ML040420424
| ML040420424 | |
| Person / Time | |
|---|---|
| Site: | Monticello, Palisades, Kewaunee, Point Beach, Prairie Island, Duane Arnold  |
| Issue date: | 01/30/2004 |
| From: | Weinkam E Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML040420424 (74) | |
Text
N Commtted to Nuclear Ecep Operated by Nuclear Management Company, LLC January 30, 2004 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Duane Arnold Energy Center Docket 50-331 License No. DPR-49 Kewaunee Nuclear Power Plant Docket 50-305 License No. DPR-43 Palisades Nuclear Plant Docket 50-255 License No. DPR-20 Monticello Nuclear Generating Plant Docket 50-263 License No. DPR-22 Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 License Nos. DPR-24 and DPR-27 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 License Nos. DPR-42 and DPR-60
Subject:
Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process Pursuant to 10 CFR 50.90, Nuclear Management Company, LLC (NMC) hereby requests an amendment to the Technical Specifications (TS) for the above identified facilities.
The proposed amendment will delete the TS requirements related to hydrogen recombiners, and hydrogen/oxygen' monitors. The proposed TS changes support implementation of the revisions to 10 CFR 50.44, Standards for Combustible Gas Control System in Light-Water-Cooled-Power Reactors," that became effective on October 16, 2003. The changes are consistent with Revision 1 of NRC-approved Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-447, "Elimination of Hydrogen Recombiners and Change to Hydrogen and Oxygen Monitors." The availability of this TS improvement was announced in the Federal Register on September 25, 2003, as part of the consolidated line item improvement process (CLIIP).
X References to Oxygen Monitors apply only to Duane Amold Energy Center and Monticello Nuclear Generating Plant.
700 First Street
- Hudson, Wisconsin 54016 Telephone: 715.377.3300 7/
A00
USNRC Page 2 provides a description of the proposed change, the requested confirmation of applicability, and plant-specific verifications and commitments. Enclosure 2 provides site-specific clarifications to the TSTF-447 in conjunction with specifying the location of various changes to each facility's Technical Specifications. Enclosure 3 provides the existing TS pages marked-up to show the proposed change. Enclosure 4 provides revised, clean TS pages. Implementation of TSTF-447 also involves various changes to the TS Bases. The TS Bases changes will be implemented in accordance with each licensee's Technical Specifications (TS) Bases Control Program. In addition, as part of implementation of this change, each site will evaluate previous regulatory commitments, in accordance with approved guidance (SECY-00-0045, Acceptance of NEI 99-04, Guidelines for Managing NRC Commitments"). The Staff will be notified of any such changes under separate cover, as necessary.
NMC requests approval of the proposed License Amendment by June 2004, with the amendment being implemented within 120 days after issuance of the amendment.
The TS pages submitted with this letter may be impacted by TS page changes in other license amendment requests. The marked up TS pages attached to this submittal do not contain incorporation of other proposed changes but reflect TS pages in their current approved state.
In accordance with 10 CFR 50.91, a copy of this application, with enclosures, is being provided to each facility's designated State Official.
Summary of Commitments This letter makes the following new commitments:
1 ) NMC has verified that a hydrogen monitoring system capable of diagnosing beyond design-basis accidents is installed at each facility and is making a regulatory commitment to maintain that capability. The hydrogen monitors will be included in the specified document or program identified in Enclosure 1, Table 1.
This regulatory commitment will be implemented by the implementation date.
- 2) NMC has verified that an oxygen monitoring system capable of verifying the status of the inerted containment is installed at Duane Arnold Energy Center and Monticello Nuclear Generating Plant and is making a regulatory commitment to maintain that capability. The oxygen monitors will be included in the specified document or program identified in Enclosure 1, Table 1. This regulatory commitment will be implemented by the implementation date.
If you should have any questions regarding this submittal, please contact John Fields, Senior Regulatory Affairs Engineer (763-295-1663).
USNRC Page 3 I declare under penalty of perjury that the foregoing is true and correct.
Executed on SI) a+,
EdardJ.
inkam Director of e latory Services Nuclear Management Company, LLC Enclosures (14) cc:
Regional Administrator, USNRC, Region IlIl Project Managers, Office of Nuclear Reactor Regulation (Duane Arnold Energy Center, Kewaunee Nuclear Power Plant, Monticello Nuclear Generating Plant, Palisades Nuclear Plant, Point Beach Nuclear Plant, Prairie Island Nuclear Generating Plant)
NRC Resident Inspectors (Duane Arnold Energy Center, Kewaunee Nuclear Power Plant, Monticello Nuclear Generating Plant, Palisades Nuclear Plant, Point Beach Nuclear Plant, Prairie Island Nuclear Generating Plant)
State Consultation (Minnesota Department of Commerce, Lou Brandon - Chief -
NFU/HWRPSIWHMD, Ms. Ave M Bie - Public Service Commission of WI, State of Iowa - D. McGhee
ENCLOSURE 1 Description and Assessment
1.0 INTRODUCTION
The proposed License amendment deletes Technical Specification (TS) requirements for Hydrogen Recombiners and references to the hydrogen and oxygen' monitors in TS. These changes are numbered according to each facility's TS as identified in Table 1. The proposed TS changes support implementation of the revisions to 10 CFR 50.44, "Standards for Combustible Gas Control System in Light-Water-Cooled Power Reactors," that became effective on October 16, 2003. The revision of the requirements for the hydrogen recombiner and hydrogen/oxygen monitors resulted in numbering and formatting changes to other TS, which were otherwise unaffected by this proposed amendment.
The changes are consistent with Revision 1 of NRC-approved Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-447, "Elimination of Hydrogen Recombiners and Change to Hydrogen and Oxygen Monitors." The availability of this TS improvement was announced in the Federal Register on September 25, 2003, as part of the consolidated line item improvement process (CLIIP).
2.0 DESCRIPTION
OF PROPOSED AMENDMENT Consistent with the NRC-approved Revision 1 of TSTF-447, the proposed TS changes include:2 Inoperable Hydrogen Monitors Deleted Containment Hydrogen Concentration Deleted Drywell H2 & 02 Analyzer Containment H2 & 02 Analyzer Hydrogen Recombiners Deleted Other TS changes included in this application are limited to renumbering and formatting changes that resulted directly from the deletion of the above requirements related to hydrogen recombiners and hydrogen and oxygen monitors.
As described in NRC-approved Revision 1 of TSTF-447, the changes to TS requirements and associated renumbering of other TSs results in changes to various TS Bases sections. The TS Bases changes will be implemented in accordance with each facility's TS Bases Control Program.
References to Oxygen Monitors apply only to Duane Arnold Energy Center and Monticello Nuclear Generating Plant.
2 Each facility's unique TS Section Identification number is provided in Table I and in the applicable (X).
Page 1 of 4
3.0 BACKGROUND
The background for this application is adequately addressed by the NRC Notice of Availability published on September 25, 2003 (68 FR 55416), TSTF-447, the documentation associated with the 10 CFR 50.44 rulemaking, and other related documents.
4.0 REGULATORY REQUIREMENTS AND GUIDANCE The applicable regulatory requirements and guidance associated with this application are adequately addressed by the NRC Notice of Availability published on September 25, 2003 (68 FR 55416), TSTF-447, the documentation associated with the 10 CFR 50.44 rulemaking, and other related documents.
5.0 TECHNICAL ANALYSIS
Nuclear Management Company, LLC (NMC) has reviewed the safety evaluation (SE) published on September 25, 2003 (68 FR 55416) as part of the CLIIP Notice of Availability. This verification included a review of the NRC staffs SE, as well as the supporting information provided to support TSTF-447. NMC has concluded that the justifications presented in the TSTF proposal and the SE prepared by the NRC staff are applicable to each of the facilities identified in this amendment request and justify this amendment for the incorporation of the changes to each facility's TS.
6.0 REGULATORY ANALYSIS
A description of this proposed change and its relationship to applicable regulatory requirements and guidance was provided in the NRC Notice of Availability published on September 25, 2003 (68 FR 55416), TSTF-447, the documentation associated with the 10 CFR 50.44 rulemaking, and other related documents.
6.1 Verification and Commitments As discussed in the model SE published in the Federal Register on September 25, 2003 (68 FR 55416) for this TS improvement, NMC is making the following verifications and regulatory commitments:
- 1.
NMC has verified that a hydrogen monitoring system capable of diagnosing beyond design-basis accidents is installed at each facility and is making a regulatory commitment to maintain that capability. The hydrogen monitors will be included in the specified document or program identified in Table 1. This regulatory commitment will be implemented by the implementation date.
- 2.
Kewaunee Nuclear Power Plant, Palisades Nuclear Plant, Point Beach Nuclear Plant Units 1 and 2, and Prairie Island Nuclear Generating Plant Units 1 and 2 do not have an inerted containment.
Page 2 of 4
Duane Arnold Energy Center and Monticello Nuclear Generating Plant have an inerted containment. NMC has verified that an oxygen monitoring system capable of verifying the status of the inerted containment is installed at Duane Arnold Energy Center and Monticello Nuclear Generating Plant and is making a regulatory commitment to maintain that capability. The oxygen monitors will be included in the specified document or program identified in Table 1.
This regulatory commitment will be implemented by the implementation date.
7.0 NO SIGNIFICANT HAZARDS CONSIDERATION NMC has reviewed the proposed no significant hazards consideration determination published on September 25, 2003 (68 FR 55416) as part of the CLIIP. NMC has concluded that the proposed determination presented in the notice is applicable to each of the facilities identified in this amendment request and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91(a).
