ML032690082
| ML032690082 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 09/25/2003 |
| From: | Thadani M NRC/NRR/DLPM/LPD4 |
| To: | Terry C TXU Energy |
| Thadani M, NRR/DLPM, 415-1476 | |
| Shared Package | |
| ML032751033 | List: |
| References | |
| TAC MB7984, TAC MB7985 | |
| Download: ML032690082 (20) | |
Text
September 25, 2003 Mr. C. Lance Terry Senior Vice President
& Principal Nuclear Officer TXU Energy ATTN: Regulatory Affairs P. O. Box 1002 Glen Rose, TX 76043
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 & 2 - ISSUANCE OF AMENDMENTS RE: ELIMINATION OF PERIODIC PROTECTION CHANNEL RESPONSE TIME TESTING (TAC NOS. MB7984 AND MB7985)
Dear Mr. Terry:
The Commission has issued the enclosed Amendment No. 107 to Facility Operating License No. NPF-87 and Amendment No. 107 to Facility Operating License No. NPF-89 for Comanche Peak Steam Electric Station (CPSES), Units 1 & 2, respectively. The amendments consist of changes to the Final Safety Analysis Report (FSAR) and Technical Specification (TS) Bases in response to your application dated March 6, 2003, as supplemented by letters dated July 25, August 29, and September 16, 2003.
Pursuant to TS 5.5.14b and 10 CFR 50.59, the amendments revise the CPSES, Units 1 and 2, FSAR and TS Bases to indicate that the response time testing may be eliminated for selected Reactor Trip System and Engineered Safety Features Actuation System protection channel equipment. The response time may be determined using the methodology described in Report WCAP-14036-P-A, Revision 1, Elimination of Protection Channel Response Time Tests.
A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,
/RA/
Mohan C. Thadani, Senior Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446
Enclosures:
- 1. Amendment No. 107 to NPF-87
- 2. Amendment No. 107 to NPF-89
- 3. Safety Evaluation cc w/encls: See next page
September 25, 2003 Mr. C. Lance Terry Senior Vice President
& Principal Nuclear Officer TXU Energy ATTN: Regulatory Affairs P. O. Box 1002 Glen Rose, TX 76043
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2 -
ISSUANCE OF AMENDMENTS RE: ELIMINATION OF PERIODIC PROTECTION CHANNEL RESPONSE TIME TESTING (TAC NOS. MB7984 AND MB7985)
Dear Mr. Terry:
The Commission has issued the enclosed Amendment No. 107 to Facility Operating License No. NPF-87 and Amendment No. 107 to Facility Operating License No. NPF-89 for Comanche Peak Steam Electric Station (CPSES), Units 1 & 2, respectively. The amendments consist of changes to the Final Safety Analysis Report (FSAR) and Technical Specification (TS) Bases in response to your application dated March 6, 2003, as supplemented by letters dated July 25, August 29, and September 16, 2003.
Pursuant to TS 5.5.14b and 10 CFR 50.59, the amendments revise the CPSES, Units 1 and 2, FSAR and TS Bases to indicate that the response time testing may be eliminated for selected Reactor Trip System and Engineered Safety Features Actuation System protection channel equipment. The response time may be determined using the methodology described in Report WCAP-14036-P-A, Revision 1, Elimination of Protection Channel Response Time Tests.
