ML20085N604
| ML20085N604 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 11/01/1983 |
| From: | Schroeder C COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 7549N, NUDOCS 8311110129 | |
| Download: ML20085N604 (5) | |
Text
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\\ Commonwealth Edison
(
'- / Ora First Nition 1 Ptna, Chicago. Ilhnois
\\ C ~7 Address R ply to: Post Offico Box 767 (j Chicago, Illinois 60690 November 1, 1983 Mr. Harold R. Denton, Director Of fice o f Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 i
Subject:
LaSalle County Station Unit 2 Updated Status of Completion of LSCS Unit 2 Preop'tational Test Program (Deferrt Request)
NRC Docket No. 5 -374 References (a):
(b):
LSCS Unit 1 Technical Specifications, License NPF-ll.
(c):
Cordell Reed letter to H. R. Denton dated July 21, 1983.
(d):
C.
W.
Schroeder letter to H. R.
Denton dated October 6, 1983.
Dear Mr. Denton:
Reference (a) describes the LSCS preoperational and startup test program.
Commonwealth Edison Company's original intentions were to complete the entire preoperational test program prior to fuel load.
However, as explained in Reference (c), it has become apparent that certain portions of a relatively small number of preoperational tests and system demonstrations have become the controlling items for fuel load.
The delays in completing these tests are due to a variety of design, delivery, and installation problems.
Commonwealth Edison has reviewed the remaining preoperational testing, considering both the safety aspects of the individual systems and the anticipated system completion dates.
Several of the systems and subsystems involved have been determined to have no impact on plant safety during shutdown and fuel loading conditions.
This determination is based on the Unit 1 Technical Specifications (Reference (b)), and, where the Technical Specifications have no specific requirements, prudent judgment.
The Unit 1 Technical Specifications were used because of the fluid state of the proposed Unit 2 Specifications; however, no differences between the two are expected to affect the justifications provided.
k O
DR I
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H. R. Denton November 1, 1983 References (c) and (d) provided Commonweath Edison's request for approval to defer the completion of certain preoperational tests listed i
on the Attachment beyond fuel load.
With the exception of Primary Containment Isolation and Process Sampling, no parts of any of the systems listed are required.
For these two tests, test evaluations will be completed prior to fuel load to ensure the adequacy of the portions of the systems required to support fuel load.
As explained in Reference (c), it should be noted that in a majority of cases it is anticipated that the physical testinc will be completed prior to fuel load.
The delay in the date requirec for test completion of remaining tests will allow additional time to ensure a thorough evaluation and review of the test results.
A review of Chapter 14 of the FSAR has revealed that several of the startup test abstracts list, as an Initial Condition, "All construc-tion and preoperational testing completed."
Approval by the NRC to defer completion of preoperational tests is understood to include authorization to deviate from this startup test prerequisite until the specified milestone is attained.
The purpose o' this letter is to provide you with another update of the status of the bystems listed in Reference (c).
The attachment to this letter indicates the current status of the preoperational tests for which deferral was requested and further substantiates our expectations that it is anticipated that, in a majority of cases, the physical testing will be completed prior to fuel load.
If there are any questions in ?.his matter, please contact this office.
l l
Enclosed for your use are one (1) signed original and forty (40) l copies of this letter and the attachment.
1 Very truly yours, V
=J= ~ ttlsl95 C. W. Schroeder Nuclear Licensing Administrator CWS/Im cc:
A. Bournia (Federal Express)
J. G. Keppler - RIII NRC Resident Inspector - LSCS 7549N
4 i
10/04/83 PROPOSED COMPLETION.
Status JUSTIFICATION TEST SECTIONS l
is initial Cri ticality 0% caplete.
TEST
.I No equipment in this system PT-NR202 ALL required during cold shutdown*
~
Traversing or refueling operations.
t in this system is initial Crlticality 10% complete.
Incore Probe No equipment PT-0G201 ALL.
~ ~.
required during cold shutdown Off-Gas or refueling operations.
Initial Criticality 100% cmplete Prlinary Containment integri ty b_ evaluation PT-PC201 ALL
'Is'not required durIng cold l
review done h
Primary shuttlown or refuelI,ng operations.
