ML20211G730
| ML20211G730 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 08/26/1999 |
| From: | Terry C, Woodlan D TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20211G738 | List: |
| References | |
| TXX-99202, NUDOCS 9909010015 | |
| Download: ML20211G730 (46) | |
Text
?
u%s TXU TNU Electric C. Lance Terry
' Comanche Peak _ Senior Vee President & Principal Nuclear Officer steam Electrk Station PO. Box 1002 Gen Rose,TX 76043
. T;l:254 897 8920 Fax:254 8976652 iterryl@txu.com Log # TXX-99202 File # 10010 916 (TRM)
Ref # 10CFR50.36 August 26,1999 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446, TRANSMITTAL OF I
TECHNICAL REQUIREMENTS MANUAL (TRM) REVISIONS 29 AND 30 Gentlemen:
i TXU Electric herewith submits Revisions 29 and 30 (enclosed) of the CPSES Technical Requirements Manual (TRM). Enclosed is the following document:
Technical Requirements Manual I signed original Revisions 29 and 30 and 10 copies Attachments I and 2 contain a description of the changes for Revisions 29 and 30 respectively. All changes applicable to CPSES Units 1 and 2 have been reviewed under the TXU Electric 10CFR50.59 process and found not to include any "unreviewed safety questions."
8 TXU Electric was formerly TU Electric. A license amendment request (LAR 99-003) was submitted per TXX-99122, dated May 14,1999, to revise the company name contained in the CPSES operating licenses. i
.nd 1 9909010015 990826 PDR ADOCK 05000445 l P PDR
)
e y TXU TXX-99202 Page 2 of 2 TRM Revisions 29 and 30, dated July 27,1999, became effective at 12:01 AM CST on July 27,1999.
This communication contains no new licensing basis commitments regarding CPSES Units I and 2. Ifyou have any questions, please contact Carl Corbin at (254) 897-0121.
Sincerely, C. L. Terry By:
D. R. Woodlan Docket Licensing Manager CBC/cbc Attachments Enclosure c- E. W. Merschoff, Region IV J. I. Tapia, Region IV
! D. H. Jaffe, NRR Resident Inspectors, CPSES l
Ch nga D:scriptions for TRM R: vision 29 Attachm:nt 1 to TXX-99202 Page 1 of 40 Summary The Current Technical Specifications (CTS) (Amendment 63/49) are being converted to the improved Technical Specifications (ITS) (Amendment 64). To support this effort, several items are relocated from the CTS to the improved Technical Requirements Manual (ITRM) (Revision
- 29. Also the relocated items and the Current Technical Requirements Manual (CTRM)
(Revision 28) are being converted to the new ITS iormat. TRM Revision 29 relocates requirements, which do not meet the Technical Specification criteria in 10CFR50.36(c)(2)(ii), to documents with established control programs such as the Technical Requirements Manual).
Further information / discussion of the Technical Specifications being relocated is provided in 1 of the CPSES ITS conversion submittal (Reference 1).
To ensure an appropriate level of control, these Technical Specification requirements are relocated to the TRM which is subject to the provisions of 10 CFR 50.59.
Compliance with the relocated requirements will not be affected by this proposed change to the TRM. The required periodic surveillances will continue to be performed to ensure that limits on parameters are maintained. Therefore, relocation of these requirements from the CTS to the ITRM will have no impact on system operability or the maintenance of controlled parameters within limits.
The CTRM was created using a similar format to the CTS. It is necessary to convert the existing Technical Requirements in the CTRM and the relocated Technical Specifications from the CTS to the new format and terminology of the ITS. These changes are considered editorial in nature (e.g. revised section numbers, new format, new rules of usage) and are made for consistency with the new ITS. Technical changes (e.g. removal of shutdown requirements from a relocated specification) are not included in this TRM Revision.
Maintaining duplicate information requires more resources and creates the potential for errors.
Therefore where ever possible, improved TRM (ITRM) sections (e.g. definitions, applicability) will refer to the ITS for related information.
The technical requirements will be restructured to the new ITS format (Limiting Condition for Operability, Applicability, Actions, Surveillance Requirements). The existing Bases information is relocated from the CTRM and the CTS. The new ITS format is not utilized for all of the relocated Bases information.
I l
r Ching3 Descriptions for TRM R: vision 29 Attachment 1 to TXX-99202 Page 2 of 40 The ITRM was developed from three general types of technical requirements " full", " supporting",
or " partial".
A " full" technical requirement is self-contained and includes a limiting condition for operation (TR LCO), applicability statement, actions, and surveillances (TRS), or ,
includes information within the existing requirement to develop the new required format.
A " supporting" technical requirement contains information (e.g. response times table) which is used by ITS.
A " partial" technical requirement is developed from a specific item out of an existing Technical Specification (e.g. a Surveillance). This item can not stand alone, therefore a technical requirement LCO, Applicability, Actions, and Surveillances, and Bases were created as required. The " partial" Technical Requirements refer to the source of the newly developed ITRM requirement, not the final product.