A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,
/RA/
Mohan C. Thadani, Senior Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446
Enclosures:
- 1. Amendment No. 107 to NPF-87
- 2. Amendment No. 107 to NPF-89
- 3. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC PDIV-1 Reading RidsNrrDlpmPdiv (HBerkow)
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G.Hill (4)
DRIP/RORP/TSS VHall Package No.: ML032690115 TS Bases:
NRR-100 Adams Accession No.: ML032690082
- See previous concurrence **SE dated 8/22/03 NRR-058 OFFICE PDIV-1/PM PDIV-1/LA RORP/SC EEIC/SC OGC PDIV-1/SC NAME MThadani:sab DJohnson CSS for TBoyce EMarinos**
RHoefling* nlo w/changes RGramm DATE 9/22/03 9/22/03 9/25/03 08/22/03 09/10/03 9/25/03 OFFICIAL AGENCY RECORD DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML032690082.wpd
TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION, UNIT NO. 1 DOCKET NOS. 50-445 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 107 License No. NPF-87 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by TXU Generation Company LP, dated March 6, 2003, as supplemented by letters dated July 25, August 29, and September 16, 2003, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, by Amendment No. 107 the license is amended to authorize revision to the Final Safety Analysis Report (FSAR) and Technical Specification Bases pursuant to Technical Specification Section 5.5.14b, as set forth in the application for amendment by TXU Generation Company LP dated March 6, 2003, as supplemented by letters dated July 25, August 29, and September 16, 2003. TXU Generation Company LP shall update the FSAR in accordance with 10 CFR 50.71(e) and operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan to reflect the revised licensing basis authorized by this amendment.
3.
The license amendment is effective as of its date of issuance, the Technical Specification Bases shall be implemented within 60 days from the date of issuance, and the FSAR changes shall be implemented in the next periodic update to the FSAR in accordance with 10 CFR 50.71(e).
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Robert A. Gramm, Chief, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Bases Date of Issuance: September 25, 2003
TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION, UNIT NO. 2 DOCKET NO. 50-446 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.107 License No. NPF-89 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by TXU Generation Company LP, dated March 6, 2003, as supplemented by letters dated July 25, August 29, and September 16, 2003, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, by Amendment No. 107 the license is amended to authorize revision to the Final Safety Analysis Report (FSAR) and Technical Specification Bases pursuant to Technical Specification Section 5.5.14b, as set forth in the application for amendment by TXU Generation Company LP dated March 6, 2003, as supplemented by letters dated July 25, August 29, and September 16, 2003. TXU Generation Company LP shall update the FSAR in accordance with 10 CFR 50.71(e) and operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan to reflect the revised licensing basis authorized by this amendment.
3.
The license amendment is effective as of its date of issuance, the Technical Specification Bases shall be implemented within 60 days from the date of issuance, and the FSAR changes shall be implemented in the next periodic update to the FSAR in accordance with 10 CFR 50.71(e).
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Robert A. Gramm, Chief, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Bases Date of Issuance: Septelmber 25, 2003
ATTACHMENT TO LICENSE AMENDMENT NO. 107 TO FACILITY OPERATING LICENSE NO. NPF-87 AND AMENDMENT NO. 107 TO FACILITY OPERATING LICENSE NO. NPF-89 DOCKET NOS. 50-445 AND 50-446 Replace the following pages of the Appendix A Technical Specification Bases with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert B 3.3-63 B 3.3-63 B 3.3-118 B 3.3-118 B 3.3-119 B 3.3-119
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 107 TO FACILITY OPERATING LICENSE NO. NPF-87 AND AMENDMENT NO. TO FACILITY OPERATING LICENSE NO. NPF-89 TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2 DOCKET NOS. 50-445 AND 50-446
1.0 INTRODUCTION
By application dated March 6, 2003, as supplemented by letters dated July 25, August 29, and September 16, 2003, TXU Generation Company LP (the licensee) requested changes, pursuant to 10 CFR 50.59 and Technical Specification (TS) Section 5.5.14b, to the Final Safety Analysis Report (FSAR) and TS Bases for the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2. The supplemental letters dated July 25, August 29, and September 16, 2003, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staffs original proposed no signficant hazards consideration determination as published in the Federal Register on April 15, 2003 (68 FR 18288).
