ML052870376
| ML052870376 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/10/2005 |
| From: | Bezilla M FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 3186, TAC MC3084 | |
| Download: ML052870376 (10) | |
Text
FENOC 5501 North State Route 2 FirstEnergy Nuclear Operating Company Oak Harbor. Ohio 43449 Mark B. Bezilla 419321-7676 Vice President - Nuclear Fax: 419-321-7582 Docket Number 50-346 10 CFR 50.90 License Number NPF-3 Serial Number 3186 October 10, 2005 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001
Subject:
Davis-Besse Nuclear Power Station (DBNPS)
Supplemental Information Regarding License Amendment Application to Revise Technical Specification (TS) 3/4.3.2.1, Safety Features Actuation System (SFAS) Instrumentation Setpoints and Surveillance Testing (License Amendment Request (LAR) 03-0014; TAC No. MC3084)
Ladies and Gentlemen:
By letter dated May 5, 2004 (Serial Number 3009), the FirstEnergy Nuclear Operating Company (FENOC) submitted an application for amendment of the Operating License, Appendix A, Technical Specifications (TS) for the DBNPS. Among other changes, the proposed amendment would: revise TS Table 3.3-4, "Safety Features Actuation System Instrumentation Trip Setpoints," "Allowable Values" entries for Safety Features Actuation System (SFAS) Functional Unit Sequence Logic Channel "a" - "Essential Bus Feeder Breaker Trip (90%)", and SFAS Functional Unit Sequence Logic Channel "b" -
"Diesel Generator Start, Load Shed on Essential Bus (59%)"; rename these trip relays to more accurately reflect their design function (replacing "90%" with "Degraded Voltage Relay (DVR)"; and "59%" with "Loss of Voltage (LVR)") and in TS Table 4.3-2, "Safety Features Actuation System Instrumentation Surveillance Requirements,"
establish annual calibration requirements for these same Functional Units, consistent with updated calculations and current setpoint methodology. The proposed changes incorporate administrative limits presently maintained by the DBNPS to ensure adequate voltage is provided to safety-related loads, and to preclude inadvertent actuation of the 4160 Volt Loss of Voltage Relay logic.
ACD
Docket Number 50-346 License Number NPF-3 Serial Number 3186 Page 2 On August 20, 2004, the NRC staff requested information regarding the electromechanical Loss of Voltage Relays, which were previously removed by modification, and the replacement solid state Loss of Voltage Relays. On October 12, 2004, FENOC representatives met with NRC staff at NRC Headquarters to discuss the NRC's request for additional information, and to present the associated instrument setpoint calculation. By letter dated January 17, 2005 (Serial Number 3100),
FENOC provided a written response to the NRC staff's request for additional information.
On July 19, 2005, the NRC staff informally requested FENOC to respond to a generic request for additional information included in a March 31, 2005 letter from James A. Lyons, NRC, to Mr. Alex Marion, Nuclear Energy Institute. A response to this request will be submitted under separate cover (Serial Number 3193).
FENOC proposes to add a footnote to TS Table 4.3-2, "Safety Features Actuation System Instrumentation Surveillance Requirements," regarding the as-left instrument setting.
This footnote is proposed to be added for consistency with the NRC staffs position stated in the March 31, 2005 letter, referenced above. The proposed footnote would read as follows:
The as-left instnrment setting shall be returnedto a setting within the tolerance band of the trip setpoint established to protect the safety linmit.
This footnote would be applicable to the Degraded Voltage Relays and the Loss of Voltage Relays. Enclosure 1 contains revised TS markup pages incorporating this change. Enclosure 2 contains the retyped TS pages incorporating this change.
The proposed footnote will ensure that the as-left instrument settings for the Degraded Voltage Relays and the Loss of Voltage Relays following annual Channel Calibrations and monthly Channel Functional Tests are conservative and in compliance with the requirements of 10 CFR 50.36, "Technical Specifications." Other than the administrative description of the change itself, the conclusions of the previously submitted evaluation for LAR 03-0014 are unaffected, including the technical analysis, no significant hazards consideration, and environmental consideration.
A list of regulatory commitments made in this letter is included in Enclosure 3. Should you have any questions or require additional information, please contact Mr. Henry L.
Hegrat, Supervisor - Fleet Licensing, at (330) 315-6944.
Docket Number 50-346 License Number NPF-3 Serial Number 3186 Page 3 The statements contained in this submittal, including its associated enclosures and attachments are true and correct to the best of my knowledge and belief. I am authorized by the FirstEnergy Nuclear Operating Company to make this submittal. I declare under penalty of perjury that the foregoing is true and correct.
Executed on: 0 c ('ge /0, zZ d, By: AXE4/
Bark B. Bezilla, Vice Prevdcnt-Nuclear MSH Enclosures cc: J. L. Caldwvell, Regional Administrator, NRC Region III N. Dragani, Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)
W. A. Macon, DB-1 NRC/NRR Project Manager C. S. Thomas, DB-I NRC Senior Resident Inspector Utility Radiological Safety Board
Docket Number 50-346 License Number NPF-3 Serial Number 3186 Enclosure I Page 1 of 3 REVISED PROPOSED MARKUP OF TECHNICAL SPECIFICATION PAGES 3/4 3-21 and 3/4 3-22 (TABLE 4.3-2)
(two pages follow)
TABLE 4.3-2 SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE U FUNCTIONAL UNIT CIIECK CALIBRATION TEST REQUIRED
- 1. INSTRUMENT STRINGS
- a. DELETED DELETED DELETED DELETED DELETED
- b. Containment Pressure - High S E M(2) 1,2,3
- c. Containment Pressure - High-High S E M(2) 1,2,3
- d. RCS Pressure - Low S R M 1,2,3
- e. RCS Pressure - Low-Low S R M 1,2,3
- f. BWST Level - Low-Low S E M 1,2,3
- 2. OUTPUT LOGIC
- a. Incident Level #1: Containment Isolation S E M 1,2,3,4
- b. Incident Level #2: High Pressure Injection and Starting Diesel Generators S E M 1,2,3,4 I
- c. Incident Level #3: Low Pressure Injection S E M 1,2,3,4
- d. Incident Level #4: Containment Spray S E M 1,2,3,4 0
W
- e. Incident Level #5: Containment Sump Recirculation Permissive S E M 1, 2, 3,4 00
- 3. MANUAL ACTUATION
'PO
- a. SFAS (Except Conthinment Spray NA' NA M(1) 1,2,3,4 9-.