The ITRM section numbers will be the same as ITS with the following exceptions:
- 1. Add "1" to the beginning of each number to prevent confusion with Technical Specifications Example:
Technical Specification - 3.3.1 Reactor Trip System Instrumentation Technical Requirement- 13.3.1 Reactor Trip System instrumentation Response Times
- 2. Technical Requirements which are directly tied to the Technical Specifications will have the same number (other than the added "1" described above) as the Technical Specification (i.e. Technical Requirement 13.3.1 - Reactor Trip Response Times)
- 3. Technical Requirements not directly tied to the Technical Specifications will be grouped under a related Technical Specification general section nurnber.
Example:
Technical Requirement- 13.3.31 Seismic Instrumentation Note: These type of Technical Requirements will be numbered sequentially starting with the number "31". The number "31" was chosen because the highest subsection number in the Improved Technical Specifications was "20". The number "13" indicates a TRM requirement, the "3.3" indicates the TR is related to instrumentation, the "31" indicates the TR is not directly tied to the Technical Specifications.
Ch:ngs D:scriptions for TRM Ravision 29 Attachment 1 to TXX-99202 j Page 3 of 40 Format for description of changes:
Change Request No. [ sequential number]
ITRM NoJTitle l
(Improved Technical Requirement Manual Section Number, Revision 29]
lTS Reference # [ Improved Technical Specifications (Amendment 64) which are directly referenced by the improved Technical Requirement]
q ITS Change No. [Related change as identified in margins of ITS Submittal, Reference 1] '
CTS No. [ Current Technical Specification Number, Amendment 63/49]
CTRM No. [ Current Technical Requirement Section Number, Revision 28]
[ Description of change: j Where applicable, excerpts from the ITS change description are included (Soction 3A of References 1 and 2.
i BASES:]
]
A cross reference table between the CTRM, CTS, ITS, and ITRM is provided below. Due to the major format changes, TRM Revision 29 contains no revision bars.
The CTRM BASES Sections are located with each individual Technical Requirement. The ITRM BASES have been relocated to BASES Section at the end of the Technical Requirements Manual.
i
~
. Chings D:SCriptionS for TRM R:viSlon 29 AttaChmsnt 1 to TXX-99202 Page 4 Of 40 Cross Reference Table - CTRM vs. CTS vs. ITS vs. ITRM Change Current l Current Tech ITS Ref improved Section Description ITS Change Full',
RequestTRM Sect' Spec (Amend (Amend. TRM Sect No. Partial, or No. (Rev 2.8).63/49) 64) (Rev 29) __Supp _
1 0.1 - - 11.1-4 Definitions, Logical Connectors, Completion Times, - -
Frequency 2 0.2 - - 13 Applicability - -
-3 - 3/4.1.2.2 - 13.1.31 Boration Flow Path - Operating 7-01-R full 4 - 3/4.1.2.1 - 13.1.32 Boration Flow Path Shutdown 6-01-R full 5 - 3/4.1.2.4 - 13.1.33 Charging Pump Operating 9-01-R full 6 - 3/4.1.2.3 - 13.1.34 Charging Pump Shutdown 8-01-R full 7 - 3/4.1.2.6 - 13.1.35 Borated Water Sources Operating 11-01-R fuit 8 - 3/4.1.2.5 - 13.1.36 Borated Water Sources Shutdown 10-01-R full 9 - 4.1.3.1.1, 3.1.4, 3.1.7 13.1.37 Rod Group Alignment Limits and Rod Position Indicator 12-16-LG partial 4.1.3.2 10 - 4.1.3.6 3.1.6 13.1.38 Control Bank Insertion Limits 12-16-LG partial 11 - 3/4.1.3.3, - 13.1.39 Rod Position Indication - Shutdown 14-01-R 5- full 3/4.10.5, tsi- 02-M 006-r0 12 1.3 - - 13.2.31 Moveable incore Detection System - full 13 - 4.2.1.1.a2.b 3.2.3 13.2.32 Axial Flux Difference (AFD) 1-07-LG partial 14 - 4.2.4.1.b 3.2.4 13.2.33 Quadrant Power Tilt Ratio (OPTR) Alarm 1-07-LG partial 15 1.1 3/4.3.1 3.3.1 13.3.1 Reactor Trip System (RTS) Instrumentation Response - support Times 16 1.2 3/4.3.2: 3.3.2 13.3.2 Engineered Safety Feature Actuation System (ESFASl - support 4.7.1.2.c.1, Instrumentation Response Times B3/4.7.1.2 17 1.2 3/4.3.2 3.3.5 13.3.5 Loss of Power (LOP) Diesef Generator (DG) Start - support instrumentation Response Times 18 1.4 - - 13.3.31 Seismic Instrumentation - ft.II 19 - T3.31,6.a.2 - 13.3.32 Source Range, Neutron Flux 1-38-R partial 20 - 3/4.3.4 - 13.3.33 Turbine Overspeed Protection 10-01-R full .
