ML20195C594
| ML20195C594 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/03/1999 |
| From: | Peterson S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20195C601 | List: |
| References | |
| NUDOCS 9906080229 | |
| Download: ML20195C594 (10) | |
Text
{{#Wiki_filter:I' gn UO </ 'o UNITED STATES 8" "g NUCLEAR REGULATORY COMMISSION n WASHINGTON, D. C. 20555 s.,...../ FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE i CITY OF KISSIMMEE CITY OF LEESBURG CITY OF NEW SMYRNA BEACH AND UTILITIES COMMISSION. CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES COMMISSION AND CITY OF ORLANDO SEMINOLE ELECTRIC COOPERATIVE. INC. CITY OF TALLAHASSEE DOCKET NO. 50-302 l CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT l i AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.177 License No. DPR-72 1. The Nuclear Regulatory Commission (the Commission) has found that: 1 A. The application for amendment by Florida Power Corporation, et al. (the licensees), dated August 31,1998, comp!!ss with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility w;11 cperate in conformity with the application, 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 Commission's reQulations; i D. The issuance of this amendment will not be inimical to the common defense and securih or to the health and safety of the public; and i l 9906090229 990603 PDR ADOCK 05000302 P PDR 1 J
f o-2 l l E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. 2. Accordingly, the license is amended by changes to the Technical Specifications as l Indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-72 is hereby amended to read as follows: Technical Specifications - The Technical Specifications contained in Appendices A and B, as revised through Amendment No.177. are hereby incorporated in the license. Florida Power Corporation shall operate the facility in accordance with the Technical Specifications. 3. This license amendment is effective as of its date of issuance and shall be implemented prior to commencing cycle 12 operation. FOR THE NUCLEAR REGULATORY COMMISSION ) M% $. >- Sheri R. Peterson, Chief, Section 2 Project Directorate ll Division of Project Licensing Management Office of Nuclear Reactor Regulation l-Date of issuance: June 3,199 i
r e i ATTACHMENT TO LICENSE AMENDMENT NO.177 TO FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO. 50-302 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contains verticallines indicating the area of change. Remove Paoe insert Paae 3.3-40 3.3-40 .3.3-41 3.3-41 B 3.3-125B B 3.3-1258 B 3.3-138C B 3.3-138D B 3.3-143 8 3.3-143-B 3.3-144 8 3.3-144
8. y PAM Instrumentation ~, 3.3.17 ' SURVEILLANCE REQUIREMENTS
NOTE-------------------------------------
These SRs apply to each PAM instrumentation Function in Table 3.3.17-1. I SURVEILLANCE FREQUENCY SR 3.3.17.1
NOTE--------------------
Not required for Function 4. Perform CHANNEL' CHECK for each required-31 days instrumentation channel that is normally energized. .-----NOTE----- SR 3.3.17.2
NOTE----------
The Frequency Neutron detectors are excluded from CHANNEL for Function 12 CALIBRATION. is 18 months.
NOTE--------------------
Not required for Functions 23 and 25. Perform CHANNEL CALIBRATION. 24 months 'SR 3.3.17.3
NOTE--------------------
Only required for Functions 23 and 25. Perform CHANNEL FUNCTIONAL TEST. 24 months Crystal River Unit 3 3.3-40 Amendment No. 177 1
PAM Instrumentation 3.3.17 Table 3.3.17-1 (page 1 of 1) Post Accident Monitoring Instrumentation CONDITIONS REFERENCED FROM FUNCTION REQUIRED CHAwELS REQUIRED ACTION D.1
- 1. Wide Range Aeutron Fluu 2
l 2. RCS Hot Leg Temperature 2 E 3. RC5 Pressure (Wide Range) 2 I 4 Reactor Coolant Inventory 2 F 5. Borated Water Storage Tank Level 2 E 6. High Pressure Injection Flow 2 per injection line E 7. Containment Sump Water Level (Flood Level) 2 0 8. Containment Pressure (Expected Post-Accident E 2 Range) 9. Containment Pressure (Wide R.nge) 2 E
- 10. Containment Isolation Valve Position 2 per penetration (a)(b)
E
- 31. Containment Area Radiation (High Range) 2 F
- 12. Containment Hydrogen Concentration 2
E
- 13. Pressurizer Level 2
E
- 14. Steam Generator Water Level (Statt.up Range) 2 per OTSG I
- 15. Steam Generator Water Level (Operating Range) 2 per OTSC E
- 16. Steam Generator Pressure 2 per 015G E
- 17. Emergency Feedwater Tank Level 2
E 184. Core Exit Temperature (Thermocouple) 2 thermocouples per core E Quadrant 18b. Core Exit Temperature (Recorder) 2 E
- 19. Emergency feedwater Flow 2 per OT5G E
- 20. Low Pressure injection Flow 2
E
- 21. Degrees of Subcooling 2
E
- 22. Emergency Diesel Generator kW Indication 2(C)
I
- 23. LPI Pump Run Status 2
E
- 24. DHV-42 and DHV-43 Open Position 2
E
- 25. HPI Pump Run Status 2
E
- 26. RCS Pressure (Low Range) 2 E