8.0 ENVIRONMENTAL EVALUATION NMC has reviewed the environmental evaluation included in the model SE published on September 25, 2003 (68 FR 55416) as part of the CLIIP. NMC has concluded that the staffs findings presented in that evaluation are applicable to each of the facilities identified in this amendment request and the evaluation is hereby incorporated by reference for this application.
9.0 PRECEDENT This application is being made in accordance with the CLIIP. NMC is not proposing variations or deviations from the TS changes described in TSTF-447 or the NRC staffs model SE published on September 25, 2003 (68 FR 55416). However, the unique characteristics of each facility's TS in relationship to TSTF-447 are identified and clarified in Enclosure 2. The differences between each facility's TS and TSTF-447 do not affect the no significant hazards consideration determination and environmental evaluation included in the model SE published on September 25, 2003 (68 FR 55416) as part of the CLIIP.
10.0 REFERENCES
Federal Register Notice: Notice of Availability of Model Application Concerning Technical Specification Improvement To Eliminate Hydrogen Recombiner Requirement, and Relax the Hydrogen and Oxygen Monitor Requirements for Light Water Reactors Using the Consolidated Line Item Improvement Process, published September 25, 2003 (68 FR 55416).
Page 3 of 4
Table I - Site Specific Information Specified Specified Revised TS document or document or Section program for program for Identification relocation of relocation of Facility
- numbers Hydrogen Monitors Oxygen Monitors Duane Arnold 3.3.3.1 Technical Technical Energy Center Requirements Requirements
__nergy____Center Manual Manual (a)
Table 3.5-6 Technical N/A Power Plant Table 4.1-1 Requirements Manual Monticello Nuclear 3.7. E/4.7.E Commitment Commitment Generating Plant Table 3.14.1/4.14.1 Tracking Program Tracking Program (a)
Palisades Nuclear 3.3.7 Commitment N/A Plant Table 3.3.7-1 Management 3.6.7 Program Point Beach 3.3.3 Technical N/A Nuclear Plant Table 3.3.3-1 Requirements 5.6.6 m anual Prairie Island 3.3.3 Technical N/A Nuclear Generating Table 3.3.3-1 Requirements Plant
~3.6.7 Manual Plant
~~5.6.8
- Site-specific clarifications from TSTF-447,.
Rev. 1 are included and explained in (a) Only the post-accident monitoring function will meet Regulatory Guide 1.97 (RG 1.97) and will be included in the Technical Requirements Manual or Commitment Tracking Program. Other, non-RG 1.97 instruments may be used to verify an inerted containment during normal power operations.
Page 4 of 4
ENCLOSURE 2 SITE SPECIFIC CLARIFICATIONS FROM TSTF-447 The purpose of this enclosure is to provide site-specific clarifications to the TSTF-447 in conjunction with specifying the location of various changes to each facility's Technical Specifications. This enclosure augments discussions contained in Enclosure 1, Section 9.0 and Table 1.
Duane Arnold Energy Center Duane Arnold Energy Center (DAEC) is not proposing any variations or deviations from the model Technical Specification (TS) changes for TSTF-447 Revision 1. However, due to minor differences between DAEC TS and the model TS in NUREG-1433, uStandard Technical Specifications, General Electric Plants BWRI4," Revision 2 in several cases small variances from the TSTF mark-up changes are necessary. These clarifications are discussed below and do not affect the adoption or application of TSTF-447, Revision 1.
- 1.
In the TSTF mark-ups, STS 3.3.3.1, PAM Instrumentation, is modified by deleting a Note to Condition C, eliminating Condition D and re-numbering the following Conditions. DAEC TS do not have the Note in Condition C and do not include Condition D in the STS. Thus, these changes are not needed to adopt the TSTF.
- 2.
In the TSTF mark-ups, STS Table 3.3.3.1-1, Post Accident Monitoring Instrumentation, deletes line items 10 and 11 for the Drywell and Containment H2 and 02 Analyzers, respectively. In DAEC Table 3.3.3.1-1, the equivalent line items are Items 7a and b and the same change is being made.
- 3.
In the TSTF mark-ups, STS 3.6.3.1, Primary Containment Hydrogen Recombiners is deleted and the subsequent LCOs are re-numbered accordingly. DAEC TS do not have an equivalent section, so these changes are not needed in the DAEC TS to adopt the TSTF.
- 4.
In the TSTF mark-ups, STS 5.6.7, Post Accident Monitoring Report, is modified based upon the changes described in Item 1 above. Because the DAEC TS do not require the Conditions in LCO 3.3.3.1 to be re-numbered, the DAEC TS do not require this change.
Page 1 of 6
Kewaunee Nuclear Power Plant Kewaunee Nuclear Power Plant (KNPP) Technical Specifications (TS) have not been modified to the Improved Standard Technical Specifications included in NUREG-1431, "Standard Technical Specifications, Westinghouse Plants," Revision 2. Therefore, the following clarifications were made to accommodate the TSTF-447, Revision 1. These clarifications are discussed below and do not affect the adoption or application of TSTF-447, Revision 1.
- 1.
In the TSTF mark-ups, STS Table 3.3.3.1-1, Post Accident Monitoring Instrumentation, deletes line item 11 for Hydrogen Monitors. KNPP TS refer to Hydrogen Monitors in TS Table 3.5-6, Item 7 as "Containment Hydrogen Monitor." This line item is being deleted as an equivalent change to the TSTF.
- 2.
TS Table 3.5-6, Item 7, Containment Hydrogen Monitor, has an associated note (3), which states, "With the number of OPERABLE accident monitoring instrumentation channels less than the required total number of channels shown, either restore the inoperable channels to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />."
Since this note is only applicable to TS Table 3.5-6, Item 7, which is being deleted from the KNPP TS, the note is no longer required and may also be deleted. The proposed deletion is consistent with TSTF-447.
- 3.
KNPP Table TS 4.1-1 MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS," Item 38 is proposed for deletion.
Since the requirements for hydrogen monitors are being deleted from the KNPP TS, the supporting checks, calibrations, and tests for the hydrogen monitors is no longer required and may also be deleted. The proposed deletion is consistent with TSTF-447.
- 4.
In the TSTF mark-ups, STS 3.6.8, "Hydrogen Recombiners", is deleted.
Because the KNPP TS do not contain similar requirements, the KNPP TS do not require this change. Based on the revisions to 10 CFR 50.44 that became effective on October 16, 2003, KNPP will no longer require dedicated penetrations into containment for combustible gas control nor require the hydrogen recombiners to be available.
Page 2 of 6
Monticello Nuclear Generating Plant Monticello Nuclear Generating Plant (MNGP) Technical Specifications (TS) have not been modified to the Improved Standard Technical Specifications included in NUREG-1433, "Standard Technical Specifications, General Electric Plants, BWRI4,"
Revision 2. Therefore, the following clarifications were made to accommodate the TSTF-447, Revision 1. These clarifications are discussed below and do not affect the adoption or application of TSTF-447, Revision 1.
- 1.
MNGP TS Table of Contents indicate that "Combustible Gas Control System" is identified as subsection 3.7.E14.7.E. This Table of Contents entry will be deleted.The TSTF does not include changes to the Table of Contents, but these changes are administrative in nature and are in keeping with the intent of TSTF-447, Revision 1.
- 2.
In the TSTF mark-ups, STS 3.6.3.1, Primary Containment Hydrogen Recombiners is deleted and the subsequent LCOs are re-numbered accordingly. MNGP TS refer to the identical equipment as Combustible Gas Control System." Therefore, the equivalent changes remove MNGP TS section 3.7.E14.7.E.
- 3.
In the TSTF mark-ups, STS Table 3.3.3.1-1, Post Accident Monitoring Instrumentation, deletes line items 10 and 11 for the Drywell and Containment H2 and 02 Analyzers, respectively. MNGP TS refer to the identical equipment in TS Table 3.14.1/4.14.1 as Drywell and Suppression Pool Hydrogen and Oxygen Monitor." This line item is being deleted as an equivalent change to the TSTF.
- 4.
In the TSTF mark-ups, STS 5.6.7, Post Accident Monitoring Report, is modified based upon the changes described in Item 3 above. Because the MNGP TS do not contain similar requirements, the MNGP TS do not require this change.
Page 3 of 6
Palisades Nuclear Plant NMC is not proposing any variations or deviations from the model TS changes for TSTF-447, Revision 1. However, due to minor differences between Palisades TS and the model TS in NUREG-1432, "Standard Technical Specifications, Combustion Engineering Plants," Revision 2, in several cases small variances from the TSTF mark-up changes are necessary. These clarifications are discussed below and do not affect the adoption or application of TSTF-447, Revision 1.
- 1.
In the TSTF mark-ups, STS 3.3.11, PAM Instrumentation, is modified by eliminating Condition D and renumbers the remaining Conditions. In Palisades TS 3.1.7, Condition D has been marked "not used" and the remaining Conditions have not been renumbered. This change is equivalent to the TSTF mark-up and will avoid unnecessary renumbering in supporting plant documents.
- 2.
In the TSTF mark-ups, STS Table 3.3.11-1, Post Accident Monitoring Instrumentation, deletes line item 10 for the Containment Hydrogen Monitors and renumbers the remaining items. In Palisades Table 3.3.7-1, the equivalent line item, Item 7, has been marked as "deleted" and the remaining items have not been renumbered. This change is equivalent to the TSTF mark-up and will avoid unnecessary renumbering in supporting plant documents.
