ML20135A812
| ML20135A812 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 02/24/1997 |
| From: | Terry C TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20135A815 | List: |
| References | |
| TXX-97048, NUDOCS 9702270419 | |
| Download: ML20135A812 (4) | |
Text
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m Nummer Log # TXX 97048
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File # 10010 '
Ref. #
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lilELECTRIC' February 24, 1997 C. Lance Terry Group Mce Prendent U. S. Nuclear Regulatory Commission Attn:
Document Control Room Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50 445 AND 50 446 TRANSHITTAL OF TECHNICAL REQUIREMENTS MANUAL (TRM)
REVISION 22 TU Electric herewith submits Revision 22 (enclosed) of the CPSES Technical Requirements Manual (TRM).
Enclosed is the following document:
Technical Requirements Manual 1 signed original Revision 22 and 10 copies The attachment contains a description of the changes. As has been the TV Electric practice in the past several TRH revisions all changes described in the attachment have been evaluated for relative significance (i.e., the group number 1, 2. 3, or 4 corresponds to each change justification as discussed in TU Electric letter TXX-88467 dated June 1. 1988).
In addition, all changes applicable to CPSES Units 1 and 2 have been reviewed under the TU Electric 10CFR50.59 process and found not to include any "unreviewed safety questions".
TRH Revision 22, dated February 24, 1997, became effective at 11:01 PM CST on February 24, 1997.
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9702270419'970224 VD36 i
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0 P. O. Box 1002 Glen Rose Texas 76043 1
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TXX 97048 Page 2 of 2 1
If you should have any questions, please contact Mr. Carl B. Corbin at (817) 897 0121.
Sincerely, C. L. Terry By:
D. R. Woodlan Docket Licensing Manager CBC/cbc Attachment Enclosure cc:
Mr. J. E. Dyer, Region IV Mr. J. I. Tapia, Region IV Mr. T. J. Polich, NRR Resident Inspector, CPSES l
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q Attachmst to TXk-97048 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT i
REVISION -
. 22 l
DETAILED DESCRIPTION l
Prefix Page Page 1 (as amended)
Group Description Seption:
1-2 2
Revises the "Overtemperature N.16" response time from "less than or equal to 7 seconds" to "less than or equal to 8 seconds" (ltem 7 of Table 1.1.1, Reactor Trip System Instrumentation Response Times). This change is applicable for Unit 2 only.
Revision
[
A time delay is added to each N16 Overtemperature trip channel to prevent unit trip from spurious signals, usually resulting from lightning strikes. The l
time delay is produced by adding a new card in each 7300 Protection cabinet.
Increased time response is justified by analysis. Since Reactor Trip system is i
safety-related, a single failure will not prevent completion of safety function required by accident analyses, and does not constitute a new failure mode.
i Setpoints and Allowable Values in Tech Specs remain valid with the I
increased response time.
Change Request Number TR 4
.I Related SER : 7.2.1 SSER : 22 Section: 7.2.1 l
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