and Emergency Sump Recirculation)
- b. Containment Spray NA NA M(1) 1,2,3
- 4. SEQUENCE LOGIC CHANNELS S NA M ,, ,3, 4 I
TABLE 4.3-2 (Continued)
W SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH W CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED 4SBEOI E -LQOICICIANNELS _
- a. aqqucr S NA M L1A
- h. Essential f Busee er BreakerpTripS A M3 12 DegradYlage.Relay(DVR)
- c. Diesel-GeneghtorStart, S Aj I 2.,14 Load Shed onEsscntialBus Los oY-olta ay MVR)
- 5. INTERLOCK CHANNELS
- a. Decay Heat Isolation Valve S R ** 1, 2, 3
- b. Pressurizer Heater S R ** 3 ##
jr
- eeSpeeiiatjon 4.5.^.d TABLE NOTATION I
p (I) Manual actuation switches shall be tested at least once per REFUELING INTERVAL. All other circuitry associated with manual safeguards actuation shall receive a CHANNEL FUNCTIONAL TEST at least once per 31 days.
(2) The CHANNEL FUNCTIONAL TEST shall include exercising the transmitter by applying either vacuum or pressure to the appropriate side of the transmitter.
(3) The as-lefinst inLstuinal~bereturnecdto-sclingwithinletolernnancd ofthe-trip soipntsishe pd-to-roteUhe saii 1y
^° limit.
00
+/-* SgeeSpecification 4.5.2d 00
- f# When either Decay Heat Isolation Valve is open.
Docket Number 50-346 License Number NPF-3 Serial Number 3186 Page 1 of 3 REVISED PROPOSED RETYPED TECHNICAL SPECIFICATION PAGES 3/4 3-21 and 3/4 3-22 (TABLE 4.3-2)
(two pages follow)
TABLE 4.3-2 SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED
- 1. INSTRUMENT STRINGS
- a. DELETED DELETED DELETED DELETED DELETED
- b. Containment Pressure - High S E M(2) 1,2,3
- c. Containment Pressure - High-High S E M(2) 1, 2, 3
- d. RCS Pressure - Low S R M 1,2,3
- e. RCS Pressure - Low-Low S R M 1, 2, 3
- f. BWST Level - Low-Low S E M 1, 2, 3
- 2. OUTPUT LOGIC
- a. Incident Level #1: Containment Isolation S E M 1,2,3,4
- b. Incident Level #2: High Pressure Injection and Starting Diesel Generators S E M 1,2,3,4
- c. Incident Level #3: Low Pressure Injection S E M 1,2,3,4
- d. Incident Level #4: Containment CZSpray S E M 1, 2,3, 4 LI e. Incident Level #5: Containment b.Sump Recirculation Permissive S E M 1,2,3,4
- 3. MANUAL ACTUATION
- a. SFAS (Except Containmefit Spray NA ' NA 'M(l) 1, 2,3, 4 w and Emergency Sump
°° Recirculation)
- b. Containment Spray NA NA M(l) 1, 2, 3
TABLE 4.3-2 (Continued)
SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS U CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE VI ra FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED
- 4. SEQUENCE LOGIC CHANNELS
- a. Sequencer S NA M 1,2,3,4
- b. Essential Bus Feeder Breaker Trip, S A(3) M(3) 1,2,3,4 Degraded Voltage Relay (DVR)
- c. Diesel Generator Start, S A(3) M(3) 1,2,3,4 Load Shed on Essential Bus, Loss of Voltage Relay (LVR) to
- 5. INTERLOCK CHANNELS
- a. Decay Heat Isolation Valve S R *$ 1,2,3
- b. Pressurizer Heater S R ** 3 ##
I TABLE NOTATION (1) Manual actuation switches shall be tested at least once per REFUELING INTERVAL. All other circuitry associated with manual safeguards actuation shall receive a CHANNEL FUNCTIONAL TEST at least once per 31 days.
(2) The CHANNEL FUNCTIONAL TEST shall include exercising the transmitter by applying either vacuum or pressure to the appropriate Lan I o side of the transmitter.
so (3) The as-left instrument setting shall be returned tb a setting within the tolerance band of the trip setpoint established to protect the safety
-a limit.
- See Specification 4.5.2.d.1 t3
'0
- l When either Decay Heat Isolation Valve is open.
Docket Number 50-346 License Number NPF-3 Serial Number 3186 Page 1 of 1 COMMITMENT LIST The following list identifies those actions committed to by the Davis-Besse Nuclear Power Station, Unit Number 1, (DBNPS) in this document. Any other actions discussed in the submittal represent intended or planned actions by the DBNPS. They are described only for information and are not regulatory commitments. Please notify Henry L. Hegrat, Supervisor-Licensing (330-315-6944) of any questions regarding this document or associated regulatory commitments.