ML20196C528
| ML20196C528 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 11/24/1998 |
| From: | Terry C, Walker R TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20196C534 | List: |
| References | |
| TXX-98253, NUDOCS 9812020065 | |
| Download: ML20196C528 (6) | |
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Log # TXX-98253 r
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File # 10010 1
916 7UELECTRIC Ref. # 10 CFR 50.90 10 CFR 50.36
- c. imeelnerry senior vice emisen:
November 24,1998
& PrincipalNuclear Officer U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 FOLLOW-UP ITEMS RELATED TO THE PROPOSED CONVERSION TO THE IMPROVED TECHNICAL SPECIFICATIONS SECTION 1.0,3.4 AND 3.6 l
REF: 1) TU Electric letter, logged TXX-97105, from C. L. Terry to the NRC dated May 15,1997
. 3) TU Electric letter, logged TXX-98195, from C. L. Terry to the NRC dated August 28,1998
TU Electric requested an amendment to the Comanche Peak Facility Operating Licenses 4
(NPF-87 for Unit 1 and NFP-89 for Unit 2) by incorporating changes to the Technical Specifications (TS) as provided in Reference 1. The NRC staff requested additional l) information regarding Section 3.4, " Reactor Coolant System," and Section 5.0, " Administrative j
Controls," which was provided in Reference 2. The NRC staff requested additionalinformation regarding Section 1.0, "Use and Application," Section 2.0, " Safety Limits," and Section 3.0,
" Limiting Conditions for Operation Applicability / Surveillance Requirement Applicability" which c[
i was provided in Reference 3. The NRC staff requested additionalinformation regarding tp o Section 3.1, " Reactivity Control Systems," Section 3.2, " Power Distribution Systems," Section )
3.5, " Emergency Core Cooling Systems," Section 3.9, " Refueling Operations," and 4.0,
" Design Features," which was provided in Reference 4. The NRC staff requested additional information regarding Section 3.6, " Containment Systems," which was provided in Reference
- 5. The Attachments to this letter provide (1) additional information or supporting documentation COMANCHE PEAK STEAM ELECTRIC STATION 7
pnnox 1002 Glen Rose Texas 76043-1002 9812020065 981124 PDR ADOCK 05000445 P-PDR
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TXX-98253 Page 2 of 2 questions, or (3) additional changes identified by t ponse, (2) answers to follow-up Reference 1 will be provided at a later date.This letter and e erence 1. A supplement to The only commitment contained in this letter is to provid later date.
e a supplement to Reference 1 at a (254-897-0122).If you have any questions conceming the content of thi l s etter, please contact Mr. Bob Dacko Sincerely, C. L. Terry By:
c(g6r d. Walker
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Regulatory Affairs Manager BSD/bd Attachments c-E. W. Merschoff, Region IV J.1. Tapia, Region IV Resident inspectors, CPSES T. J. Polich, NRR J. N. Donohew, NRR Mr. Arthur C. Tate Bureau of Radiation Control Texas Department of Public Health 1100 West 49* Street Austin, Texas 78704
TXX-98253 Page 2 of 2 not provided in the original Request for Addition Information response, (2) answers to follow-up questions, or (3) additional changes identified by the licensee.
This letter and its attachments are not a supplement to Reference 1. A supplement to Reference 1 will be provided at a later date.
The only commitment contained in this letter is to provide a supplement to Reference 1 at a later date.
If you have any questions conceming the content of this letter, please contact Mr. Bob Dacko (254-897-0122).
Sincerely, C. L. Terry By:
M lofg6r b. Wa'lker Regulatory Affairs Manager BSD/bd Attachments c-E. W. Merschoff, Region IV J. l. Tapia, Region IV Resident inspectors, CPSES T. J. Polich, NRR J N. Donohew, NRR Mr. Arthur C. Tate Bureau of Radiation Control Texas Department of Public Health 1100 West 49* Street Austin, Texas 78704
i Attachment to TXX-98253 i
Page 1 of 2 i
The item numbers are formatted as follows: [ Source] [lTS Section]-[nnn) l Source =
Q-NRC Question NR-NRC Follow-up Question
-j CA-AmerenUE i
DC-PG&E' WC -WCNOC l
CP - TU Electric TR -Traveler ITS ltem Number Applicability Enclosed 1.0 Q 1.1-4 DC, CP, WC, CA YES 1.0 NR 1.0-001 (NEW)
DC NA 3.4 Q 3.4.9-3 CP, WC YES 3.4 Q 3.4.12-5 CA, WC NA s
^
3.5 Q 3.5.5-2 CA, WC NA 3.6 Q 3.6.1-5 DC NA 3.6 Q 3.6.1-6 DC, CP, WC, CA YES j
3.6 Q 3.6.2-6 DC, CP, WC, CA YES 3.6 Q 3.6.3-1 CP, WC YES 3.6 -
Q 3.6.3-4 CP, WC, CA YES 3.6 Q 3.6.3-7 DC NA 3.6 Q 3.6.3-10 DC, WC, CA NA 3.6 Q 3.6.3-11 DC, CP, WC, CA YES 3.6 Q 3.6.3-13 WC, CA NA 3.6 Q 3.6.3-14 CP YES 3.6 Q 3.6.3-15 WC, CA NA 3.6 Q 3.6.3-16 DC NA 3.6 Q 3.6.3-17 WC, CA NA 3.6 Q 3.6.3-21 WC, CA NA 3.6 Q 3.6.3-24 WC, CA NA j
3.6 Q 3.6.3-28 DC, CP, WC, CA YES
'l 3.6 Q 3.6.3-30 CP YES
)