- 3.
In the TSTF mark-ups, STS 3.6.13, Shield Building Exhaust Air Cleanup System (SEBEACS)(Dual), is renumbered as STS 3.6.8. Palisades TS do not have an equivalent section, so these changes are not needed in the Palisades TS to adopt the TSTF.
- 4.
In the TSTF mark-ups, STS 5.6.7, Post Accident Monitoring Report, is modified to reflect changes made in the TSTF to the PAM Instrumentation Conditions. Palisades TS 5.6.6 does not have wording concerning specific PAM Instrumentation Condition numbers, so these changes are not needed in the Palisades TS to adopt the TSTF.
Page 4 of 6
Point Beach Nuclear Plant Point Beach Nuclear Plant (PBNP)-specific clarifications are being proposed so as to eliminate differences between the existing PBNP TS and the Standard TS (NUREG-1431, Revision 2) on which TSTF-447 is based. This variation will align PBNP TS 3.3.3 with the Standard TS in accordance with TSTF-447.
Surveillance Requirement (SR) 3.3.3.2, and an associated note, are not separately listed in the Standard TS (nor in TSTF-447). This requirement and the associated note are being proposed for deletion. SR 3.3.3.2 states, "Calibrate gas portion of Hydrogen Monitor. The associated note, which precedes it, states, "SR 3.3.3.2 applies to Function 14 only." This SR and its associated note were supplementary requirements that were carried over from the former PBNP Custom TS, during the conversion to Improved TS, as a surveillance necessary to ensure the operability of the hydrogen monitors.
Since the requirements for hydrogen monitors are being deleted from the PBNP TS, the supporting SR for hydrogen monitors is no longer required and may also be deleted.
The proposed deletion is consistent with TSTF-447.
TS Table 3.3.3-1, Item 14, Hydrogen Monitors, has an associated note (c), which states, (c)
Each monitor shall be powered from an independent power supply.
This note is not separately listed in the Standard TS (nor in TSTF-447). The note is being proposed for deletion. This note was a requirement that was carried over from the former PBNP Custom TS, during the conversion to Improved TS, as a plant-specific clarification of the requirements for the hydrogen monitors.
Since this note is only applicable to TS Table 3.3.3-1, Item 14, which is being deleted from the PBNP TS, the note is no longer required and may also be deleted. The proposed deletion is consistent with TSTF-447.
Other TS changes associated with this variation are limited to renumbering and formatting changes that resulted directly from the deletion of the above requirements related to hydrogen monitors. As a result of these plant-specific variations, the proposed changes to Point Beach TS 3.3.3 will make this specification consistent with TSTF-447.
Page 5 of 6
Prairie Island Nuclear Generating Plant Prairie Island Nuclear Generating Plant (PINGP) is not proposing any variations or deviations from the model TS changes for TSTF-447 Revision 1. However, due to differences between PINGP TS and the model STS in NUREG-1431, "Standard Technical Specifications, Westinghouse Plant," Revision 2 in several cases variances from the TSTF mark-up changes are necessary. These clarifications are discussed below and do not affect the adoption or application of TSTF-447, Revision 1.
LCO 3.3.3 PINGP LCO 3.3.3, [Event Monitoring] EM Instrumentation, Actions Table is formatted differently than NUREG-1431 and TSTF-447. In the PINGP TS mark-ups, LCO 3.3.3 is modified by revising the Note to Condition D, eliminating Condition E and re-lettering the following Conditions. These changes are necessary to remove the hydrogen monitors from the TS.
PINGP Surveillance Requirement (SR) includes SR 3.3.3.2 which the SR Table Note clarifies is only applicable to Function 11 (Hydrogen Monitors). This SR is being proposed for deletion and the SR Table Note is proposed to be conformed to the guidance of NUREG-1431. SR 3.3.3.3 is proposed to be re-numbered as SR 3.3.3.2.
Neither the Standard TS nor TSTF-447 identifies a separate SR for the Hydrogen Monitors. This SR, and the SR Table Note clarification, were supplementary requirements that were carried over from the former PINGP custom TS, during the conversion to Improved TS, as a surveillance necessary to ensure the operability of the hydrogen monitors. Since the requirements for Hydrogen Monitors are being removed from the PINGP TS, the supporting SR for Hydrogen Monitors is no longer required and may also be deleted. The proposed deletion is consistent with TSTF-447.
Table 3.3.3-1 mark-up differs from TSTF-447 in that, Item 11 is shown as "Not used" and the subsequent Item numbers remain unchanged.
LCO 3.6.7 The PINGP TS are numbered differently than NUREG-1431 for Westinghouse plants.
The TSTF-447 changes in LCO 3.6.8, "Hydrogen Recombiners" apply to PINGP TS LCO 3.6.7.
TS 5.6.8 The PINGP TS are numbered differently than NUREG-1431 for Westinghouse plants.
The TSTF-447 changes in TS 5.6.7, UEM Report" apply to PINGP TS 5.6.8. The specific reference to LCO 3.3.3 differs from TSTF447 due to the different format of LCO 3.3.3 discussed above.
Page 6 of 6
ENCLOSURE 3 The following Proposed Technical Specification Changes (Markups) are contained within Enclosure 3: A - Duane Arnold Energy Center B - Kewaunee Nuclear Power Plant C - Monticello Nuclear Generating Plant D - Palisades Nuclear Plant E - Point Beach Nuclear Plant Units I and 2 F - Prairie Island Nuclear Generating Plant Units I and 2 Page 1 of 1
ENCLOSURE 3A Proposed Technical Specification Changes (Markup)
Duane Arnold Energy Center Page 1 of 2
PAM Instrumentation 3.3.3.1 Table 3.3.3.1-1 (page 1 of 1)
Post Accident Monltoring Instrumentation CONDITIONS REFERENCED REQUIRED FROM REQUIRED FUNCTION CHANNELS ACTION D.1
- 1. Reactor Steam Dome Pressure 2
E
- a. Wide Range 2
E
- b. FuelZone 2
E
- 3. Suppression Pool Water Level 2
E
- 4. Drywell Pressure
- a. Narrow Range 2
E
- b. Wde Range 2
E
- 5. Primary ContaInment Area Radiation
- a. Drywell 2
F
- b. Suppression Chamber 2
F
- 6. PCIV Position 2 per penetration E
now path (aXb) 7.Hawl and 0,
prsb Ahaat" 6*44a~aly~ef 2
E b-G~~~~~~.Aftaly~~~~~~~~~~ef
~~~2 E
(a) Not required for Isolation valves whose assodated penetration flow path Is Isolated by at least one dosed and deactivated automatic valve, dosed manual valve, blind nange, or check valve with flow through the valve secured.
(b) Only one position IndIcation channel Is required for penetration flow paths with only one Installed control room IndicatIon channel.
DAEC 3.3-24 Amndment 223TSCR-067
ENCLOSURE 3B Proposed Technical Specification Changes (Markup)
Kewaunee Nuclear Power Plant Page 1 of 4
TABLE TS 3.5-6 ACCIDEN T
MO NITORINQ INSTRUMENTATIOtN OPERATING C DIONS-FR NICATO 1
1 2
REQUIRED TOTAL NO.
MINIMUM CHANNELS NO.
FUNCTIONAL UNIT OF CHANNELS OPERABLE' 1
Auxiliary Feedwater Flow to Steam Generators (Narrow Range Level Indication 1/steam generator2 Already Required OPERABLE by Table TS 3.5-2, Item 12) 2 Reactor Coolant System Subcooling Margin 2(
1 3
Pressurizer Power Operated Relief Valve Position (One Common Channel 2/valve(2) 1/valve Temperature, One Channel Limit Switch per Valve) 4 Pressurizer Power Operated Relief Block Valve Position (One Common Channel 2/valve(21 1/valve Temperature, One Channel Limit Switch per Valve) 5 Pressurizer Safety Valve Position 2/valve(2) 1/valve (One Channel Temperature, and One Acoustic Sensor per Valve) 6 Containment Water Level (Wide Range) 2_4 1
X Gomtammentiydrogem Mom_______________
+
8 Containment Pressure Monitor (Wide Range) 2(2) 1 9
Reactor Vessel Level Indication 2(4) 1 10 Core Exit Thermocouples(5) 4 thermocouple/core 2 thermocouple/core I__________________________________________________quadrant(
4 )
quadrant( 6) 11 Steam Generator Level (Wide Range) 2/steam generator(4) 1/steam generator (1) With the number of OPERABLE accident monitoring instrumentation channels less than the minimum channels OPERABLE requirements, either restore the minimum number of channels to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
(2) With the number of OPERABLE accident monitoring instrumentation channels less than the required total number of channels shown, either restore the inoperable channels to OPERABLE status within 14 days, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Page 1 of 2 Zuze*ien e-tr.
fl122L2DD4 o~o09/94
TABLE TS 3.5-6 ACCIDENT MONITORING INSTRUMENTATION OPERATING CONDITIONS FOR INDICATION 3~
th the nurber f OPERABLE tAeidet mntr* instumemtation ehaAlels less tham the equired ttal number of _hanels shIw__,
eith_r restore the ineperable ehammels t VE)ElABLE status within 30 days or be in at least I lOT STANDBYI' within the mext 6 hcus and Il9T C1 IUTDOWN with!i the following C hurs.leled (4) With the number of OPERABLE accident monitoring instrumentation channels less than the required total number of channels shown, either restore the inoperable channels to OPERABLE status within 7 days, or be In at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
(5) Refer also to TS 3.11.c and TS 3.11.d (6) For the purposes of accident monitoring instrumentation, thermocouples on the axis may be included in either adjacent quadrant.