21 - 3.4.5.2.f. 3.4.14 13.4.14 Reactor Coolant System Pressure isolation Valves 6-07-LG support 4.4.5.2.2, T3.4-1 22 1.5 - - 13.4.31 Loose Part Detection System - -
23: . 4.4.4.1.b. 3.4.11 13.4.32 Pressurtzer Power Operated Relief Valves (PORVs) 4-04-LG partial B3/4.4.4 24 - 3/4.4.6 - 13.4.33 RCS Chemistry 7-01-R full 25 - 3/4.4.8.2 - 13.4.34 Pressurizer 9-05-R full 26 - 3/4.4.10 - 13.4.35 RCS Vent Specification 11-01-R fuit 27 - 4.5.2.c 3.5.2, 3.5.3 13.5.31 ECCS - Containment Debris 2-09-LG partial
__28 - 4.5.2.h 3.5.2, 3.5.3 13.5.32 ECCS - Pump Line Flow Rates 2-15-LG partial 29 2.1 3/4.6.3 3.6.3 13.6.3 Containment isolation Valves - support 30 2.2 3/4.6.2.1 3.6.6 13.6.6 Containment Spray System - su,pport 31 - 4.6.4.2.b.1 3.6.8 13.6.31 Hydrogen Recombiners Instrumentation and Control 13-04-LG partial Circuits 32 - 4.7.1.7.a 3.7.4 13.7.31 Steam Generator Atmospheric Relief Valves (ARVs)- 6-06-LG partial Air Accumulator Tank 33 - 3/4.7.2 - 13.7.32 Steam Generator Pressure /7emperature Limitation 14-01-R full
- 34 - 3.7.5.c; 3.7.9 13.7.33 Ultimate Heat bink Sediment and Safe Shutdown (SSI) 13-03-R partial Action b; Impoundment Dam 4.7.5.b c 35 - 3/4.7.6 - 13.7.34 Flood Protection 15-01-R full 36 3.1 3/4.7.9 various 13.7.35 Snubbers 16-01-R support 37 - 3/4.7.10 - 13.7.36 Area Temperature Monitoring 17-01-R full 38 - 4.7.12.b 3.7.19 13.7.37 Safety Chilled Water System - Electrical Switchgear 18-02-LG partial Area Emergency Fan Coil Units 39 - 3/4.7.13 - 13.7.38 Main Feedwater isolation Valve Pressure / Temperature 19-01-R full ;
Limit {
l
Changs D SCriptionS for TRM R: vision 29 Attachm:nt 1 to TXX-99202 Page 5 of 40 Cross Reference Table - CTRM vs. CTS vs. ITS vs. ITRM Change Current ITS Ref Improved Section Description ITS Change Full',
' Request lTRM SpecSect (Amend l Current (Amend.
Tech TRM Sect No. Partial, or No. (Rev_28) 63/49) ___ __64) _ (R_ev_29) __Supp_
40 - various, tsi- various 13.7.39 Tomado Missile Shields - full 003-r4 41 - existing - 13.7.40 Feedwater Control Valves (FCVs) and Associated - -
I technical Bypass Valves evaluation 42 - 4.8.1.1.2.a.6, 3.8.1, 3.8.2 13.8.31 AC Sources (Diesef Generator Requirements) 1-20-LG,1- partial ;
f.1,8,13, h 38-LG,1 j 39-LG 43 4.1 3/4.8.4 various 13.8.32 Containment Penetration Conductor Overcurrent 4-01-R full Protection Devices j 44 - 3/4.9.3 - 13.0.31 Decay Time 3-01-R full 45 - 3/4.9.5 - 13.9.32 Refueling Operations / Communications 5-01-R full 46 - 3/4.9.6 - 13.9.33 Refueling Machine 6-01-R full i
47 - 3/4.9.7 - 13.9.34 Refueling - Crane Travel- Spent Fuel Storage Areas 7-01-R full 48 - 3/4.9.9.2 - 13.9.35 Water Level, Reactor Vessel, Control Rods 10-01-R full 49 - 3/4.9.10 - 13.9.36 Fuel Storage Area Water Level 11-01-LG partial 11-04-LG 50 - 3/4.3.3.4, tsi- 5.5.12a 13.10.31 Explosive Gas Monitoring Instrumentation N)1-LG full 005-r0 51 - 3/4.11.2.2 5.5.12b 13.10.32 Gas Storage Tanks 1-03-LG fuit 52 - 3/4.11.1 5.5.12c 13.10.33 Liquid Holdup Tanks 101-LG full 53 - 3/4.11.2.1 5.5.12a 13.10.34 Explosive Gas Mixture 1-02-LG fuit 54 0 6.8.1.1 5.5.17 15.5.17 Administrative Control Process - -
i 55 3.1 - various 15.5.31 Snubber Augmented Inservice inspection Program - -
l 56 3.2, 3.3 - - - Sections 3.2,3.3 deleted by previous TRM Rev - - I NOTES:
- 1. The ITRM was developed from three general types of technical requirements full, supporting, or partial. A " full" technical requirement is self-contained and includes a limiting condition for operation (TR LCO), apphcability statement, actions, and surveillances (TRS), or includes information within the existing requirement to develop the new required format. A " supporting" .
