Tech Spec Change Request 58.Moves Surveillance Requirement for Testing of High Radiation Initiation of Control Room Emergency Vent Sys from Spec 3/4.7.7.1 to Spec 3/4.3.3.1. Tech Spec Pages EnclML19296B038 |
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Crystal River |
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Issue date: |
02/15/1980 |
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From: |
FLORIDA POWER CORP. |
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To: |
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Shared Package |
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ML19296B035 |
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References |
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TAC-46970, NUDOCS 8002190734 |
Download: ML19296B038 (5) |
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Category:TECHNICAL SPECIFICATIONS
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ML20206M0961999-05-0707 May 1999 Proposed Tech Specs,Revising Wording for SR 3.5.2.5 to Be More Consistent with NUREG-1430,Rev 1 & Clarifying Process of Valve Position Verification ML20206H6541999-05-0505 May 1999 Proposed Tech Specs,Proposing Alternate Repair Criteria for Axial Tube End crack-like Indications in Upper & Lower Tubesheets of CR-3 OTSGs ML20204D9211999-03-18018 March 1999 Proposed Tech Specs Re OTSG Tubes Surveillance Program,Tube Repair Roll Process ML20202E6551999-01-27027 January 1999 Proposed Tech Specs Re OTSG Tubes Surveillance Program,Insp Interval Extension ML20196D6761998-11-30030 November 1998 Proposed Tech Specs LCO 3.9.3,allowing Both Doors in Personnel Air Locks & Single Door in Oeh to Be Open During Refueling Operations ML20195K4551998-11-24024 November 1998 Proposed Tech Specs,Installing diesel-driven EFW Pump to Remove Interim ITS & Provide Resolution to EDG Capacity Limitations ML20195K0031998-11-23023 November 1998 Proposed Tech Specs Re LAR Number 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Discussed in FSAR & Improved TS ML20217D2741997-10-0101 October 1997 Proposed Tech Specs Adding Methodology to Monitor first-span Intergranular Attack (Iga) Indications & Disposition Growth During Future B OTSG Eddy Current Exams ML20210T9771997-09-12012 September 1997 Proposed Tech Specs Replacement Pages Re New Improved TS 3.4.11 Re Low Temp Overpressure Protection Sys ML20216F8481997-09-0909 September 1997 Proposed Tech Specs Re Analysis Rev for Makeup Sys Letdown Line Failure Accident as Discussed in FSAR ML20217Q2121997-08-26026 August 1997 Proposed Tech Specs Changing Design Basis of EDG Air Handling Sys ML20217N2501997-08-20020 August 1997 Proposed Improved Tech Specs 5.6.2.10 Re Tube Surveillance ML20210K8921997-08-16016 August 1997 Proposed Tech Specs 3.8.1.3,requesting one-time Outage on Each EDG to Perform Necessary Mod & Maint ML20151L7541997-08-0404 August 1997 Proposed Tech Specs Extending Frequency of EDG Surveillances During Period of Time CR-3 EDGs Are Being Modified ML20196J1431997-07-29029 July 1997 Proposed Tech Specs Adding EDG Kilowatt Indication to post- Accident Monitoring Instrumentation to Support CR-3 Restart Issue of EDG Load Mgt ML20196H0281997-07-18018 July 1997 Proposed Tech Specs Changes Establishing Requirements for Low Temperature Overpressure Protection Sys ML20148K7811997-06-14014 June 1997 Proposed Tech Specs Re Efw,Hpi,Emergency Feedwater Initiation & Control Sys ML20138H8781997-05-0101 May 1997 Proposed Tech Specs Replacing Prescriptive Requirements of 10CFR50,App J,Option a w/performance-based Approach to Leakage Testing Contained in 10CFR50,App J,Option B ML20137X5361997-04-18018 April 1997 Proposed Tech Specs,Providing Revs to CR-3 Improved TS Bases That Update NRC Copies of Improved TS 1999-09-02
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212C1121999-09-16016 September 1999 Criticality Safety Analysis of W Spent Fuel Storage Racks in Pool B of Crystal River Unit 3 ML20212C0961999-09-16016 September 1999 Proposed ITS & Bases Changes Strikeout & Shadowed Text & Revision Bar Format,Increasing Licensed Capacity for Spent Fuel Assembly Storage in SFP & Revising Configuration for Storage of Fresh Fuel ML20211L1011999-09-0202 September 1999 Proposed Tech Specs Re Once Though SG Tube Surveillance Program,Alternate Repair Criteria (ARC) for Axial Tube End Crack (Tec) Indications ML20212C0991999-08-31031 August 1999 Criticality Safety Analysis of Crystal River