PAS 2 ofedmen 2No 5
Page 2 of 2 01=21210 no~/G9/9
TABLE TS 4.1-1 MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS CHANNEL DESCRIPTION CHECK CALIBRATE TEST REMARKS
- 34. Safety Valve Position Monthly Each refueling cycle Not applicable Indicator (Acoustic)
- a. Back-up Monthly Each REFUELING cycle Not applicable (Temperature)
- 36. Reactor Coolant System Monthly Each refueling cycle Each refueling Subcooling Monitor cycle
- 37. Containment Pressure Daily Each refueling cycle Not applicable (Wide Range)
- 38. Containment Hydrogn Qaiy Eaoh rofuoling cycle
- 39. Containment Water Level Not applicable Not applicable Each refueling (Wide Range) cycle
- 40. Reactor Vessel Level Monthly Each refueling cycle Not applicable Indication
- 41. Core Exit Thermocouples Monthly Each refueling cycle Not applicable
- 42. Steam Generator Level Monthly Each refueling cycle Not applicable (Wide Range) j2~gAmondmont No. 151 ac 04 2O20 Page 6 of 7
ENCLOSURE 3C Proposed Technical Specification Changes (Markup)
Monticello Nuclear Generating Plant Page 1 of 5
TABLE OF CONTENTS (Cont'd) 3.4 and 4.4 3.5 and 4.5 3.6 and 4.6 3.7 and 4.7 Standby Liquid Control System A.
System Operation B.
Boron Solution Requirements C.
3.4 and 4.4 Bases Core and Containment/Spray Cooling Systems A.
ECCS Systems B.
RHR Intertie Return Line Isolation Valves C.
Containment Spray/Cooling System D.
RCIC E.
Cold Shutdown and Refueling Requirements F.
Recirculation System 3.5 and 4.5 Bases Primary System Boundary A.
Reactor Coolant Heatup and Cooldown B.
Reactor Vessel Temperature and Pressure C.
Coolant Chemistry D.
E.
Safety/Relief Valves F.
Deleted G.
Jet Pumps H.
Snubbers 3.6 and 4.6 Bases Containment Systems A.
'C Secondary Containment D.
Primary Containment Isolation Valves i~. Co 1btstible ias ConI
- 3yste, 3.7 Bases 4.7 Bases 93e 93 93 95 96 99' 101 101 103 104 105 106 107 110 121 121 122 123 126 127 128 129 145 156 156
.166 169 170 175 183 ii 08/21403, Amendment No. 9, 35, 17, 71, 77, 79, 102, 137
3.0 LIMITING GAS CONTROL SYSTEM 4.0 SURVEILLANCE REOUIREMENTS 3.0 LIMITING GAS CONTROL SYSTEM 4.0 SURVEILLANCE REQUIREMENTS 4
L.
-citi:La
-OnR001 SYSSM-
_J -
z
.E. -Gatustibl Gets CGntrci Gysteft 1 At loast GAnG 2n Gooortino MWIRo uorfIRm9 tho
- 1. :: cpurFto and inenpcdent C mbutibi.e 9a Czrntfel System tremms shall he. etea atal! Uiiv t"
I rcor ir in the r-n mods *xoPt-n-POWifid in oetia.E2 and 3 7 E3 boW.-.
- 2.
A4F o Of
-- e t_
btliblo Gac, Gontrl Syotm rAmln()
t madS oF founI o
40b IGPoraFbl fr yR catu ith n ^W0 dayc or Submit a GpROial roport to tho Commiccion within the no 30 days whI;h
_iA
$h*.-1Y01ffl!FR0 P;
- 1) Idontification of the inoporab10 legipment or gwb~','temt. and the reacon or inoperobility, 2)% Aoion(c) to be tken to ;rcto oipmont to.
oparable GtcWim, Qnd
-3) gwmmary dooriptien ef ootienLI) takon to-
. A4th both. of the Combicti!bio Gas CoRol1 Syrtom.
trAS 1AoPOFAb f
QA roncon, rooao at lnot4
. tai t zporable Atatue within 30 dayc or inf4irt n 3Fderly 6ItO~
of th ofuto G2acr Crnd he It
-eaei-aa IJ
-9 r
- 1 i-
- lilEiFilE Hi TO i iown4 ThArmotan and-eantrol otrol to I
- -I-.
h..
-2. TIno low indec~tr.
A.R2 gR1011 high! reh4 tPr High r~ct9o 4O~MbOWItepertur h_ Porform _ roolotn to aroutact +o-n all.
A Vor1 thIANiah _ ytounl PAMiRFAtOR that thefonr l
__*** *__IR
__Tl!
noA 1;%0i3Acn oomienrin
^
A
- w _ _ _
.sL _
..__s
. sL L t_
. ".t P;oaot cncO 0440ry sw) monin:s kgqwrm in rooomurnor
-realction Qhamber opwrility by hwoifyipe that he ouiot tomAratuO OOS& 6009P within411 Gno hour
__,j U-4
=Of -9
.^ e srr_
r t
-whn -ho pow r
rtn VVIit ll UIitceaotM im WhR4_P9WFr[!g_.
m~-~ t aiu
- e.
X_
r e
- 6.
no ait! :Nntneccr inW rcovMlalnero rind.
macaciad piping ohaii he '.orlfid during each
&hutdon whon; a Typo A~ oIvaorll Integrated
-contain3ment leakage test i egwirod by; cithor:
- a. _ening the O mbNHO t,__I_, t.
,h ntainment during tho Typo A t r*
h PorfcrrWin a teparato oakag4 tort of bllth rocornbinor tralnO and addng th rute to to-Tor A otie[
j I
- I 3.7/4.7 Next page is 175 172 Amendment No. 6-,74--
ltft§9
Table 3.14.1 Instrumentation for Accident Monitoring Function Total No. of Minimum No. of Required Instrument Channels Operable Channels Conditlons*
Reactor Vessel Fuel Zone Water Level 2
1 A, B Safety/Relief Valve Position 2
1 A, C (One Channel Pressure Switch and One Channel Thermocouple Position Indication per Valve)
Drywell Wide Range Pressure 2
1 A, B Suppression Pool Wide Range Level 2
1 A, B Suppression Pool Temperature 2
1 A, D Drywell High Range Radiation 2
1 A, D Dryell and Supposslon Pool 4-A, B-.
Offgas Stack Wide Range Radiation 2
1 A, D Reactor Bldg Vent Wide Range Radiation
- 2 I
A, D
- Required Conditions A.
When the number of channels made or found to be Inoperable is such that the number of operable channels is less than the total number of channels, either restore the Inoperable channels to operable status within seven days, or prepare and submit a special report to the Commission pursuant to Technical Specification 6.7.D within the next 30 days outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the system to operable status.
- 3.14/4.14 229b
.l42124t Amendment No. _ 8, 63, 4 04-
Table 4.14,1 Minimum Test and Calibration Frequency for Accident Monitoring Instrumentation Instrument Channel Test (Note 1)
Calibration (Note 1)
Sensor Check (Note 1)
Reactor Vessel Fuel Zone Water Level Monitor Once/Operating Cycle Oncelmonth (Note 3)
Safety/Relief Valve Position (Pressure Switches)
Once/Operating Cycle Once/month (Notes 2 & 4)
Safety/Relief Valve Position (Thermocouples)
Once/Operating Cycle Once/month (Note 4)
Drywell Wide Range Pressure Monitors Once/Operating Cycle Once/month Suppression Pool Wide Range Level Monitors Once/Operating Cycle Once/month Suppression Pool Temperature Once/Operating Cycle Once/month Drywell High Range Radiation Monitors Once/Operating Cycle Once/month Dr-::ll an~d Supprocclon Poe!
ort'O3rating Ccle o~
i ldrogon And ogeon Monitorr Offgas Stack Wide Range Radiation Monitors Once/Operating Cycle Once/month Reactor Bldg Wide Range Radiation Monitors Once/Operating Cycle Once/month Notes:
(1)
Functional tests, calibrations, and sensor checks are not required when the instruments are not required to be operable. If tests are missed, they shall be performed prior to returning the Instruments to an operable status.
(2)
Once/month sensor check will consist of verifying that the pressure switches are not tripped.
(3)
Once/month sensor check will consist of verifying that the fuel zone level indicates off scale high.
(4)
Following every Safety/Relief Valve actuation it will be verified that recorder traces or computer logs indicate sensor responses.
3.14/4.14 229d 4t89-Amendment No.c2-Gr68
ENCLOSURE 3D Proposed Technical Specification Changes (Markup)
Palisades Nuclear Plant Page 1 of 6
PAM Instrumentation 3.3.7 3.3 INSTRUMENTATION 3.3.7 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.7 The PAM instrumentation for each Function in Table 3.3.7-1 shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3.
ACTIONS KI IlT rE
-N -
L I
- 1.
LCO 3.0.4 is not applicable.
- 2.
Separate Condition entry is allowed for each Function.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more Functions A.1 Restore required 30 days with one required channel channel to OPERABLE inoperable.
status.