technical requirement contains information (e.g. response times table) which is used by ITS. A " partial" technical requirement is developed from a specific item out of an existing Technical Specification (e.g. a Technical Surveillance). This item can not stand alone, therefore a technical requiremeat LCO, Applicability, Actions, and Survelilances, and Bases were created as requirod.,
The " partial" Technical Requirements refer to the source of the newly developed ITRM requirement not the final product.
J l
l 4
Ch nge D:scriptions for TRM R vision 29 Attachm:nt 1 to TXX-99202 Page 6 of 40 Change Request # TR-97-009.1 ITRM # 11.1 - 11.4 Use and Application: Definitions, Logical Connectors, Completion Times, Frequency ITS Reference # -
ITS Change # -
CTS # -
CTRM # 0.1 Description of change:
Similar to the CTRM, the ITRM indicates that the use and application of the Technical Specifications apply to the Technical Requirements. This change provides consistency between the Technical Specifications and the Technical Requirements Manual.
Change Request # TR-97-009.2 iTRM # 13.0 Technical Requivment Limiting Condition for Operation (TR LCO) and
- whnical Requirement Surveillance (TRS)
Applicability ITS Reference # -
ITS Change # -
CTS # -
CTRM # 0.2 Description of change:
The guidance for use and application of the LIMITING CONDITION FOR OPERATION j (LCO) APPLICABILITY and SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ]
contained in the Technical Specifications is applicable to the Technical Requirements I contained in the TRM. A cross reference table between the Technical Requirements l Section and the Technical Specification Section is included.
The ITRM does not have a Section similar to Technical Specification LCO 3.0.3. As part of the conversion to the Improved Technical Specifications in July 1999, certain Technical Specifications were relocated to the Improved Technical Requirements Manual. The shutdown requirements (similar to TS LCO 3.0.3) for each Technical Requirement are in three categories: (1) remains with the parent Technical Specification by direct reference to the Technical Specifications, (2) relocated by incorporation into the individual Technical Requirements (i.e. additional conditions were added), or (3) not applicable (i.e. all possible conditions were addressed within the TR LCO). Therefore, the TRM has no corresponding LCO 3.0.3 similar to the TS LCO 3.0.3.
When a Required Action and Completion Time is not met and no associated Required Action is provided, the condition will be documented in the corrective action program (e.g. the report required by Condition B.3 of TR 13.3.31 is not submitted within 14 days).
The ITRM does not have a Section similar to Technical Specification LCO 3.0.6.
Technical Specification LCO 3.0.6 provides entry into the Safety Function Determination Program (SFDP). The SFDP is not directly applied to the Technical Requirements Manual. However, TRM requirements may result in inoperable items which either
Ching) Descriptions for TRM R vision 29 Attachment 1 to TXX-99202 Page 7 of 40 support a parent Technical Specification (e.g. TR 13.3.1, " Reactor Trip System (RTS) instrumentation Response Times.") or provide directions to declare the associsted item inoperable and enter the applicable Technical Specification (e.g. TR 13.7.31, " Steam Generator Atmospheric Relief Valve (ARV)- Air Accumulator Tank").
Change Request # TR-97-009.3 ITRM # 13.1.31 Boration Flow Path - Operating ITS Reference # -
ITS Change # 3/4.1, 7-01-R CTS # 3/4.1.2.2 CTRM # -
Description of change:
ITS Change # 7-01-R:
The CTS 3.1.2.2, Operating Boration Flow Path and associated SR 4.1.2.2 are relocated to a licensee controlled document. This is consistent with NUREG-1431. The boration subsystem of the chemical and volume control system (CVCS) provides the means to meet one of the functional requirements of the CVCS, i.e., to control the chemical neutron absorber (boron) concentration in the RCS and to help control the boron concentration to maintain shutdown margin (SDM). To accomplish this functional requirement, the boration systems TS require a source of borated water, one or more flow paths to inject this borated water into the reactor coolant system (RCS), and appropriate charging pumps to provide the necessary charging head.
This proposed TS revision relocates requirements, which do not meet the TS criteria in 10CFR50.36(c)(2)(ii), to documents with established control programs.
This regulation addresses the scope and purpose of TS. In doing so, it sets forth a specific set of objective criteria for determining which regulatory requirements and operating restrictions should be included in the TS. Relocation of these requirements allows the TS to be reserved only for those conditions or limitations upon reactor operation which are necessary to obviate the possibllity of an abnormal situation or event giving rise to an immediate threat to the public health and safety thereby focusing the scope of the TS. An evaluation of the applicability of these criteria to this specification is provided in Attachment 21.