Unit 3 Pool a for Storage of 5% Enriched Mark B-11 Fuel in Checkerboard Arrangement with Water Holes ML20209D2971999-07-0808 July 1999 Proposed Tech Specs,Changing ITS for CREVS & VFTP & Correcting Typo in ITS Section 5.6.2.12 ML20195B8091999-05-26026 May 1999 Proposed Tech Specs,Revising ITS Bases That Will Update NRC Copies of ITS ML20195B7081999-05-17017 May 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ML20199G5581999-01-12012 January 1999 Rev 4 to AP-404, Loss of Decay Heat Removal ML20199G5691999-01-12012 January 1999 Rev 4 to AP-604, Waterbox Tube Failure ML20198T2411999-01-0606 January 1999 Rev 19 to AR-701, Ssf P Annunciator Response ML20196G6771998-12-0101 December 1998 Rev 17 to Annunciator Response AR-702, Ssf Q Annunciator Response ML20196D6761998-11-30030 November 1998 Proposed Tech Specs LCO 3.9.3,allowing Both Doors in Personnel Air Locks & Single Door in Oeh to Be Open During Refueling Operations ML20196G5851998-11-25025 November 1998 Rev 32 to AR-303, ESC Annunciator Response ML20196G3371998-11-25025 November 1998 Reissued Rev 15 to AR-702, Ssf Q Annunciator Response ML20195K4551998-11-24024 November 1998 Proposed Tech Specs,Installing diesel-driven EFW Pump to Remove Interim ITS & Provide Resolution to EDG Capacity Limitations ML20196F6691998-11-24024 November 1998 Rev 11 to AP-330, Loss of Nuclear Svc Cooling ML20195K0031998-11-23023 November 1998 Proposed Tech Specs 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November 1998 Rev 1 to Crystal River Unit 3 ASME Section Xi,Isi Program Interval 3 & Ten Yr NDE Program ML20195H8761998-11-0505 November 1998 Rev 23 to AR-302, Esb Annunciator Response ML20155F4021998-10-30030 October 1998 Proposed Revised Improved Tech Specs (ITS) Section 5.6.2.19, ITS Section 3.4.11,Bases 3.4.11 & 3.4.3 Re PTLR & LTOP Limits 1999-09-02
[Table view] |
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Technical Specification Change Request No._58 (Appendix A)
Replace pages 3/4 3-23, 3/4 3-24, 3/4 3-25, and 3/4 7-21 with the attached revised pages 3/4 3-23, 3/4 3-24, 3/4 3-25, and 3/4 7-21.
Proposed Change This change will move the surveillance requirement for testing the hign ra-diation initiation of the control room emergency ventilation system from Specification 3/4.7.7.1 to Specification 3/4.3.3.1.
Reason for Proposed Change Specification 4.7.7.1.e.2 presently requires the control room emergency ventilation system to automatically switch into a recirculation mode of op-eration with either an ESFAS test signal or a high radiation test signal.
In ordec to comply with the high radiation portion of this specification, RM-A5 must be operable. There is no redundancy built into RM-AS. There-fore, each time RM-A5 f ails both ventilation systems should technically be declared inoperable, since we cannot meet the surveillance requirements unich demonst' rate system operability. This will envoke the requirements of Specification 3.0.3 which dictates a one-hour shutdown.
This surveillance requirement is poorly structured to fit the requirements of system operability. Failure of the systems' ability to automatically shift to recirculation upon a high radiation test signal does not conpromise the system operability, especially if the system is manually placed in the recirculation mode when the automatic function is deactivated. The system will still circulate, filter, and cool the air in the control room.
What we are really addressing in this specification is the function of a process radiation monitor. Therefore, the surveillance requirements of RM-A5 would be more appropriately located under Specification 3.3.3.1, Radiation Monitoring Instrumentation. By this action, the interlock functions of RM-A5 will be properly addressed and tested, and the appropriate action taken upon a f ailure. These changes are consistent with the Babcock and Wilcox Standard Technical Specifications, Rev. 3, July 1979 (page 3/4 3-26, 3-27, and 7-16) as well.
Safety Analysis of Proposed Change There are no additional safety concerns involved with these changes. The control complex emergency ventilation system will be adec,uately tested so that it will perform its intended function. Additionally, the operability of RM-A5 will be tested such that it will provide the interlock function to the control complex ventilation system when required. Therefore, both systems will function as designed and no unreviewed safety question is involved.