The proposed changes would revise the FSAR and TS Bases to indicate that the response time for selected Reactor Trip System (RTS) and Engineered Safety Features Actuation System (ESFAS) protection channel equipment may be determined using the methodology described in WCAP-14036-P-A, Revision 1, Elimination of Periodic Protection Channel Response Time Tests, dated December 1995 (the WCAP). Specifically, the proposed changes would revise the Bases for TS 3.3.1 and TS 3.3.2 to cite this report and also add a new reference on TS Bases pages B 3.3-63 and B 3.3-119.
This safety evaluation addresses the acceptability of the proposed license amendments.
2.0 REGULATORY EVALUATION
The current standard technical specifications require nuclear power plants to periodically perform Response Time Tests (RTT) for instrument channels in the Reactor Protection System, Emergency Core Cooling System, and the Isolation Actuation System. The intent of these tests is to ensure that changes in instrumentation response time beyond the limits assumed in the plants safety analyses are detected and combined with instrument calibrations to ensure that the instrumentation is operating correctly.
The Institute of Electrical and Electronics Engineers (IEEE) Standard 338-1977, "Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety Systems," which is endorsed in Regulatory Guide 1.118, Revision 2, "Periodic Testing of Electric Power and Protection Systems," defines a basis for eliminating RTT. Specifically, Section 6.3.4 of IEEE Standard 338-1977 states, in part, the following basis:
Response time testing of all safety-related equipment, per se, is not required if, in lieu of response time testing, the response time of the safety system equipment is verified by functional testing, calibration check, or other tests, or both. This is acceptable if it can be demonstrated that changes in response time beyond acceptable limits are accompanied by changes in performance characteristics which are detectable during routine periodic tests.
The Westinghouse Owners Group (WOG) performed two analyses to assess the impact of elimination of RTT for instruments and instrument loops. The first of these analyses was WOG Licensing Topical Report WCAP-13632-P-A, Revision 2, "Elimination of Pressure Sensor Response Time Testing Requirements," dated August 1995. It was approved by the U.S.
Nuclear Regulatory Commission (NRC) staff as documented in a safety evaluation report (SER) dated September 5, 1995. The second, WCAP-14036-P-A, Revision 1, was approved by the NRC staff as documented in an SER dated October 6, 1998. Each of these SERs stipulated conditions that individual plant licensees must meet when implementing the guidelines in WCAP-13632 and WCAP-14036 on a plant-specific basis. The SER on WCAP-14036, which the licensee has used to justify the proposed changes, requires that the licensee verify that the Failure Modes and Effects Analysis (FMEA) performed in the WCAP is applicable to the equipment actually installed in the licensees facility, and that the analysis is valid for the versions of the boards used in the protection system.
3.0 TECHNICAL EVALUATION
The NRC staff has reviewed the licensees regulatory and technical analyses in support of its proposed license amendment. The detailed evaluation of the TS Bases changes is provided in the following subsections. Corresponding changes to FSAR (Update) are provided by the licensee in Attachment 4 of the March 6, 2003, request for amendment.
3.1 TS Bases Changes The licensee proposed elimination of RTT for the RTS and Engineered Safety Feature systems, and instead will depend upon calibration and other periodic testing, as described in WCAP-14036, in order to determine the proper operation and functioning of the above systems instrumentation. In those cases where the TS Bases require the licensee to verify that a protective system can meet its protective function in a prescribed time, a bounding response time will be added to those portions of the protective system actually tested for response time in order to determine the total system response time. The requirement to actually measure the response times would be eliminated, and instead, the response times will be verified by summing allocated times for the process protection system, the nuclear instrumentation system, and the logic system. These allocated values will be added to the measured times for the sensors and actuated devices, and compared to the overall analysis limits.
Verification of RTT in the place of actual testing requires a TS Bases change. Appendix A of WCAP-14036 lists the TS Bases changes based on the Standard TS wording found in NUREG-0452, "Standard Technical Specifications for Westinghouse Pressurized Water Reactors," and NUREG-1431, "Standard Technical Specifications - Westinghouse Plants."
These modify the following:
TS Definitions: Add a sentence to the Engineered Safety Features Response Time (ESFRT) and Reactor Protection System Response Time (RPSRT) definitions.