B.
Required Action and B.1 Initiate action in Immediately associated Completion accordance with Time of Condition A not Specification 5.6.6.
met.
C.
NOTE Not aipplicabl t hydFogen monitor ehnnels.
One or more Functions C.1 Restore one channel to 7 days with two required channels OPERABLE status.
Palisades Nuclear Plant 3.3.7-1 Amendment No. 4A9,
PAM Instrumentation 3.3.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D.
-$Rl~w D.1 Roctoro one hydrogen 72 hus monitor channels mnitor channel to finpef1ble.
OPERABLE status.
E. Required Action and E.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C ef4)~
Table 3.3.7-1 for the not met.
channel.
F. As required by Required F.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action E.1 and referenced in Table 3.3.7-1.
AND F.2 Be in MODE 4.
30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> G. As required by Required G.1 Initiate action in Immediately Action E.1 and referenced accordance with in Table 3.3.7-1.
Specification 5.6.6.
Palisades Nuclear Plant 3.3.7-2 Amendment No. 449,
PAM Instrumentation 3.3.7 Table 3.3.7-1 (page 1 of 1)
Post Accident Monitoring Instrumentation CONDITIONS REFERENCED REQUIRED FROM REQUIRED FUNCTION CHANNELS ACTION E.1
- 1.
Primary Coolant System Hot Leg Temperature (wide range)
- 2.
Primary Coolant System Cold Leg Temperature (wide range)
- 3.
Wide Range Neutron Flux
- 4.
Containment Floor Water Level (wide range)
- 5.
Subcooled Margin Monitor
- 6.
Pressurizer Level (wide range)
- 7.
r eeCoticnHdocnMnor
- 8.
Condensate Storage Tank Level
- 9.
Primary Coolant System Pressure (wide range)
- 10.
Containment Pressure (wide range)
- 11.
Steam Generator A Water Level (wide range)
- 12. Steam Generator B Water Level (wide range)
- 13.
Steam Generator A Pressure
- 14.
Steam Generator B Pressure
- 15. Containment Isolation Valve Position
- 16. Core Exit Temperature - Quadrant 1
- 17.
Core Exit Temperature - Quadrant 2
- 18.
Core Exit Temperature - Quadrant 3 2
2 F
F 2
2 F
F 2
2 2
2 2
F F
F F
2 2
F F
2 F
2 2
1 per valve(a) 4 4
4 4
2 2
F F
F F
F F
F G
G
- 19.
Core Exit Temperature - Quadrant 4
- 20.
- 21. Containment Area Radiation (high range)
(a)
Not required for isolation valves whose associated penetration is isolated by at least one closed and de-activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.
Palisades Nuclear Plant 3.3.7-4 Amendment No. 4A8,
Hydrogen rscombiners 3.6.7 3.6 CONTA!NMNIT SYSTEMS 3.6.7 Hdroaen Reeombinerz I
r Ct v Tr...
rr rrrl r
t-r_
t-1 9n CDA121 C-L - kJ d.U.f I ViU IIVUIUUUII IULUIIIUIIIUIL Lllll UU J - =lUl\\DL=.
A
-~
1O A ni IV.
tbA>C I
__,1 n
- F'-LR.,NILI I r
MUU 1 aIid.
ACTIONS GONDITION REQUIRFED ACTION COMPLETION TIME A.
One hydrogen recombincr NOTE inoporbl.
LCO 3.0.4 i not applicablo.
A.1 Roctoro hydrogon 3dayG rccombincr to OPER'ABLE ctatus.
- e.
Required Action and B.1 Bc in MODE 3.
6 heFS accociatod Completion Timo Palisades Nuclear Plant 3.6.7 1 Amendmont No. 180
Hydrogon Rocombuinor 3.67 GSURYEILA.NCE REQUIREMENTS SURVEILLANCE F
QNGY SR 3.6.7.1 PGr-form a system functional test for cach hydrogen 48-FeRthS FeermbinRe.
SR 3.6.7.2 Visually cxamine each hydrogen recombincr 48-FieRths onclocuro and verify thoro ic no evidAnca of abnormal ceRditioRs.
SR 3.6.7.3 Porform continuity and a rosistance to ground tct for 48 mnRth6 each hcatcr phasc.
n-
_____- -I
__ e-.. -- _ _ z -
, s1_
nn Palsades-NucleaF Rlam d.la.f '
fmNameEontR NOG. 1*U
ENCLOSURE 3E Proposed Technical Specification Changes (Markup)
Point Beach Nuclear Plant Units I and 2 Page 1 of 6
PAM Instrumentation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3 The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3.
ACTIONS 1.-LC-3.04-isnot-ppliable--------------------------N
- 1. LCO 3.0.4 is not applicable.
I)TE-S-
- 2. Separate Condition entry is allowed for each Function.
CONDITION REQUIRED ACTION COMPLETIONTIME A.
One or more Functions A.1 Restore required 30 days with one required channel to OPERABLE channel inoperable.
status.
B.
Required Action and B.1 Initiate action in Immediately associated Completion accordance with Time of Condition A not Specification 5.6.6.
met.
C.
NOTE C.1 Restore one channel to 7 days Not applicable to OPERABLE status.
hydrogen monitor Ghels.
One or more Functions with two required channels inoperable.
(continued)
Point Beach 3.3.3-1 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206
PAM Instrumentation 3.3.3 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLElONTIME D. To hydrogen monitor D.1 Rotoro one hydrogen 72 huF channtel inoporablo.
monitor chann to OPERABLE tatU6.
E-.
Required Action and E-2 1 Enter the Condition Immediately associated Completion referenced in Time of Condition C e4 Table 3.3.3-1 for the not met.
channel.
Hi. As required by F.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Required Action E-Q.1 and referenced in AND Table 3.3.3-1.
FE.2 Be in MODE 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> GE. As required by Required GE. 1 Initiate action in Immediately Action E_.1 and accordance with referenced in Specification 5.6.6.
Table 3.3.3-1.
Point Beach 3.3.3-2 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206
PAM Instrumentation 3.3.3 SURVEILLANCE REQUIREMENTS kL %Yr!T LJ I t---------------------------___________-
SR 3.3.3.1 applies to each PAM instrumentation Function in Table 3.3.3-1. SR 3.3.3.2 applies to Function 11 only. SR 3.3.3.32 applies to each PAM instrumentation Function in Table 3.3.3-1, except Function 12. SR 3.3.3.4a applies to Function 12 only.
SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.
S R 3.3.3.2 Calibrato gas portion of the Hydrogen Monitor.
02days SR 3.3.3.3
NOTE---------------------------
CHANNEL CALIBRATION of Containment Area Radiation (High Range) detectors shall consist of verification of a response to a source.
Perform CHANNEL CALIBRATION.
18 months SR 3.3.3.42 Perform TADOT.
18 months Point Beach 3.3.3-3 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206
PAM Instrumentation 3.3.3 Table 3.3.3-1 (page 1 of 1)
Post Accident Monitoring hstrumentation CONDITION REFERENCED FROM FUNCTION REQUIRED CHANNELS REQUIRED ACTION
.1
- 1. Reactor Coolant System (RCS) Subcooflng Monitor
- 2. RCS Hot Leg Temperature (Wide Range)
- 3. RCS Cold Leg Temperature (Wide Range)
- 4. RCS Pressure (Wide Range)
- 5. RCS Pressure (Narrow Range)
- 6. Reactor Vessel Water Level (Wide Range)
- 7. Reactor Vessel Water Level (Narrow Range)
- 8. Containment Sump B Water Level
- 9. Containment Pressure (Wide Range)
- 10. Containment Pressure (Intermediate Range)
- 11. Containment Pressure (Low Range)
- 12. Containment Isolation Valve Position
- 13. Containment Area Radiation (High Range) 2 2 per loop 2 per loop 2
2 2
2 2
2 2
2
- 11. Ivdroen I.¶onitor.
15.
14.
10A.
24g.
Pressurizer Level Steam Generator Water Level (Wide Range)
Steam Generator Water Level (Narrow Range)
Steam Generator Pressure Condensate Storage Tank Level Core Exit Temperature -
Quadrant I Core Exit Temperature -
Quadrant 2 2 per penetration flow path (a)(b) 2 A2 2
2 per steam generator 2 per steam generator 2 per steam generator 2 per tank 2
2 2
2 2
2 6G F
PFE P=E F-E rF£ r-9 F=E FT F£ F£ FE FE 221.
Core Exit Temperature -
Quadrant 3 23a.
Core Exit Temperature -
Quadrant 4 243,.
Auxiliary Feedwater Flow 2S.
Refueling Water Storage Tank Level (a)
Not required for solation valves whose associated penetration Is Isolated by at least one dosed and deactivated automatic valve, dosed manual valve, blind flange, or check valve with flow through the valve secured.
(b)
Only one position Indication channel is required for penetration flow paths with only one installed control room ndication channel.
(4 Each monitor chall Pe pwered from an Indopandent power supply' I
Point Beach 3.3.3-4 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)
- a.
RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, hydrostatic testing, LTOP enabling, and PORV lift settings as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:
(1) LCO 3.4.3, RCS Pressure and Temperature (PIT) Limits" (2) LCO 3.4.6, RCS Loops-MODE 4" (3) LCO 3.4.7, RCS Loops-MODE 5, Loops Filled" (4) LCO 3.4.10, Pressurizer Safety Valves" (5) LCO 3.4.12, "Low Temperature Overpressure Protection (LTOP)"
- b.