y 3.6 Q 3.6.3-33 WC, CA NA 3.6 Q 3.6.3-34 CA NA 3.6 Q 3.6.3-35 DC NA 3.6 Q 3.6.3-39 DC NA
^
3.6 Q 3.6.3-43 DC NA I
t i
Attachment to TXX-98253 Page 2 of 2 ITS ltem Number Applicability Enclosed 3.6 O 3.6.3-44 DC NA 3.6 Q 3.6.3-48 DC NA 3.6 Q 3.6.3-56 DC,CP YES 3.6 O 3.6.5-4 DC, WC NA 3.6 O 3.6.6-2 DC NA 3.6 Q 3.6.6-8 DC NA 3.6 O 3.6.6-13 DC, WC, CA NA 3.6 Q 3.6.6-15 DC NA 3.6 O 3.6.6-18 CA NA 3.6 Q 3.6.7-4 DC NA 3.6 O 3.6.7-12 CP YES 3.6 O 3.6.7-16 CP YES 3.6 Q 3.6.8-6 CA NA 3.6 Q 3.6.8-7 DC NA 3.6 CA 3.6-001 CA NA 3.6 CA 3.6-004 CA NA 3.6 CP 3.6-006 CP YES 3.6 DC 3.6-001 (NEW)
DC NA 3.6 WC 3.6-ED WC NA 4
3.6 WC 3.6-006 WC NA 3.6 WC 3.6-010 CA NA i
j 3.7 O 3.7.1-4 CA NA 3.9 CA 3.9-001 (NEW)
CA NA 3.9 DC ALL-005 DC NA (3.9 Section only) 5.0 O 5.6-2 DC NA
f E
ADDITIONAL INFORMATION COVER SHEET t
ADDITIONAL INFORMATION NO: Q 1.1-4 APPLICABILITY: CA, CP, DC, WC REQUEST:
CTS 1.13, Engineered Safety Features Response Time [Diablo Canyon, Wolf Creek, and Callaway]
i CTS 1.14, Engineered Safety Features Response Time [ Comanche Peak) l CTS 1.27, Reactor Trip System Response Time [ Wolf Creek and Callaway]
CTS 1.29, Reactor Trip System Response Time [Diablo Canyon and Comanche i
Peak]
j DOC 1-08-A ITS 1.1, Engineered Safety Feature (ESF) Response Time ITS 1.1, Reactor Trip System (RTS) Response Time JFD 1.1-5 i
The definitions for ESF Response Time and RTS Response Time are proposed to be revised to i
substitute the word " verified"in lieu of " measured." The JFD states that this change is made to be consistent with STS SR 3.3.1.6, SR 3.3.2.10, and TSTF-111, Rev.1. Mcwever, the DOC does not refer to TSTF-111 applicability for this change.
Comment: If NRC has not approved TSTF-111 by the time the draft safety evaluation is prepared, then this change should be withdrawn from the conversion submittal at that time.
1 This change will not be reviewed on a plant-specific basis. Also, revise the DOC to include TSTF-111 applicability.
. j FLOG RESPONSE (original): The response to Comment Number 1.1-4 will be provided separately after the August 17,1998 NRC letter to NEl on TSTF-111 has been fully evaluated.
i FLOG RESPONSE (revised): This is a modified response, which replaces the original response provided in Reference 2 of the cover letter, in order to provide the requested response.
1 i
The FLOG continues to pursue the changes proposed in TSTF-111 Rev. 4. The attached CTS and ITS mark-ups reflect that traveler's definition changes. In addition, DOC 1-08-A and JFD 1.1-5 have been revised.
DOC 1-08-A has been revised to read as follows:
"The current TS definitions for Engineered Safety Features Response Time and Reactor Trip System Response Time are modified to be consistent with NUREG-1431 Rev.1, as modified by TSTF-111. The addition of the statement that response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured, is administrative in nature. This is consistent with the methodology presently described in the current TS Bases for demonstrating total channel response time. Likewise, the addition of the statement that response times for selected components may be verified by other means approved by NRC is also administrative in nature since it allows no response time testing change unless NRC approval has been first obtained. This statement is consistent with Gection 6.3.4 of IEEE 338-1977, traveler TSTF-111, and approved topical reports on response time testing verification methodology."
i
'JFD 1.1-5 has been revised to read as follows:
"The definitions for ESF Response Time and RTS Response Time are revised consistent with traveler TSTF-111. The addition of the statement that response times for selected components may be verified by other means approved by NRC is administrative in nature since it allows no i
response time testing change unless NRC approval has been first obtained. This statement is
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consistent with Section 6.3.4 of IEEE 338-1977, traveler TSTF-111, and approved topical l
reports on response time testing verification methodology."
3 Since the NRC has not approved WCAP-14036-P the bracketed references to that document j
and its discussion of allocated response times for signal conditioning and actuation logic that are included in the STS Bases revisions specified by TSTF-111, Revision 4 are not included in i
the plant specific markups. However, Callaway and DCPP continue to pursue the sensor response time changes approved by the NRC in WCAP-13632-P-A as noted in Section 3.3 DOC 1-03-LS-1.
ATTACHED PAGES:, CTS 1.0, Definitions Enct2 1-4 and 1-8 Enci 3A 2
Enci3B 1
~
EnciSA Traveler Page,1.1-3 and 1.1-5 Enci 6A 1
Enci 6B 1, ITS 3.3, Instrumentation EnctSA Traveler Page Enci 58 8 3.3-59, B 3.3-59a, B 3.3-60, B 3.3-120a, B 3.3-121, B 3.3-121a and B 3.3-123 l
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