TS Instrumentation: In the Surveillance Requirements for ESFRT and RPSRT, change the word demonstrated to verified.
TS Bases Instrumentation: Change the word demonstrated to verified and add two paragraphs.
TS Bases Surveillance Requirements: In the sections addressing ESFRT and RPSRT, add two paragraphs.
TS Bases
References:
In the sections addressing ESFRT and RPSRT, add two references.
The TS Bases changes listed in the licensees amendment request differ from those in the WCAP, which are based on Standard TS wording. This is because CPSES has adopted the Improved TSs, which already incorporate the majority of the wording changes.
The actual change to the licensee's TS Bases revises the TS Bases for "Engineered Safety Features (ESF) Response Time" and "Reactor Trip System (RTS) Response Time" to provide for verification of response time for selected components, provided that the components and the methodology for verification have been previously reviewed and approved by the NRC. The TS requirements for response time verification will continue to be implemented by surveillance requirements 3.3.1.16 and 3.3.2.10.
Based on the above, the NRC staff concludes that the proposed changes reflect the adoption of previous NRC-approved methods. They are based on the Westinghouse Report WCAP-14036-P-A, Revision 1, and the NRC staff SER approving the Westinghouse report; the adoption of the wording similar to the NRC staff-approved standard TSs; and addition of the citation of WCAP-14036-P-A, Revision 1, as a reference in the proposed Bases change pages.
Accordingly, the proposed changes to Bases pages B 3.3-63, B 3.3-118, and B 3.3-119 are acceptable.
3.2 Verification of Plant-Specific Conditions The SER approving WCAP-14036, Revision 2, states that licensees submitting plant-specific license amendment (TS Bases change) requests must verify that the FMEA performed by the WOG is applicable to the equipment actually installed in the licensee's facility, and that the analysis is valid for the versions of the boards used in the protection system. Westinghouse letters WOG-98-238, WOG-98-244, and WPT-16357, identify the versions of the 7300 system cards for which the FMEA referenced in WCAP-14036 is applicable. The licensee has confirmed that the FMEA presented in WCAP-14036 is applicable to and valid for the equipment actually installed at CPSES. The staff has verified that with one exception, the FMEA is applicable to the equipment for which CPSES has requested the elimination of RTT.
The N-16 Power Range Module (PRM) was not included in WCAP-14036, and was therefore not approved for elimination of RTT in the staff SER. The licensee agreed that WCAP-14036 does not apply to this module, and its July 25, 2003, response to the staffs request for additional information (RAI) withdrew their request to eliminate RTT for the PRM. TXU Generation Company LP will continue to perform actual RTTs on the PRM.
3.3 Bounding Response Times When a plant accident analysis determines that a mitigation system is required to actuate in a certain response time, the testing for that response time is generally required by TS. The licensees amendment request will eliminate some of the testing previously required. The WCAP mentioned above provides adequate justification that calibrations and other surveillance testing will prove that the instruments are functioning properly. When the testing is not done to a portion of the instrument loop, but the TS Bases requires the verification of assumptions made in the accident analysis, some assumed or bounding value for the untested portion of the loop must be added to the tested portion, to arrive at a total system response time.
WCAP-14036 includes these maximum or bounding response times for the equipment which was analyzed in that report. Table 1 lists the values taken from section 4.5 of the WCAP which were used to determine the channel allocations. Tables 2 and 3 list the bounding sensor response times for CPSES which were included in Enclosure 3 of the July 25, 2003, TXU Generation Company LP RAI response.
The staff has verified that the values listed in the tables have been previously approved in the SER approving WCAP-14036, and are therefore acceptable.