To ensure an appropriate level of control, these requirements will be relocated to
- 1) documents that are subject to the provisions of 10 CFR 50.59,2) other licensee documents which have similar regulatory controls (e.g., the Quality Assurance Plan, as described in the FSAR, which is controlled by 10CFR50.54a),
or 3) to programs that are controlled via the Administrative Controls section of the improved TS. The identification of the specific licensee controlled document containing this requirement is provided in Enclosure 3B of the conversion submittal.
Compliance with the relocated requirements will not be affected by this proposed l change to the current Technical Specifications. The required periodic
e
.Ching) D:scriptions for TRM R:: vision 29 Attachment 1 to TXX-99202 Page 8 of 40 surveillances will continue to be performed to ensure that limits on parameters are maintairsed. Therefore, relocation of these requirements will have no impact ;
on system operability or the maintenance of controlled parameters within limits. l l
Condition D was added to ITRM 13.1.31 to incorporate shutdown requirements from CTS 3.0.3.
BASES:
The CTS BASES Section 3/4.1.2, *Boration Systems," is relocated to ITRM BASES 13.1.31, "Boration Flow Path - Operating". ITRM BASES Sections 13.1.32 thru 13.1.33 refer to TRB 13.1.31. l Change Request # TR-97-009.4 ITRM # 13.1.32 Boration Flow Path - Shutdown ITS Reference # -
ITS Change # 3/4.1, 6-01-R CTS # 3/4.1.2.1 CTRM # -
Description of change:
i ITS Change # 6-01 R:
The CTS 3.1.2.1, Shutdown Boration Flow Path and associated SR 4.1.2.1 are relocated to a licensee controlled document. This is consistent with NUREG- '
1431. The boration subsystem of the chemical and volume control system (CVCS) provides the means to meet one of the functional requirements of the CVCS, i.e., to control the chemical neutron absorber (boron) concentration in the RCS and to help control the boron concentration to maintain shutdown margin (SDM). To accomplish this functional requirement, the boration systems TS require a source of borated water, one or more flow paths to inject this borated water into the reactor coolant system (RCS), and appropriate charging pumps to provide the necessary charging head.
This proposed TS revision relocates requirements, which do not meet the TS criteria in 10CFR50.36(c)(2)(ii), to documents with established control programs.
This regulation addresses the scope and purpose of TS. In doing so, it sets forth a specific set of objective criteria for determining which regulatory requirements and operating restrictions should be included in the TS. Relocation of these requiraments allows the TS to be reserved only for those conditions or limitations upon reactor operation which are necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety thereby focusing the scope of the TS. An evaluation of the applicability of these criteria to this specification is provided in Attachment 21.
To ensure an appropriate level of control, these requirements will be relocated to
- 1) documents that are subject to the provisions of 10 CFR 50.59,2) other licensee documents which have similar regulatory controls (e.g., the Quality
Chings D:scriptions for TRM R: vision 29 Attachment 1 to TXX-99202 Page 9 of 40 Assurance Plan, as described in the FSAR, which is controlled by 10CFR50.54a),
or 3) to programs that are controlled via the Administrative Controls section of the improved TS. The identification of the specific licensee controlled document containing this requirement is provided in Enclosure 3B of the conversion submittal.
Compliance with the relocated requirements will not be affected by this proposed change to the current Technical Specifications. The required periodic surveillances will continue to be performed to ensure that limits on parameters are maintained. Therefore, relocation of these requirements will have no impact on system operability or the maintenance of controlled parameters within limits.
BASES:
See description for Change Request Number TR-97-009.3.
Change Request # TR-97-009.5 ITRM # 13.1.33 Charging Pump - Operating ITS Reference # -
ITS Change # 3/4.1, 9-01-R CTS # 3/4.1.2.4 CTRM # -
Description of change:
ITS Change # 9-01-R:
The CTS 3.1.2.4, Lperating Charging Pump and associated SRs 4.1.2.4.1 and 4.1.2.4.2 are relocated to a licensee controlled document. This is consistent with NUREG-1431. The charging pumps are components within the Boration System.
The function o the Boration System is to ensure that negative reactivity control is available during each mode of facility operation.
This proposed TS revision relocates requirements, which do not meet the TS criteria in 10CFR50.36(c)(2)(in, to documents with established control programs.
This regulation addresses the scope and purpose of TS. In doing so, it sets forth a specific set of objective criteria for determining which regulatory requirements and operating restrictions should be included in the TS. Relocation of these requirements allows the TS to be reserved only for those conditions or limitations upon reactor operation which are necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety thereby focusing the scope of the TS. An evaluation of the applicability of these criteria to this specification is provided in Attachment 21.