The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the NRC Letters dated October 6, 2000 and July 23, 2001.
- c.
The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.
5.6.6 PAM Report When a report is required by Condition B or GF of LCO 3.3.3, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.
5.6.7 Tendon Surveillance Report Abnormal conditions observed during testing will be evaluated to determine the effect of such conditions on containment structural integrity. This evaluation should be completed within 30 days of the identification of the condition. Any condition which is determined in this evaluation to have a significant adverse effect on containment structural integrity will be considered an abnormal degradation of the containment structure.
Point Beach 5.6-5 Unit 1 - Amendment No. 207 Unit 2 - Amendment No. 212
ENCLOSURE 3F Proposed Technical Specification Changes (Markup)
Prairie Island Nuclear Generating Plant Units I and 2 Page 1 of 8
EM Instrumentation 3.3.3 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. One or more required B.1 Restore required CET 30 days Core Exit Thermocouple channel(s) to OPERABLE (CET) channel(s) status.
AND At least 4 CET channels OPERABLE in the center region of the core.
AND At least one CET channel OPERABLE in each quadrant of the outside core region.
C. Required Action and C.1 Initiate action in accordance Immediately associated Completion with Specification 5.6.8.
Time of Condition A or B not met.
D. -NOTE------------
D.I Restore one channel to 7 days Not applicable to OPERABLE status.
hy) drogen monitor or CET channels.
One or more Functions with two required channels inoperable.
Prairie Island Units 1 and 2 Unit 1 - Amendment No. 4-:8 Unit 2 - Amendment No. 449 3.3.3-2
EM Instrumentation 3.3.3 ACTIONS (continued)_
CONDITION REQUIRED ACTION COMPLETION TIME L.
Two hydrogen monitor E. 1 Rcstorc one hydrogen hors hafnnels noperable.
monitor channel to OPERABLE status.
KR Three or more required
.1 Restore required channels 7 days CET channels inoperable to OPERABLE status.
in one or more quadrants.
AND Less than four CETs OPERABLE in the center region of the core.
G. Three or more required FG.1 Restore required channels 7 days CET channels inoperable to OPERABLE status.
in one or more quadrants.
AND Less than one CET OPERABLE in each quadrant of the outside core region.
- 14. Required Action and P14.1 Enter the Condition Immediately associated Completion referenced in Table 3.3.3-1 Time of Condition D, ET for the channel.
F or Hi not met.
Prairie Island Units I and 2 Unit 1 - Amendment No. 4-5-s Unit 2 - Amendment No. 449 3.3.3-3
EM Instrumentation 3.3.3 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME I1. As required by Required 1.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action UR.1 and referenced in Table 3.3.3-1.
[J. As required by Required
[J. 1 Initiate action in Immediately Action>.l and accordance with referenced in Specification 5.6.8.
Table 3.3.3-1.
Prairie Island Units I and 2 Unit 1 - Amendment No. 448 Unit 2 - Amendment No. 449 3.3.3-4
EM Instrumentation 3.3.3 SURVEILLANCE REQUIREMENTS NOTE-------------------------------
SR 3.3.3.1 and SR 3.3.3.> apply to each EM instrumentation Function in Table 3.3.3-1 exeept Function 1. SR 3.3.3.1 and SR 3.3.3.2 apply to Function 1 1.
SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.
SR 3.3.2 PerformChNN 0
EL CALIBRAT4ON.
92-days SR 3.3.3.
NOTE----------------------------
Neutron detectors are excluded from CHANNEL CALIBRATION.
Perform CHANNEL CALIBRATION.
24 months Prairie Island Units I and 2 Unit I - Amendment No. 4-5 Unit 2 - Amendment No. 449 3.3.3-5
EM Instrumentation 3.3.3 Table 3.3.3-1 (page I of 1)
Event Monitoring Instrumentation FUNCTION REQUIRED CHANNELS
- 1.
Power Range Neutron Flux (Logarithmic Scale)
- 2.
Source Range Neutron Flux (Logarithmic Scale)
- 3.
Reactor Coolant System (RCS) Hot Leg Temperature
- 4.
RCS Cold Leg Temperature S.
RCS Pressure (Wide Range)
- 6.
- 7.
Containment Sump Water Level (Wide Range)
- 8.
Containment Pressure (Wide Range)
- 9.
Penetration Flow Path Automatic Containment Isolation Valve Position
- 10.
Containment Area Radiation (High Range)
I.
44y4do-e)honto
- 12.
Pressurizer Level
- 13.
Steam Generator Water Level (Wide Range)
- 14.
Condensate Storage Tank Level
- 15.
Core Exit Temperature
- 16.
Refueling Water Storage Tank Level 2
2 2
2 2
2 2
2 2 per penetration flow path(a)(b) 2 CONDITION REFERENCED FROM REQUIRED ACTION
.1
[it El:4
[it
))I I
fit 2
2 per steam generator 2
fit it 4 per quadrant(c)
Elt 2
(a)
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.
(b)
Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.
(c)
A channel consists of one core exit thermocouple (CET).
Prairie Island Units 1 and 2 Unit 1 - Amendment No. 158 Unit 2 - Amendment No. 449 3.3.3-6
II) dregen Recembiners 3.6.7 3.6 CONTAINMENT SYSTEMS 3.6.7 Hoty se Iydrogen ReeembineFs t ' _ _
_1
_st t
TT" A Y A
^,
^
LLu C i..7 Iwo hdFrogen recombiners shall be U'lKAljLl.
A31PLGAB31JY:-i MODES 1 and 2.
A IONS C-ONDJI4ONI REQUIRED ACTI ON C
-OPLET N
~~~ ~~~~~~~~~~~~~~~4M4'-
,4.
One hydrogen A.l NOTE rveembinec inoperable.
I CO 3.0.4 is not applicable.
30 &ys Restarce hydrogen reeembiner to B.
Rcquired Ation and B.4 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> a.seeiated Compen Tim not met.~~~~~~~~~~~~~
Prairie Island Units and 2 Unit 1 - Amendment No. 458 Unit 2 - Amendment No. 4-49 3.6.7-1
Not Ued 4ydrogen Re-embiners 3.6.7 SURVEILLANCE REQUIREMNTS SURVElhLANGE FIMQU SR 3.6.7.1 Perform a system functional test for each 24 mnths hydrogen recombiner.
SR 3.6.7.2 Visually examine each hydrogen recombinet 24 months enclosure and verit there is no cvidenee of abnormal conditions.
SR 3.6.7.3 Perform a rsistance to ground test for each heater 24 months phase.~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
Prairie Island Units 1 and 2 Unit 1 - Amendment No. 4&n Unit 2 - Amendment No. 449 3.6.7-2
ENCLOSURE 4 The following Final Technical Specification Pages are contained within : A - Duane Arnold Energy Center B - Kewaunee Nuclear Power Plant C - Monticello Nuclear Generating Plant D - Palisades Nuclear Plant E - Point Beach Nuclear Plant Units I and 2 F - Prairie Island Nuclear Generating Plant Units I and 2 Page 1 of 1
ENCLOSURE 4A Proposed Technical Specification Pages Duane Arnold Energy Center Page 1 of 2
PAM Instrumentation 3.3.3.1 Table 3.3.3.1-1 (page 1 of 1)
Post Accident Monitoring Instrurnentaton CONDTIONS REFERENCED REQUIRED FROM REQUIRED FUNCTION CHANNELS ACTION D.1
- 1. Reactor Steam Dome Pressure 2
E
- a. Wide Range 2
E
- b. FuelZone 2
E
- 3. Suppression Pool Water Level 2
E
- 4. Drywell Pressure
- a. Narrow Range 2
E
- b. Wide Range 2
E
- 5. Primary Containment Area Radiation
- a. Drywel 2
F
- b. Suppression Chamber 2
F
- 6. PCIV Position 2 per penetration E
flow path (aXb)
I (a) Not requied for Isolation valves whose associated penetration flow path Is Isolated by at least one closed and deactivated automatic valve, dosed manual valve, blind flange, or check valve with flow through the valve seoured.
(b) Only one position Indicatlon channel Is required for penetration flow paths with only one Installed control room Indication channel.
DAEC 3.3-24 TSCR-067
ENCLOSURE 4B Proposed Technical Specification Pages Kewaunee Nuclear Power Plant Page 1 of 4
TABLE TS 3.5-6 ACCIDENT MONITORING INSTRUMENTATON OPERAi CO.,DMONS FORNDICATIOh
-I j
1 2
NO.
FUNCTIONAL UNIT REQUIRED TOTAL NO.