l (a) Only one position indication is required for penetrations with one Control Room indicator. (b) Not required for isolation valves whose associated penetration is isolated by at least one closed and deactivated automatic valve, closed manual valve. blind flange, or check valve with flow through the valve secured. (c) One indicator per EDG, i Crystal River Unit 3 3.3-41 Amendment No. 177
PAM Instrumentation B 3.3.17 BASES FUNCTION CHANNEL A CHANNEL B
- 15. Steam Generator Water OTSG A: SP-17 LI1 or OTSG A: SP-18-L11 Level (Operating Range)
SP-17-L I R OTSG B: SP-22 L11 OTSG B: SP-21-Ll1 or SP-21-LIR
- 16. Steam Generator OTSG A: MS-106-P11 or OTSG A: MS-107-PI1 or Pressure MS-106 PIR, MS-107 PIR OTSG 8: MS-110-P11 or OTSG B: MS-111-P11 or MS 110 PIR MS-111 PIR
- 17. Emergency Feedwater EF-98-LI1 EF-99-L11 Tank Level
- 18. Core Exit Temperature Three detectors from each of the following groups; (Backup)
Quadrant WX: IM-2G TE /IM-5G-TE /IM-6C-TE /lM 7F-TE Quadrant XY: IM-9E-TE /IM-10C-TE/IM 11G-TE/IM-13G-TE Quadrant YZ: IM-9H-TE /IM-10M TE/IM-100-TE/IM 13L TE Quadrant zu: IM 3L-TE /IM-4N-TE /IM 6L-TE /IM 60 TE and Recorders RC 171 TR, RC 172-TR, RC-173-TR
- 19. Emergency Feedwater OTSG A: EF 25-F11 DTSG A: EF-26-Fl1 Flow OTSG B: EF 23-F11 OTSG B: EF-24-Ff1
- 20. Low Pressure Injection DHV-110 Hand / Auto station f'ow DHV-111 Hand / Auto station flow Flow indication (DH-1-FK3 1) indication (DH-1-FK4-1)
- 21. Degrees of Subcooling RC-4-114 and RC-4-T!5 and SPDS "A" or SPDS "BH
- 22. Emergency Olesel EGDG-1A Wattmeter SSF-AH Main EGDG-1B Wattmeter SSF-AX Main Generator kW Indication control board indicator control board indicator
- 23. LPI Pump Run Status ESFA-LX3 (Red Light) or ESFB LX3 (Red Light) or ESFA-HU (ES Light Matrix "A")
ESFB-HU (ES Light Matrx "B")
- 24. DHV-42 and DHV-43 ESFA-KN3 (Red Light)
ESFB KN3 (Red Light) Open Position
- 25. HPI Pump Run Status HPI Pump 1A:
HPI Ptap 1C: ESFA-MF7 (Red Light) or ESFB-MF7 (Red Light) or ESFA AH (ES Light Matrix "A") ESFB-AH (ES Light Matrix "B") OR OR HPI P g 18: HPI Pump 1B; ESFA-MN7 (Red Light) or ESFB MV7 (Red Light) or ESFA AJ (ES Light Matrix HA") ESFB-AJ (ES Light Matrix "B")
- 26. RCS Pressure RC-147 PI1 RC 148-PI1 (Low Range)
NOTES: For Function 18, OPERABILITY of only two detectors (and associated recorder) for any group constitutes entry into Condition A of LCO 3.3.17. Any group with only one OPERABLE detector / recorder combination constitutes entry into Condition C of LCO 3.3.17. Separate condition entry is allowed for each group. For Function 21, with both channels of SPDS inoperable, LCO Condition C and its associated Required Action are applicable. For Function 25, OPERABILITY of indication is required only for the one ES selected HPI pump in each channel. (continued) Crystal River Unit 3 8 3.3-125B Amendment No. 177 I
F 1 ( PAM Instrumentation B 3.3.17 BASES LC0 23. LPI Pumo Run Status (continued) LPI Pump Run Status is used by the operator during the ECCS Pump Suction Transfer to initiate the opening of DHV-Il and DHV-12, the " Piggyback" valves. LPI Pump Run Status is a Type A variable because the opening of these valves to establish a suction source is a planned manual action and is necessary to maintain HPI in LOCAs where the RCS pressure has not decreased to the )oint that LPI will provide injection of coolant into tie Reactor Coolant System and when single failures occur which result in only one train of LPI being available. 24. DHV-42 and DHV-43 Open Position DHV-42 and DHV-43 Open Position, the suction valves from the RB sump to the LPI pumps, are used by the operator during the ECCS Pump Suction Transfer to initiate the closing of DHV-34 and DHV-35, the suction valves from the BWST to the LPI pumps. DHV-42 and DHV-43 Open Position are Type A variables because the closing of DHV-34 and DHV-35 to manually isolate the BWST from the LPI and BS suction is necessary to prevent vortexing and consequential damage to the LPI and BS pumps, which are required for maintaining core and containment cooling. 25. HPI Pumo Run Status HPI Pump Run Status is used by the operator in determining the total HPI flow per pump. If the total flow decreases below the minimum pump flow limits, then a manual action is taken to open the recirculation valves in order to avoid low flow ~ operation which could damage the pump and render it inoperable while it is being used to mitigate a design basis accident. HPI Pump Run Status is a Type A variable because there are some SBLOCAs that would result in HPI flows of this small a magnitude. Since these actions are necessary to protect equipment that is necessary to mitigate the accident, these are Type A variables. (continued) Crystal River Unit 3 B 3.3-138C Amendment No. 177 i l.