To ensure an appropriate level of control, these requirements will be relocated to
- 1) documents that are subject to the provisions of 10 CFR 50.59,2) other licensee documents which have similar regulatory controls (e.g., the Quality Assurance Plan, as described in the FSAR, which is controlled by 10CFR50.54a),
or 3) to programs that are controlled via the Administrative Controls section of the
Ch:nga Descriptions for TRM R:; vision 29 Attachm:nt 1 to TXX-99202 Page 10 of 40 improved TS. The identification of the specific licensee controlled document containing this requirement is prov!nd in Enclosure 3B of the conversion submittal.
Compliance with the relocated requirements will not be affected by this proposed change to the current Technical Specifications. The required periodic surveillances will continue to be performed to ensure that limits on parameters are maintained. Therefore, relocation of these requirements will have no impact on system operability or the maintenance of controlled parameters within limits.
Condition C was added to ITRM 13.1.33 to incorporate shutdown requirements from CTS 3.0.3.
BASES:
See description for Change Request Number TR-97-009.3.
Change Request # TR-97-009.6 ITRM # 13.1.34 Charging Pump - Shutdown ITS Reference # - l ITS Change # 3/4.1, 8-01-R l' CTS # 3/4.1.2.3 CTRM # -
I Description of change:
ITS Change # 8-01-R: j j
The CTS 3.1.2.3, Shutdown Charging pump and associated SRs 4.1.2.3.1 and 4.1.2.3.2 are relocated to a licensee controlled document. This is consistent with NUREG-1431. The charging pumps are components within the Boration System.
The function of the Boration System is to ensure that negative reactivity control is available during each mode of facility operation.
This proposed TS revision relocates requirements, which do not meet the TS criteria in 10CFR50.36(c)(2)(ii), to documents with established control programs. ,
This regulation addresses the scope and purpose of TS. In doing so, it sets forth I a specific set of objective criteria for determining which regulatory requirements l and operating restrictions should be included in the TS. Relocation of these l requirements allows the TS to be reserved only for those conditions or limitations upon reactor operation which are necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health '
and safety thereby focusing the scope of the TS. An evaluation of the applicability of these criteria to this specification is provided in Attachment 21.
To ensure an appropriate level of control, these requirements will be relocated to
- 1) documents that are subject to the provisions of 10 CFR 50.59,2) other licensee documents which have similar regulatory controls (e.g., the Quality Assurance Plan, as described in the FSAR, which is controlled by 10CFR50.54a),
Changs Descriptions for TRM Rsvision 29 Attachment 1 to TXX-99202 Page 11 of 40 or 3) to programs that are controlled via thc Administrative Controls section of the improved TS. The identification of the specific licensee controlled document containing this requirement is provided in Enclosure 3B of the conversion submittal.
Compliance with the relocated requirements will not be affected by this proposed change to the current Technical Specifications. The required periodic surveillances will continue to be performed to ensure that limits on parameters are maintained. Therefore, relocation of these requirements will have no impact on system operability or the maintenance of controlled parameters within limits.
BASES:
i See description for Change Request Number TR-97-009.3. I 1
Change Request # TR-97-009.7 ITRM # 13.1.35 Borated Water sources - Operating i ITS Reference # -
ITS Change # 3/4.1,11-01-R CTS # 3/4.1.2.6 CTRM # -
Description of change:
ITS Change # 11-01-R:
The CTS 3.1.2.6, Operating Borated Water Source and associated SR 4.1.2.6 i are relocated to a licensee controlled document. This is consistent with NUREG- l 1431. The borated water source is a component within the Boration System. )
The function of the Boration System is to ensure that negative reactivity control is available during each mode of facility operation.
This proposed TS revision relocates requirements, which do not meet the TS criteria in 10CFR50.36(c)(2)(ii), to documents with established control programs.
This regulation addresses the scope and purpose of TS. In doing so, it sets forth a specific set of objective criteria for determining which regulatory requirements and operating restrictions should be included in the TS. Relocation of these requirements allows the TS to be reserved only for those conditions or limitations upon reactor operation which are necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety thereby focusing the scope of the TS. An evaluation of the applicability of these criteria to this specification is provided in Attachment 21.
To ensure an appropriate level of control, these requirements will be relocated to
- 1) documents that are subject to the provisions of 10 CFR 50.59,2) other licensee documents which have similar regulatory controls (e.g., the Quality Assurance Plan, as described in the FSAR, which is controlled by 10CFR50.54a),
or 3) to programs that are controlled via the Administrative Controls section of the improved TS. The identification of the specific licensee controlled document
Changa D:scriptions for TRM Rsvision 29 Atta :hm:nt 1 to TXX-99202 Page 12 of 40 containing this requirement is provided in Enclosure 3B of the conversion submittal.
Compliance with the relocated requirements will not be affected by this proposed change to the current Technical Specifications. The required periodic surveillances will continue to be performed to ensure that limits on parameters are maintained. Therefore, relocation of these requirements will have no impact on system operability or the maintenance of controlled parameters within limits.