MINIMUM CHANNELS OF CHANNELS OPERABLE' I
Auxiliary Feedwater Flow to Steam Generators (Narrow Range Level Indication 1/steam generator("
Already Required OPERABLE by Table TS 3.5-2, Item 12) 2 Reactor Coolant System Subcooling Margin 2(
1 3
Pressurizer Power Operated Relief Valve Position (One Common Channel 2/valve(2)
I/valve Temperature, One Channel Limit Switch per Valve) 4 Pressurizer Power Operated Relief Block Valve Position (One Common Channel 2/valve 2) 1/valve Temperature, One Channel Limit Switch per Valve) 5 Pressurizer Safety Valve Position 2/valve(2) 1/valve (One Channel Temperature, and One Acoustic Sensor per Valve) 6 Containment Water Level (Wide Range) 2 1
7 Deleted l
8 Containment Pressure Monitor (Wide Range) 2(2) 1 9
Reactor Vessel Level Indication 2(4) 1 10 Core Exit Thermocouples(s) 4 thermocouple/core 2 thermocouple/core quadrant( 4 )
quadrant(6) 1 Steam Generator Level (Wide Range) 2/steam generator(4) 1/steam generator I
(') With the number of OPERABLE accident monitoring instrumentation channels less than the minimum channels OPERABLE requirements, either restore the minimum number of channels to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
(2) With the number of OPERABLE accident monitoring instrumentation channels less than the required total number of channels shown, either restore the inoperable channels to OPERABLE status within 14 days, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Page 1 of 2
TABLE TS 3.5-6 ACCIDENT MONITORING INSTRUMENTATION OPERATING CONDITIONS FOR INDICATION (3) Deleted
}
(4) With the number of OPERABLE accident monitoring instrumentation channels less than the required total number of channels shown, either restore the inoperable channels to OPERABLE status within 7 days, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
(5) Refer also to TS 3.11.c and TS 3.11.d (6) For the purposes of accident monitoring instrumentation, thermocouples on the axis may be included in either adjacent quadrant.
Page 2 of 2
TABLE TS 4.1-1 MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS CHANNEL DESCRIPTION CHECK CALIBRATE TEST REMARKS
- 34. Safety Valve Position Monthly Each refueling cycle Not applicable Indicator (Acoustic)
- a.
Back-up Monthly Each REFUELING cycle Not applicable (Temperature)
- 36. Reactor Coolant System Monthly Each refueling cycle Each refueling Subcooling Monitor cycle
- 37. Containment Pressure Daily Each refueling cycle Not applicable (Wide Range)
- 38. Deleted
- 39. Containment Water Level Not applicable Not applicable Each refueling (Wide Range) cycle
- 40. Reactor Vessel Level Monthly Each refueling cycle Not applicable Indication
- 41. Core Exit Thermocouples Monthly Each refueling cycle Not applicable
- 42. Steam Generator Level Monthly Each refueling cycle Not applicable (Wide Range)
I Page 6 of 7
ENCLOSURE 4C Proposed Technical Specification Pages Monticello Nuclear Generating Plant Page 1 of 5
TABLE OF CONTENTS (Cont'd) 3.4 and 4.4 3.5 and 4.5 3.6 and 4.6 3.7 and 4.7 Standby Liquid Control System A.
System Operation B.
Boron Solution Requirements C.
3.4 and 4.4 Bases Core and Containment/Spray Cooling Systems A.
ECCS Systems B.
RHR Intertie Return Line Isolation Valves C.
Containment Spray/Cooling System D.
RCIC E.
Cold Shutdown and Refueling Requirements F.
Recirculation System 3.5 and 4.5 Bases Primary System Boundary A.
Reactor Coolant Heatup and Cooldown B.
Reactor Vessel Temperature and Pressure C.
Coolant Chemistry D.
E.
Safety/Relief Valves F.
Deleted G.
Jet Pumps H.
Snubbers 3.6 and 4.6 Bases Containment Systems A.
Standby Gas Treatment System C.
Primary Containment Isolation Valves E.
(Deleted) 3.7 Bases 4.7 Bases a3e 93 93 95 96 99 101 101 103 104 105 106 107 110 121 121 122 123 126 127 128 129 145 156 156 166 169 170 I
175 183 ii Amendment No. 0, 35, 417, 71, 77, 79, 102,4137-
3.0 LIMITING GAS CONTROL SYSTEM 4.0 SURVEILLANCE REQUIREMENTS 3.0 LIMITING GAS CONTROL SYSTEM 4.0 SURVEILLANCE REQUIREMENTS 4
E. (Deleted)
E. (Deleted) 172 Amendment No. 35,71 I
3.7/4.7 NEXT PAGE IS 175
Table 3.14.1 Instrumentation for Accident Monitoring Function Total No. of Minimum No. of Required Instrument Channels Operable Channels Conditions*
Reactor Vessel Fuel Zone Water Level 2
1 A, B Safety/Relief Valve Position 2
1 A, C (One Channel Pressure Switch and One Channel Thermocouple Position Indication per Valve)
Drywell Wide Range Pressure 2
1 A, B Suppression Pool Wide Range Level 2
1 A, B Suppression Pool Temperature 2
1 A, D Drywell High Range Radiation 2
1 A, D Offgas Stack Wide Range Radiation 2
1 A, D Reactor Bldg Vent Wide Range Radiation 2
1 A, D
- Required Conditions I
A.
When the number of channels made or found to be inoperable is such that the number of operable channels is less than the total number of channels, either restore the inoperable channels to operable status within seven days, or prepare and submit a special report to the Commission pursuant to Technical Specification 6.7.D within the next 30 days outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the system to operable status.
3.14/4.14 229b Amendment No. 2, 37, 63, 104
Table 4.14.1 Minimum Test and Calibration Frequency for Accident Monitoring Instrumentation Instrument Channel Test (Note 1)
Calibration (Note 1)
Sensor Check (Note 1)
Reactor Vessel Fuel Zone Water Level Monitor Once/Operating Cycle Once/month (Note 3)
Safety/Relief Valve Position (Pressure Switches)
Once/Operating Cycle Once/month (Notes 2 & 4)
Safety/Relief Valve Position (Thermocouples)
Once/Operating Cycle Once/month (Note 4)
Drywell Wide Range Pressure Monitors Once/Operating Cycle Once/month Suppression Pool Wide Range Level Monitors Once/Operating Cycle Once/month Suppression Pool Temperature Once/Operating Cycle Once/month Drywell High Range Radiation Monitors Once/Operating Cycle Once/month Offgas Stack Wide Range Radiation Monitors Once/Operating Cycle Once/month Reactor Bldg Wide Range Radiation Monitors Once/Operating Cycle Once/month I
Notes:
(1)
Functional tests, calibrations, and sensor checks are not required when the instruments are not required to be operable. If tests are missed, they shall be performed prior to returning the instruments to an operable status.
(2)
Once/month sensor check will consist of verifying that the pressure switches are not tripped.
(3)
Once/month sensor check will consist of verifying that the fuel zone level indicates off scale high.
(4)
Following every Safety/Relief Valve actuation it will be verified that recorder traces or computer logs indicate sensor responses.
3.14/4.14 229d Amendment No. 2, 37, 63
ENCLOSURE4D Proposed Technical Specification Pages Palisades Nuclear Plant Page 1 of 4
PAM Instrumentation 3.3.7 3.3 INSTRUMENTATION 3.3.7 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.7 The PAM instrumentation for each Function in Table 3.3.7-1 shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3.
ACTIONS k1 Tr el NUI t-" -
- 1.
LCO 3.0.4 is not applicable.
- 2.
Separate Condition entry is allowed for each Function.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more Functions A.1 Restore required 30 days with one required channel channel to OPERABLE inoperable.
status.
B.
Required Action and B.1 Initiate action in Immediately associated Completion accordance with Time of Condition A not Specification 5.6.6.
met.
C.
One or more Functions C.1 Restore one channel to 7 days with two required channels OPERABLE status.
I Palisades Nuclear Plant 3.3.7-1 Amendment No.
A8,
PAM Instrumentation 3.3.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D.
(Not used)
E.
Required Action and E.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C not Table 3.3.7-1 for the met.
channel.
F.
As required by Required F.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action E.1 and referenced in Table 3.3.7-1.
AND F.2 Be in MODE 4.
30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> G.
As required by Required G.1 Initiate action in Immediately Action E.1 and referenced accordance with in Table 3.3.7-1.
Specification 5.6.6.
I I
Palisades Nuclear Plant 3.3.7-2 Amendment No. 4A,
PAM Instrumentation 3.3.7 Table 3.3.7-1 (page 1 of 1)
Post Accident Monitoring Instrumentation CONDITIONS REFERENCED FROM REQUIRED ACTION E.1 REQUIRED CHANNELS FUNCTION
- 1.
Primary Coolant System Hot Leg Temperature (wide range)
- 2.
Primary Coolant System Cold Leg Temperature (wide range)
- 3.
Wide Range Neutron Flux
- 4.
Containment Floor Water Level (wide range)
- 5.
Subcooled Margin Monitor
- 6.
Pressurizer Level (wide range)
- 7.
(Deleted)
- 8.
Condensate Storage Tank Level
- 9.
Primary Coolant System Pressure (wide range)
- 10. Containment Pressure (wide range)
- 11.
Steam Generator A Water Level (wide range)
- 12.
Steam Generator B Water Level (wide range)
- 13.
Steam Generator A Pressure
- 14.
Steam Generator B Pressure
- 15. Containment Isolation Valve Position
- 16. Core Exit Temperature - Quadrant 1
- 17. Core Exit Temperature - Quadrant 2
- 18.
Core Exit Temperature - Quadrant 3
- 19.
Core Exit Temperature - Quadrant 4
- 20.
- 21.
Containment Area Radiation 2
2 F
F 2
2 2
2 2
2 2
2 2
2 2
1 per valve(a) 4 4
4 4
2 2
I (high range)
(a)
Not required for isolation valves whose associated penetration is isolated by at least one closed and de-activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.
Palisades Nuclear Plant 3.3.7-4 Amendment No. 4A,
ENCLOSURE 4E Proposed Technical Specification Pages Point Beach Nuclear Plant Units 1 and 2 Page 1 of 6
PAM Instrumentation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3 The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3.