PAM Instrumentation B 3.3.17 BASES LC0 26. RCS Pressure (Low Ranael-(continued)- RCS pressure is measured by pressure transmitters with
- a. span of 0-600 psig. Redundant monitoring capability is provided by two trains of instrumentation.
The control room indications are the primary indications used by the operator during an accident. Therefore, the LCO deals specifically with this portion of the: instrument string. RCS Pressure (Low Range) is classified as a Type B Category 1 variable because none of the acticns taken by the operator based on RCS pressure variables qualifies it as a Type A variable. It is included in Table 3.3.17-1 as it is a Category 1 variable and relied on by the operators to maintain RCS pressure for several contingency actions included in the E0Ps. Those actions are:
- 1) determination that an ES actuation of the LPI pumps should have occurred, 2) selecting Low Temperature Overpressure Protection (LTOP),3 Heat Remov)al, 4) ensure adequate RCP NPSH at low RCSopeni pressure, and 5) ensure NDT limits have not been exceeded.
(continued) Crystal _ River Unit 3 8 3.3-138D Amendment No. 177 j
PAM Instrumentation B 3.3.17 BASES SURVEILLANCE SR 3.3.17.1 (continued) REQUIREMENTS A note to the Surveillance excludes the performance of a CHANNEL CHECK on Function 4. FPC requested, and was granted, exception from performing a CHANNEL CHECK on this instrumentation as part of Amendment 124, dated October 17, 1989. The basis for not performing this SR is based on the design of the system. The system utilizes differential hot leg an(d the reactor vessel when the RCPs are tripped. pressure dp) measurements across vertical elevations of the Performance of the SR with the RCPs in operation provides no meaningful information,d.such that a CHANNEL CHECK of this Function is not require SR 3.3.17.2 CHANNEL CALIBRATION is a complete check of the instrument channel, including the sensor, to verify the channel responds to the measured parameter (s) within the necessary rangr. and accuracy. For tlm Containment Area Radiation instrumentation, a CHAWN R CALIBRATION consists of an electronic calibration of the channel, not including the detector, for range decades above 10 R/hr. The calibration also provides a one point check of the detector below 10 R/hr using a gamma test source (Reference NUREG 0737, Table II.F.1-3). The 24 month Frequency is based on the results of a review of instrument drift data conducted in accordance with NRC Generic Letter 91-04. The Frequency for the hydrogen monitors is 18 months based on operating experience and was originally selected to be consistent with the typical industry fuel cycle. A Note clarifies that the neutron detectors are not required to be tested as part of the CHANNEL CALIBRATION. Adjustment of the detectors is unnecessary because they are passive devices and operating experience has shown them to exhibit minimal drift. Furthermore, there is no adjustment that can be made to the detectors. A Note to the Surveillance excludes the performance of a CHANNEL CALIBRATION on Functions 23 and 25. FPC requested, and was granted, exception from performing a CHANNEL CALIBRATION on this instrumentation as part of Amendment (TBD, dated indic)ations is[TBD]. Since no adjustment of these on-off possible, performance of the SR provides no meaningful information such that a CHANNEL CALIBRATION of this Function is not required. Instead these indications are sub'iected to a CHANNEL FUNCTIONAL T$ST as described in l SR 3.3.17.3. (continued) l Crystal River Unit 3 B 3.3-143 Amendment No. 177 i
c:. PAM instrumentation B 3.3.17 ' BASES:
- ((
t ISURVEILLANUE SR 3.3.17.3 REQUIREMENTS -(continued) ' CHANNEL FUNCTIONALJTEST is, for switch contacts, the injection of,a simulated or actual signal -into the channel -as close to the sensor as practicable to verify OPERABILITY, including required alarm and trip functions. For the LPI Pump.Run Status, and the HPI-Pump Run' Status, the CHANNEL FUNCTIONAL TEST verifies the red indicating ' lights on the main control' board and the:ES Light Matrix . indicators during testing of the pumps already required by other~ surveillance' requirements. The 24 month frequency is based on providing consistency between this surveillance testing and the other surveillance requirements for. verifying operability of these specific pumps.. REFERENCES. 1. FSAR, Table 7-12. 2. Regulatory Guide 1.97, Revision 3.
- 3.. 'NUREG-0737, 1979.
4.- 32-1177256-00, " Technical-Basis for Reactor Vessel
- Level Indication System.(RVLIS) Action Statement,"
April 10, 1990. 1 = Crystal River Unit 3 B 3.3-144 Amendment No. 177 r.!}}