Condition E was added to ITRM 13.1.35 to incorporate shutdown requirements from CTS
3.0.3. BASES
See description for Change Request Number TR-97-009.3.
Change Request # TR-97-009.8 ITRM # 13.1.36 Borated Water Sources - Shutdown ITS Reference # -
ITS Change # 3/4.1,10-01-R CTS # 3/4.1.2.5 CTRM # -
Description of change:
ITS Change # 10-01-R:
The CTS 3.1.2.1, Shutdown Borated Water Source and associated SR 4.1.2.5 are relocated to a licensee controlled document. This is consistent with NUREG-1431. The borated water source is a component within the Boration System.
The function of the Boration System to ensure that negative reactivity control is available during each mode of facility operation.
This proposed TS revision relocates requirements, which do not meet the TS criteria in 10CFR50.36(c)(2)(ii), to documents with estabiished control programs.
This regulation addresses the scope and purpose of TS. In doing so, it sets forth a specific set of objective criteria for determining which regtllatory requirements and operating restrictions should be included in the TS. Relocation of these requirements allows the TS to be reserved only for those conditions or limitations upon reactor operation which are necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety thereby focus:ng the scope of the TS. An evaluation of the applicability of these criteria to this specification is provided in Attachment 21.
To ensure an appropriate level of control, these requirements will be relocated to
- 1) documents that are subject to the provisions of 10 CFR 50.59,2) other licensee documents which have similar regulatory controls (e.g., the Quality Assurance Plan, as described in the FSAR, which is controlled by 10CFR50.54a),
or 3) to programs that are controlled via the Administrative Controls section of the
r Chinga D::scriptions for TRM R: vision 29 Attachm:nt 1 to TXX-99202 Page 13 of 40 improved TS. The identification of the specific licensee controlled document containing this requirement is provided in Enclosure 3B of the conversion submittal.
Compliance with the relocated requirements will not be affected by this proposed change to the current Technical Specifications. The required periodic surveillances will continue to be performed to ensure that limits on parameters are maintained. Therefore, relocation of these requirements will have no impact on system operability or the maintenance of controlled parameters within limits.
BASES:
See description for Change Request Number TR-97-009,3.
]
Change Request # TR-97-009.9 ITRM # 13.1.37 Rod Group Alignment Limits and Rod Position Indicator ITS Reference # 3.1.4, 3.1.7 ITS Change # 3/4.1,12-16-LG CTS # 4.1.3.1.1, 4.1.3.2 i CTRM # -
Description of Change:
ITS Change # 12-16-LG:
Several surveillances (e.g., rod position deviation monitor and rod insertion limit monitor in this section) contain actioas in the form of increased surveillance frequency to be performed in the event of inoperable alarms. These actions are moved from the TS to licensee controlled documents since the alarms do not themselves directly relate to the limits. This detail is not required to be in the TS to provide adequate protection of the public health and safety. Therefore, moving this detail is acceptable and is consistent with traveler TSTF-110.
This technical requirement was developed from a specific item out of an existing Technical Specification (i.e. CTS 4.1.3.1.1,4.1.3.2). This item can not stand alone, therefore a technical requirement LCO, Applicability, Actions, and Surveillances, and Bases were created as required.
BASES:
Added a reference to related information in Technical Specification Bases Section 3.1.4.
Change Request # TR-97-009.10 ITRM # 13.1.38 Control Bank Insertion Limits ITS Referer-ce #
. 3.1.6 ITS Change # 3/4.1,12-16-LG CTS # 4.1.3.6 CTRM # -
Chings Drscriptions for TRM Rsvision 29 Attachm:nt 1 to TXX-99202 Page 14 of 40 Change
Description:
ITS Change # 12-16-LG:
Several surveillances (e.g., rod position deviation monitor and rod insertion limit monitor in this section) contain actions in the form of increased surveillance frequency to be performed in the event of inoperable afarms. These actions are moved from the TS to licensee controlled documents since the alarms do not themselves directly relate to the limits. This detailis not required to be in the TS to provide adequate protection of the public health and safety. Therefore, moving this detail is acceptable and is consistent with traveler TSTF-110.
This technical requirement was developed from a specific item out of an existing Technical Specification (i.e. CTS 4.1.3.6). This item can not stand alone, therefore a technical requirement LCO, Applicability, Actions, and Surveillances, and Bases were created as required.
BASES:
Added a reference to related information in Technical Specification Bases Section 3.1.6.
l l
Change Request # TR-97-009.11 !
ITRM # 13.1.39 Rod Position Indication - Shutdown l ITS Reference # -
ITS Change # 3/4.1,14-01-R; 3/4.10, 5-02-M CTS # 3/4.1.3.3, 3/4.10.5, TSI-006-RO j CTRM # -
Description of Change:
ITS Change # 14-01-R:
Shutdown Position Indication System specification 3.1.3.3 is relocated to a licensee controlled document. This is consistent with NUREG-1431 Rev.1. The Digital Rod Position Indicadon System is used for verification of agreement with demanded position.
