directed at evaluating the proposed design criteria and the conceptual design described in GESSAR.
The
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status of our review of the instrumentation and controls for the engineered safety feature systems is discussed in subsequent sections of this report.
The results of our evaluation presented in Section 7.2 of this report with regard uo the use of analog sensors, the criteria for instrumentrangeandtrippbintselection,andtheadequacyofthe periodic testing provisions _for the solid state protection system are also applicable to the' instrumentation for the engineered j
safety feature systhms.
We have concluded that, except as discussed in Section 7.3.6 I
of this report, the criteria listed in Figure 7.1-2 of GESSAR and identified by GE as applicable to the engineered safety feature 1
systems form a generally acceptable basis for proceeding with the development of preliminary designs subject to the detailed staf f review and approval of the preliminary designs following the issuance of the PDA.
In addition, in response. to the staff 's position, GE has committed to designing all essential auxiliary supporting systems (e.g., essential service water) in accordance with the same
e.
4 SER SECTION STAFF CONCERN STATUS T
6.3.2 GE will need to reanalyze GE recently submitted the LOCA using methods this information and we acceptable to the staff are reviewing it~and.,
and in accordance with-will report in an SER Appendix K of 10 CFR 50.
supplement. (12/6/74) 20.
7.0 GE needs to rovide th design GE is working to 8.0 bases and
.iteria, f.ctional prepare information diagratr and an ev '.iation for our review.. We of tb-esigns of
.e"instrumen-will report on this in tat and contr areas.
In an SER supplement.
a~
. tion incon tencies within Chapter 7 of *4 SAR and between Chapter 7 a 9 other chapters
.need to be arrected.
21.
9.1.3 We require ane' h. source of GE has proposed
. of e
water f S* goy,cy I makeup water systeyeIs.vice seismic Ca*
the essential ne spent' fuel this pool ner than RHR.
source.
e are 0
3 reviev., this and wi] *.eport in an P'
supplement.
22.
9.1.3 GE needs to demons' ;.te that 100'F GE has recently.ovided is the maximum r
_1on cooling such informat' We have 4.
water tempera *ebe that could notyetcom,pkedour occur in tb oYoalysis of fuel review.
r %ill report o
g pool coo 1 4, capability even on this +6em in an SER in the ent the normal heat supple at when our sink
, unavailabic.
revie. is finished.
23.
9.2 We will require further Same status as item 22.
discussion, P and I diagrams There are still some open and safety evaluations of issues in 9.2.
Many various water systems othets have been resolved.
discussed in Section 9.2 of our SER.
24.
9.3.1 GE needs to provide further Same status as item 22.
MSLIV leakage control system Two minor items still discussion.
unresolved.
i 25.
9.4 Thereareseverge.kACsystems Same ste*goYIs item 22.
that are pregc+ o single failures.
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.SER SECTION STAIT CONCERN '
STATUS 9.5 GE needs to provide added GE needs to supply information with respect added information.
to the fire protection We will report in system for it to be a supplement.
acceptable.
- 27. '11.3.2 Additional means to reduce GE is reviewing the: activity of gaseous this item.
releases are required since the SGTS appears to be too small to handle exhausts from all areas directed towards it.
- 28. ~11.4 We require that space'for GE is proposing a solid waste-storage be one month storage provided to allow for more capability.
than one month decay.
N GEshofbverifeg%'e GE feels their waste 29.
11 4 so1#p3 of fre %ater in abse-preparation methods
.wasterg4~
prevent. free water.-
I
- 30. 15.1 We will' require further GE is preparing i
evaluation of transients information to with PRT, and what the address these alternatives are to PRT.
concerns.
NEW ISSUES 31.
5.2.1 We requ' GE to / ine the
.GE feels that they can upset;#adcond!cfnasupset justify by time history tran' t.nts plug *+.he OBE.
analyses that such a i
combination is not required.
32.
5.2.2 GE has not justified (Ament-GE is preparing this ment 21) why they went from information.
22 to 19 safety relief valves.
/
33, 6.2.4 GE has vp presented r s GE has addressed these Y
cons 4 o,nt descrie
_ items further. We will re-in p ament lingsS. ggt.' of
.enetrating view them.We will report es.,tainment, t.id they need to on this by 12/6/74 environmental criteria clarify the environmental still outstanding.
design criteria and bases for safety related equipment in the drywell and containment.
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