ACTIONS
NOTES---------------------------------------------
- 1. LCO 3.0.4 is not applicable.
- 2. Separate Condition entry is allowed for each Function.
CONDITION REQUIRED ACTION COMPLEI1ONTIME A.
One or more Functions A.1 Restore required 30 days with one required channel to OPERABLE channel inoperable.
status.
B.
Required Action and B.1 Initiate action in Immediately associated Completion accordance with Time of Condition A not Specification 5.6.6.
met.
C.
One or more Functions C.1 Restore one channel 7 days with two required to OPERABLE status.
channels inoperable.
(continued)
Point Beach 3.3.3-1 Unit 1 - Amendment No.
Unit 2 - Amendment No.
PAM Instrumentation 3.3.3 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETIONTIME D.
Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C Table 3.3.3-1 for the not met.
channel.
E.
As required by E.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Required Action D.1 and referenced in AND Table 3.3.3-1.
E.2 Be in MODE 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> F.
As required by Required F.1 Initiate action in Immediately Action D.1 and accordance with referenced in Specification 5.6.6.
Table 3.3.3-1.
I I
Point Beach 3.3.3-2 Unit 1 - Amendment No.
Unit 2 - Amendment No.
PAM Instrumentation 3.3.3 SURVEILLANCE REQUIREMENTS
NOTE-------------------------------------------------
SR 3.3.3.1 applies to each PAM instrumentation Function in Table 3.3.3-1. SR 3.3.3.2 applies to each PAM instrumentation Function in Table 3.3.3-1, except Function 12.
SR 3.3.3.3 applies to Function 12 only.
SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.
NOTE---------------------------
CHANNEL CALIBRATION of Containment Area Radiation (High Range) detectors shall consist of verification of a response to a source.
Perform CHANNEL CALIBRATION.
18 months SR 3.3.3.3 Perform TADOT.
18 months I
I Point Beach 3.3.3-3 Unit 1 - Amendment No.
Unit 2 - Amendment No.
PAM Instrumentation 3.3.3 Table 3.3.3-1 (page 1 of 1)
Post Accident Monitoring Instrumentation CONCDON RFERENCED FROM FUNCTION REQUFED CHANNELS REQUIRED ACTION D.1
- 1. Reactor Coolant System (RCS) Subcooling Monitor
- 2.
RCS Hot Leg Temperature (Wide Range)
- 3.
RCS Cold Leg Temperature (Wide Range)
- 4. RCS Pressure (Wide Range)
- 5.
RCS Pressure (Narrow Range)
- 6. Reactor Vessel Water Level (Wide Range)
- 7.
Reactor Vessel Water Level (Narrow Range)
- 8. Containment Sump B Water Level
- 9. Containment Pressure (Wide Range)
- 10. Containment Pressure (Intermediate Range)
- 11. Containment Pressure (Low Range)
- 12. Containment Isolation Valve Position
- 13. Containment Area Radiation (High Range)
- 14. Pressurizer Level
- 15. Steam Generator Water Level (Wide Range)
- 16. Steam Generator Water Level (Narrow Range)
- 17. Steam Generator Pressure
- 18. Condensate Storage Tank Level
- 19. Core Exit Temperature -
Quadrant 1
- 20. Core Exit Temperature -
Quadrant 2
- 21. Core Exit Temperature -
Quadrant 3
- 22. Core Exit Temperature -
Quadrant 4
- 23. Auxiliary Feedwater Flow
- 24. Refueling Water Storage Tank Level 2
2 per loop 2perloop 2
2 2
2 2
2 2
2 2 per penetration flow path (a)(b) 2 2
2 per steam generator 2 per steam generator 2 per steam generator 2 per tank 2
2 2
2 2
2 E
E (a)
Not required for isolation valves whose associated penetration Is Isolated by at least one dosed and deactivated automatic valve, dosed manual valve, blind flange, or check valve with flow through the valve secured.
(b)
Only one position Indication channel Is required for penetration flow paths with only one installed control room ndication channel.
I Point Beach 3.3.3-4 Unit 1 - Amendment No.
Unit 2 - Amendment No.
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)
- a.
RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, hydrostatic testing, LTOP enabling, and PORV lift settings as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:
(1) LCO 3.4.3, RCS Pressure and Temperature (P/T) Limits" (2) LCO 3.4.6, RCS Loops-MODE 4" (3) LCO 3.4.7, RCS Loops-MODE 5, Loops Filled" (4) LCO 3.4.10, Pressurizer Safety Valves" (5) LCO 3.4.12, Low Temperature Overpressure Protection (LTOP)"
- b.
The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the NRC Letters dated October 6, 2000 and July 23, 2001.
- c.
The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.
5.6.6 PAM Report When a report is required by Condition B or F of LCO 3.3.3, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.
5.6.7 Tendon Surveillance Report Abnormal conditions observed during testing will be evaluated to determine the effect of such conditions on containment structural integrity. This evaluation should be completed within 30 days of the identification of the condition. Any condition which is determined in this evaluation to have a significant adverse effect on containment structural integrity will be considered an abnormal degradation of the containment structure.
Point Beach 5.6-5 Unit 1 - Amendment No.
Unit 2 - Amendment No.
ENCLOSURE 4F Proposed Technical Specification Pages Prairie Island Nuclear Generating Plant Units I and 2 Page 1 of 7
EM Instrumentation 3.3.3 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. One or more required B.1 Restore required CET 30 days Core Exit Thermocouple channel(s) to OPERABLE (CET) channel(s) status.
AND At least 4 CET channels OPERABLE in the center region of the core.
AND At least one CET channel OPERABLE in each quadrant of the outside core region.
C. Required Action and C.1 Initiate action in Immediately associated Completion accordance with Time of Condition A or B Specification 5.6.8.
not met.
D. ----------NOTE------------
D.1 Restore one channel to 7 days Not applicable to CET OPERABLE status.
channels.
One or more Functions with two required channels inoperable.
Prairie Island Units I and 2 Unit 1 - Amendment No. 4-Unit 2 - Amendment No. 449 3.3.3-2
EM Instrumentation 3.3.3 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME E.
Three or more required E.1 Restore required channels 7 days CET channels inoperable to OPERABLE status.
in one or more quadrants.
AND Less than four CETs OPERABLE in the center region of the core.
F.
Three or more required F. 1 Restore required channels 7 days CET channels inoperable to OPERABLE status.
in one or more quadrants.
AND Less than one CET OPERABLE in each quadrant of the outside core region.
G. Required Action and G. 1 Enter the Condition Immediately associated Completion referenced in Table 3.3.3-1 Time of Condition D, E, for the channel.
or F not met.
Prairie Island Units I and 2 Unit 1 - Amendment No. 148 Unit 2 - Amendment No. 449 3.3.3-3
EM Instrumentation 3.3.3 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME H. As required by Required H.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action G.1 and referenced in Table 3.3.3-1.
I.
As required by Required 1.1 Initiate action in Immediately Action G. 1 and accordance with referenced in Specification 5.6.8.
Table 3.3.3-1.
I Prairie Island Units I and 2 Unit I - Amendment No. 458 Unit 2 - Amendment No. 449l 3.3.3-4
EM Instrumentation 3.3.3 SURVEILLANCE REQUIREMENTS NOTE--------------------------------------------------
SR 3.3.3.1 and SR 3.3.3.2 apply to each EM instrumentation Function in Table 3.3.3-1.
I SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.
NOTE----------------------------
Neutron detectors are excluded from CHANNEL CALIBRATION.
Perform CHANNEL CALIBRATION.
24 months Prairie Island Units I and 2 Unit 1 - Amendment No. 485l Unit 2 - Amendment No. 149 3.3.3-5
EM Instrumentation 3.3.3 Table 3.3.3-1 (page I of I)
Event Monitoring Instrumentation FUNCTION
- 1.
Power Range Neutron Flux (Logarithmic Scale)
REQUIRED CHANNELS 2
CONDITION REFERENCED FROM REQUIRED ACTION G.1 H
I
- 2.
Source Range Neutron Flux (Logarithmic Scale)
- 3.
Reactor Coolant System (RCS) Hot Leg Temperature
- 4.
RCS Cold Leg Temperature
- 5.
RCS Pressure (Wide Range)
- 6.
- 7.
Containment Sump Water Level (Wide Range)
- 8.
Containment Pressure (Wide Range)
- 9.
Penetration Flow Path Automatic Containment Isolation Valve Position
- 10.
Containment Area Radiation (ligh Range)
II.
Pressurizer Level
- 12.
Steam Generator Water Level (Wide Range)
- 13.
Condensate Storage Tank Level
- 14.
Core Exit Temperature
- 15.
Refueling Water Storage Tank Level 2
2 2
2 2
2 2
2 per penetration flow path(a)(b) 2 2
2 per steam generator 2
4 per quadrant(C) 2 H
H1 H
H H
H H
H I
H1 H1 H1 (a)
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.
(b)
Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.
(c)
A channel consists of one core exit thermocouple (CET).
Prairie Island Units 1 and 2 Unit 1 - Amendment No. 4l-Unit 2-Amendment No. 149 3.3.3-6
Not Used 3.6.7 3.6 CONTAINMENT SYSTEMS 3.6.7 Not Used I
I Prairie Island Units 1 and 2 3.6.7-1 Unit 1 - Amendment No. 48 Unit 2 - Amendment No. 449l