TSCRh58(DN-93) 800219073%
TABLE 3.3-6 9
g RADIAT10ti MUNITORIf4G liiSTRUMElil AT10t4 5
r- MINIMUM
$ CHAtitlE LS APPLICABLE ALARM / TRIP MEASURLMENT INSTRUMEliT SETPOINT ACTION g OPERABLE MODES RANGE
' l. AREA MONITORS E
q a. Fuel Storage Pool Area m i. Criticality Monitor 1 $15 mr/hr 10 104 mr/hr 14
- 2. PROCESS M0lilTORS
- a. Fuel Storage Pool Area
- i. Gaseous Activity -
w Ventilation 3 System Isolation 1
- 12 x background 101 - 106cpm 16
[ b. Reactor Building w i. Gaseous Activity -
a) Purge Exhaust Duct isolation 1 6 101 - 103cpm 17 b) RCS Leakage Detection 1 1, 2, 3 a 4 flot Applicable 101 - 100cpm 15 ti. Iodine Activity -
RCS Leakage Detection 1 1, 2, 3 a 4 Not Applicable 101 - 100 cpm 15
- c. Control Room
- i. Iodine Activity -
Ventilation System Isolation /
Recirculation 1 All Modes 12 x background 101 - 106cpm 18
- With fuel in the storage pool or building
- With irradiated fuel in the storage pool
- Determined by requirements of Appendix "B", Tech. Specs., Section 2.4.2 - Crystal River 3 Operating License No. DPR-72.
TABLE 3.3-6 (Continued)
TABLE NOTATION ACTION 14 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 15 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the action requirements of Specification 3.4.6.1.
ACTI0tl 16 - With the number of channels OPERABLE less thar, required by the Minimum Channels OPERABLE requirement, comply with the ACTION requir ements of Specification 3.9.12.
ACTION 17 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTI0fi requirements of Specification 3.9.9.
ACTION 18 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the control roan emergency ventilation system in the recirculation mode of operation.
CRYSTAL RIVER - UNIT 3 3/4 3-24
~.
TABLE 4.3-3 9
iy, RADIATIOfl MONITORING INSTRUMEf4 TAT 10N SURVEILLANCE REQUIREMEf4TS C
r-CHANilEl MUDLS IN WillCli
$ CitANNEL CilANNEL FUfiCTIONAL SURVEILLANCE g If4STRUMENT CitECK CALIBRATION TEST REQUIRED
- l. AREA MONITORS E *
- 1 a. Fuel Storage Pool Area w i. Criticality Monitor S R M
- 2. PROCESS MONITORS
- a. Fuel Storage Pool Area
- i. Gaseous Activity -
w Ventilation **
2 System Isolation S R M w
a b. Reactor Building ,
a) Purge Exhaust .
Duct Isolation S Q M 6 b) RCS Leakage Detection S R M 1, 2, 3, a 4 ii. Iodi ne Activi ty -
RCS Leakage Detection S R M 1, 2, 3, a 4
- c. Control Room
- i. Iodine Activity -
Ventilation System Isolation /
Recirculation S R M All Modes
- With fuel in the storage pool or building
- With irradiated fuel in the storage pool
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- 1. Verifying that, with the system operatino at a flow rate of 43,500 cfm +10%, and exhausting through the HEPA filters and charcoal adsorbers, the total bypass flow of the system to the facility vent, including leakage through the system di-verting valves, is 11% when the system is tested by admit-ting cold DOP at the system intake.
- 2. Verifying that the ventilation system satisfies the in-place testing acceptance criteria, and uses the test procedures of Regulatory Positions C.S.a, C.5.c*, and C.S.d* of Regulatory Guide 1.52, Revision 1, July 1976, and the system flow rate is 43,500 cfm 1.10%.
- 3. Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample, obtained in ac-cordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 1, July 1976, meets the laboratory testing criteria of Regulatory Position C.6.1 of Regulatory Guide 1.52, Revision 1, July 1976.
- 4. Verifying a system flow rate of 43,500 cfm 110% during sys-tem operation, when tested in accordance L;th ANSI N10-1975.
- d. After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal absorber operation, by verify-ing, within 31 days after removal, that a laboratory analysis of a representative carbon sample, obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 1, July 1976, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 1, July 1976.
- e. At least once per 18 months, by:
- 1. Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is <6 inches Water Gauge while operating the system at a flow rate of 43,500 cfm 1.10%.
- 2. Verifying that on a containment isolation test signal, the l system automatically switches into a recirculation mode of operation with flow through the HEPA filters and charcoal adsorber banks.
CRYSTAL RIVER - UNIT 3 3/4 7-21