Containment In tegri ty inltial CritIcallty 1007, coniolete.
only' secondary containment test being cPT-PC203 Everything except
' Integrity is required during evaluated by Secondary Containment refueling operallonst Primary engineering Containment Isolation Isolations containment cannot be maintained Systems while fueling.
Inlttal Critlcallty 100% cmplete No equipment in this syite'm is -
evaluation review PT-Rl201 ALL required du' ring cold shutdown done Reactor Core or refuellr.g operations, Isolation
. Cooling InltIal CrIticallty ~
100% complete.
The remote shutdown system is test being PT-RP202 ALL not required during cold evaluated by shutdown or refueling operations.
enoineering s
Remote Shutdown initial Criticality.
90T complete.,
The reactor recirculation and ALL PT-RR201 flow control system is not required operable during cold Reactor Recirculation shutdown or refueling operations.
p '-
Requested Pre, operational Test Progrem Execptions
~10/04/83
- t..
Status COMPLETl0N REQUIRED PRIOR T0_
JUSTlFICATION TEST TEST SECTIONS Initial Crit 1cality 90% conplete No equipment in this test is PT-CH-201 ALL required operable during cold Containment' shutdown or refueling operations.
Honitoring PT-CH-202 ALL Ho equipment in this test is ini tial Cri ticali ty.
3Q%'conplete required operable during cold shutdown or refueling operations.
Post LOCA
- ~
Containment i
Monitoring Initlai Criticality LOO % conplete No equipment operated by drywell test being PT-IN201 ALL pneumatics is required operable evaluated by Drywell during cold shutdown or refueling engineering Pneumatics operations.
initial Criticality 100% conplete
'No leakage detection equipment svaluation -
PT-LD201 ALL
.Is required operable during f
review done, i
, Leakage
. cold' shutdown or refueling i
Detection
' operations.
Initial CriticalltY 88% cm plete fTlie HSIV Leakage Control System PT-MS20lA ALL is not required operable during HSIV Leakage cold shutdopn or refueling Control System operations.
initial Criticality 83% couplete No equipment in this test is PT-MS2018 ALL required operable during cold HSIV's and MS shutdown or refueling operations.
Instrumentation initial Heatup, prior 70%,conplete No equipment in this system is required to be operable until to exceedirg 122 psig PT-MS201C ALL the reactor is critical and ADS and MS Safety / Relief above 122 psig. Per USAR Chapter 14, this test is to be finished dyring heatup in the startup test program.
e 4
9
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4 2a 10/04/83 PROPOSED COMPLEil0N Status _ '.
TEST TEST SECTIONS JUSTIFICATION The probability of a severe translent initial lleat-up 100% cmp 10t6
~
evaluation review PT-Sl202 ALL (e.g.6 selsmic, LOCA) oc' curring during Plpe Vibration E
the preoperational test program that done.
Monitoring could damage system'plping or com-ponents iI the dynamic restraints are installed is acceptably low; and not the testing will be completed prior to power operation which would generate decay heat and fission product inventory.
Therefore, the use of these systems will not be required to protect the health and safety of the public prior to the tests.
i initial Criticality 0% cmplete.
PT-VP202 Portions involvi,g the hydrogen recombiner are l
not required to s0pport tinit 2 during Post LOCA Unl t 2 (Both recom-cold : shutdown 'and refueling ' operations.
Hydrogen biners have been Recombiners demonstrated with the Uni t I containme,t.
371L'omplete.
' Containment ventilatlon Is not Ini tial l{ eat-up PT-VP203 ALL
. required to maintain temperatures Containment dntil after reactor heatup has Ventilation occured and the reactor.,Is, adding
-heat to thg containment.
initial Criticality i 100% couplete No requirements exist to maintain test being 50-PS201 All portions other water quality other than for the evaluated by Process than those necessary Sampling to monttor reactor reactor water.
engineering water quallty Initial Criticality 100% conplete
- This system is non-safety related.
evaluation review SD-SA201 ALL Although it supplies some safety-done.
Service and
. - related components, they are instrument Air designed to fall in the conservative direction upon loss of air. This system has been in operation for ayear,andhasbeenareliable air source.
For the same reasons as applied to initial Heat-up 6A%[i ccuplete.
St';al201 ALL PT-Sl202 (above).