ML20067E022
| ML20067E022 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 12/13/1982 |
| From: | Schroeder C COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20067E024 | List: |
| References | |
| TASK-2.K.3.18, TASK-TM 5578N, NUDOCS 8212210463 | |
| Download: ML20067E022 (3) | |
Text
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Chicago, Illinois 60690 December 13, 1982 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
LaSalle County Station Units 1 and 2 Amendment No. 61 to the Final Safety Analysis Report (FSAR)
NRC Docke t - No s. 50-37 3 an d 50-37 4 -
Dear Mr. Denton:
Attacheo is Amendment No. 61 to the LaSalle County Station Units 1 and 2 Final Safety Analysis Report.
FSAR Amendment #61 is issued to bring the of ficial licensing record (FSAR) into confermance with the as-built and as-tested configuration o f the plant.
The update covers seismic qualification efforts completed during early 1982, reanalysis o f containment response with added inlet feedwater enthalpy, correction o f typographical errors and clarification of references, replacement of the ammonia detector for the control room HVAC; update o f the recirculation system description to include the flux estimator, and clarification of leak testing writeup.
Additionally an amplified definition of MSIV clos-ure time was made in the description of a startup test.
More explicit elaboration on these changes is given below.
These updates are informational to bring the FSAR into conformance with the as-built plant.
No setpoint changes are involved, no equipment deletions or invalidations are involved.
Specifically, Section 3.9 was re-edited to incorporate the results of the SQRT program and the plant equipment evaluation with the condensation oscillation loads and model refinements made during 1981.
The extension of vibratory conditions to 100 hertz from the earlier 33 hertz is reported therein.
Dynamic operability test results are included for the major NSSS. components, MSIV, and the mainsteam safety-relie f valves.
Reva11dation of the major reactor internals thru extensive normal operations and anticipated transients are now documented.
Extensive reanalysis of piping systems to include the NRC agreed-upon load combinations, with condensation oscillation loads, are also included in Section 3.9.3.
The adequacy of equipment support structures for floor-mounted equipment has been included also now that the lists are completed.
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6 H. R. Denton December 13, 1982 The containment response to LOCA with less downcomer submergence end with added feedwater inlet enthalpy is included in the update of Chapter 6 to the more conservative assumptions used in the bounding This refinement brings the FSAR into agreement with Chapter 6 of case.
the Design Assessment Report.
Additionally, several, word changes were made in Section 6.4 as a result of completing the leak rate tests.
Non e of these changed the initial intent of the original statements.
Likewise, as a result of system demonstration tests on HVAC equipment which confirmed' the mean estimated valves of temperature, humidity, and dif ferential pressure, Sections 7.12 and 9.4.1.2 which deal eith power-generation design bases were edited to remove the desian tolerances for these variables.
Their ramoval has no safety signifi-cance; in fact, such design tolerance numbers should never have appeared in the original FSAR text.
Startup test Table 14.2.-122, the MSIV closure test at various power levels, was amended by inclusion of two definitions of MSIV closure time:
one with the electrical circuit-delay time-interval and one without this interval.
This enables a more useful measurement during startup while still measuring overall response time for comparison to the safety analysis of 15.2.4.
Additionally, Figure 14.2-2 was amended to include additional test conditions for startup coverage on MSIV actuation in response to prior NRC requests.
Appendix G was updated on several pages to include reference to the flux estimator used in the recirculation system control loop (a non-safety system) and on several other pages to reference the more recent measurement of vessel subcooling resulting from better quality instrumentation which was installed in late 1981.
Typographical corrections and correction of internal references were made as follows:
Table 6.2.-21 at penetration M29, pages 7.2-3,4 ;
7.2-9, 12, 14, 20 and 92 ; page 8.3-38, page 9.5-14a.
of the as-built conditions which were improved as a result ofUpdated reporting pre-operational testing includes the following:
Use of Fyrequell EHC in the hydraulic controls for the flow control valve in the recirculation system as described in Appendix G; update of instrument ranges for the area radiation monitors as recorded in Table 12.3-13; clarification of the list of local alarms as listed on page 7.3.4.5; update of the instrument ranges of the ammonia detectors and the chlorine detectors used in the HVAC ducts to the control room as recorded on pages 7.3.52a, b and 9.4-6 and 9.4-12.
The changes made in fire detection and fire protection in response to Region III field audits are recorded in Sections 8.3, 9.5.1.2 and Appendix H.
All updates and corrections to text on fire protection and detection are recorded to bring the FSAR into conformance with the as-built condition o f the plant.
such as the fire quality of the door frames is fairly broad hence aThe applicability of c considerable number of Appendix H pages were updated to reflect the as-built conditions.
Sixteen pages were placed on hold pending completion of the door frame adequacy appraisal by a certifying body.
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H. R. Denton December 13, 1982 Appendix L.62 provides recorded documentation of prior letter submittals on II.K.'3.18 (TMI Ite m), " Modification o f ADS Logic", repre-senting the LaSalle fix for which NRC review and approval is still pending.
This amendment is needed to update the official FSAR such that the baseline record agrees with and incorporates the as-built and as-tested configuration.
To the best of my knowledge and belief, the statements contained in the attachment are true and correct.
In some respects, these state-ments are not based upon my personal knowledge but upon information furnished by other Commonwealth Edison employees and contractors.
Such information has been reviewed in accordance with Company practice and I believe it to be reliable.
Three (3) signed originals and sixty (60) copies o f this trans-mittal are submitted for your use.
If there are any questions in this matter, please contact this office.
Very truly yours, L Itjo}%z C. W. Schroeder Nuclea r Licensing Administrato r 1m Enclosure cc:
NRC Resident Inspector - LSCS SUBSCRIBED and SWORN to Defor me this
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