3.4 FSAR (Updates) Changes The FSAR (Updates) changes provided by the licensee in Attachment 4 of the March 6, 2003, request for amendment correspond to the changes evaluated for TS Bases above. The proposed changes are, therefore, acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Texas State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration (68 FR 40721, published July 8, 2003) and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: V. Hall Date: September 25, 2003
TABLE 1 SELECTED RESPONSE TIMES FROM WCAP-14036-P-A, REVISION 1 Board WCAP Allocation 7300 Process Protection System Multiplier/Divider - NMD 0.104 RTD Amplifier - NRA 0.213 Summing Amplifier - NSA 0.0381 Function Generator - NCH 0.0681 Loop Power Supply - NLP 0.060 Comparator - NAL 0.005 Westinghouse NIS Level Trip 0.065 Westinghouse Solid State Protection System All Reactor Trips 0.020 ESFAS Through Master Relay 0.088 ESFAS Slave Relays 0.0362 NOTES:
1 The licensee rounded up this number from 0.0375 2 Allocated time for each relay in series
TABLE 2 PROPOSED BOUNDING VALUES FOR COMANCHE PEAK STEAM ELECTRIC STATION REACTOR TRIP FUNCTIONS Function1 Nuclear Instrumentation/
7300 System SSPS Total WCAP Allocation2 Process String for which WCAP times are credited WCAP Allocation2 SSPS String for which WCAP times are credited WCAP Allocation2 Power Range Neutron Flux High Setpoint NIS 0.065 Input+Logic 0.020 0.085 Power Range Neutron Flux Low Setpoint NIS 0.065 Input+Logic 0.020 0.085 Overtemperature N-16 (Delta Flux Upper-Lower)
NSA+NSA+NSA+
NAL 0.119 Input+Logic 0.020 0.139 Overtemperature N-16 (Delta Flux Lower-Upper)
NSA+NSA+NSA+
NAL 0.119 Input+Logic 0.020 0.139 Overtemperature N-16 (Tcold)
NRA+NSA+NAL 0.256 Input+Logic 0.020 0.276 Overtermperature N-16 (Pressurizer Pressure)
NLP+NSA+NSA+
NAL 0.141 Input+Logic 0.020 0.161 Overtemperature N-16 (N-16 Power)
NSA+NMD+NSA+
NSA+NCH+NSA+
NAL 0.329 Input+Logic 0.020 0.349 Overpower N-16 NSA+NMD+NSA+
NSA+NCH+NSA+
NAL 0.329 Input+Logic 0.020 0.349 Pressurizer Pressure Low NLP+NAL 0.065 Input+Logic 0.020 0.085 Pressurizer Pressure High NLP+NAL 0.065 Input+Logic 0.020 0.085 Reactor Coolant Flow Low NLP+NAL 0.065 Input+Logic 0.020 0.085 Undervoltage - Reactor Coolant Pumps N/A N/A Input+Logic 0.020 0.020 Underfrequency - Reactor Coolant Pumps N/A N/A Input+Logic 0.020 0.020 Steam Generator Water Level Low - Low NLP+NAL 0.065 Input+Logic 0.020 0.085 NOTES:
1 Reference CPSES Technical Requirements Manual, Table 13.3.1-1.
2 All response times presented in this table are specified in seconds.
TABLE 3 PROPOSED BOUNDING VALUES FOR CPSES ESFAS FUNCTIONS Function1 7300 System SSPS Total WCAP Allocation4 Process String for which WCAP times are credited WCAP Allocation4 SSPS String for which WCAP times are credited WCAP Allocation4 Safety Injection Containment Pressure High-1 NLP+NAL 0.065 ECCS Input+Logic+Master
+Slave+Slave 0.124 0.189 Reactor Trip Input+Logic 0.020 0.085 Emergency DG Operation Input+Logic+
Master+Slave 0.088 0.153 Containment Spray Pump Input+Logic+
Master+Slave 0.088 0.153 Pressurizer Pressure Low NLP+NAL 0.065 ECCS Input+Logic+
Master+Slave+
Slave 0.124 0.189 Reactor Trip Input+Logic 0.020 0.085 Containment Ventilation Isolation Input+Logic+
Master+Slave+
Slave 0.124 0.189 Emergency DG Operation Input+Logic+
Master+Slave 0.088 0.153 Steamline Pressure Low NLP+NAL 0.065 ECCS Input+Logic+
Master+Slave+
Slave 0.124 0.189 Reactor Trip Input+Logic 0.020 0.085 Emergency DG Operation Input+Logic+
Master+Slave 0.088 0.153
TABLE 3 (Continued)
Function1 7300 System SSPS Total WCAP Allocation4 Process String for which WCAP times are credited WCAP Allocation4 SSPS String for which WCAP times are credited WCAP Allocation4 Containment Spray Containment Pressure High-3 NLP+NAL 0.065 Containment Spray Header Isolation Valves Input+Logic+
Master+Slave 0.088 0.153 Containment Isolation Phase A Isolation Safety Injection Longest SI Signal 0.065 Input+Logic+
Master+Slave+
Slave 0.124 0.189 Steamline Isolation Containment Pressure High-2 NLP+NAL 0.065 Input+Logic+
Master+Slave 0.088 0.153 Steamline Pressure Steamline Pressure Low NLP+NAL 0.065 Input+Logic+
Master+Slave 0.088 0.153 Steamline Pressure High NLP+NAL 0.065 Input+Logic+
Master+Slave 0.088 0.153 Turbine Trip2 and Feedwater Isolation Steam Generator Water Level High-High NLP+NAL 0.065 Input+Logic+
Master+Slave 0.088 0.153 Safety Injection Longest SI Signal 0.065 Input+Logic+
Master+Slave 0.088 0.153 Auxiliary Feedwater Steam Generator Water Level Low-Low NLP+NAL 0.065 Motor Driven AFW Input+Logic+
Master+Slave+
Slave 0.124 0.189 Turbine Driven AFW Input+Logic+
Master+Slave+Slave 0.124 0.189 Safety Injection Longest SI Signal 0.065 Input+Logic+Master
+Slave+Slave 0.124 0.189 Loss of Offsite Power3
TABLE 3 (Continued)
Function1 7300 System SSPS Total WCAP Allocation4 Process String for which WCAP times are credited WCAP Allocation4 SSPS String for which WCAP times are credited WCAP Allocation4 Auto Switchover to Containment Sump RWST Level Low-Low Coincident with Safety Injection NLP+NAL 0.065 Input+Logic+Master
+Slave 0.088 0.153 NOTES:
1 Reference CPSES Technical Requirements Manual, Table 13.3.2-1.
2 Response time testing is not required for the Turbine Trip function.
3 The Loss of Offsite Power signal does not pass through the 7300 System or SSPS. This function is included in this table for completeness 4
All response times presented in this table are specified in seconds.
Comanche Peak Steam Electric Station, Units 1 & 2 cc:
Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 2159 Glen Rose, TX 76403-2159 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 Mr. Roger D. Walker Regulatory Affairs Manager TXU Generation Company LP P. O. Box 1002 Glen Rose, TX 76043 George L. Edgar, Esq.
Morgan Lewis 1111 Pennsylvania Avenue, NW Washington, DC 20004 County Judge P. O. Box 851 Glen Rose, TX 76043 Environmental and Natural Resources Policy Director Office of the Governor P. O. Box 12428 Austin, TX 78711-3189 Mr. Richard A. Ratliff, Chief Bureau of Radiation Control Texas Department of Health 1100 West 49th Street Austin, TX 78756-3189 Mr. Brian Almon Public Utility Commission William B. Travis Building P. O. Box 13326 1701 North Congress Avenue Austin, TX 78701-3326 Ms. Susan M. Jablonski Office of Permitting, Remediation and Registration Texas Commission on Environmental Quality MC-122 P. O. Box 13087 Austin, TX 78711-3087 Terry Parks, Chief Inspector Texas Department of Licensing and Regulation Boiler Program P. O. Box 12157 Austin, TX 78711