This proposed TS revision relocates requirements, which do not meet the TS criteria in 10CFR50.36(c)(2)(ii), to documents with established control programs.
This regulation addresses the scope and purpose of TS. In doing so, it sets forth a specific set of objective criteria for determining which regulatory requirements and operating restrictions should be included in the TS. Relocation of these requirements allows the TS to be reserved only for those conditions or limitations upon reactor operation which are necessary to obviate the possibility of an l abnormal situation or event giving rise to an immediate threat to the public health j and safety thereby focusing the scope of the TS. An evaluation of the applicability of these criteria to this specification is provided in Attachment 21. I
r 1 Chinga D scriptions for TRM R: vision 29 Attachment 1 to TXX-99202 !
Page 15 of 40
]
To ensure an appropriate level of control, these requirements will be relocated to
- 1) documents that are subject to the provisions of 10 CFR 50.59,2) other licensee documents which have similar regulatory controls (e.g., the Quality Assurance Plan, as described in the FSAR, which is controlled by 10CFR50.54a),
or 3) to programs that are controlled via the Administrative Controls section of the improved TS. The identification of the specific licensee controlled document 3
containing this requirement is provided in Enclosure 3B of the conversion J
submittal.
Compliance with the relocated requirements will not be affected by this proposed change to the current Technical Specifications. The required periodic j surveillances will continue to be performed to ensure that limits on parameters are maintained. Therefore, relocation of these requirements will have no impact on system operability or the maintenance of controlled parameters within limits.
ITS Change # 5-02-M:
Special Test Exception LCO 3.10.5
- Position Indication System Shutdown",
would be deleted based on relocation of LCO 3.1.3.3,
- Position Indicating Systems - Shutdown." NRC application of TS Criteria concluded that the STE LCOs could be included with corresponding LCOs remaining in TS and thus LCO 3.10.5 is no longer necessary.
Condition B was added to ITRM 13.1.39 to incorporate shutdown requirements from CTS
3.0.3. BASES
Added a reference to related information in Technical Specification BASES Section 3.1.7. Technical Specification Interpretation 006, Revision 0, is relocated verbatim to ITRM BASES 13.1.39, " Rod Position Indication - Shutdown."
Change Request # TR-97-009.12 ITRM # 13.2.31 Moveable incore Detection System ITS Reference # -
ITS Change # -
CTS # -
CTRM # 1.3 Description of Change:
Changed the existing Technical Requirement to the new ITS format.
BASES:
CTRM Bases information relocated verbatim.
Change Request # TR-97-009.13
Change Descriptions for TRM R:; vision 29 Attachment 1 to TXX 99202 Page 16 of 40 ITRM # 13.2.32 Axial Flux Difference (AFD)
ITS Reference # 3.2.3 ITS Change # 3/4.2, 01-07-LG CTS # 4.2.1.1.a2,b CTRM # -
Description of Change:
ITS Change # 01-07-LG:
As described in industry traveler TSTF-110 which modifies NUREG-1431 requirements, several surveillances contain actions (in the form of increased surveillance frequency) to be performed in the event of inoperable alarms. These actions are moved from the TS to licensee controlled documents. The alarms themselves do not directly relate to the LCO limits. This detail is not required to be in the TS to provide adequate protection of the public health and safety.
Timrefore, moving this detail is acceptable.
This technical requirement was developed from a specific item out of an existing Technical Specification (i.e. CTS 4.2.1.1.a2,b). This item can not stand alone, therefore a technical requirement LCO, Applicability, Actions, and Surveillances, and Bases were created as required.
BASES:
Added a reference to related information in Technical Specification Bases Section 3.2.3. !
1 Change Request # TR-97-009.14 j ITRM # 13.2.33 Quadrant Power Tilt Ratio (OPTR) Alarm '
ITS Reference # 3.2.4 ITS Change # 3/4.2, 01-07-LG CTS # 4.2.4.1 b CTRM # -
Description of Change:
ITS Change # 01-07-LG:
As described in industry traveler TSTF-110 which modifies NUREG-1431 requirements, several surveillances contain actions (in the form of increased surveillance frequency) to be performed in the event of inoperable alarms. These actions are moved from the TS to licensee controlled documents. The alarms themselves do not directly relate to the LCO limits. This detail is not required to ,
be in the TS to provide adequate protection of the public health and safety.
Therefore, moving this detail is acceptable.
This technical requirement was developed from a specific item out of an existing Technical Specification (i.e. CTS 4.2.4.1.b). This item can not stand alone, therefore a technical requirement LCO, Applicability, Actions, and Surveillances, and Bases were L
c
)
Chinge Descriptions for TRM R3 vision 29 Attachment 1 to TXX-99202 Page 17 of 40 created as required.
BASES:
Added a reference to related information in Technical Specification Bases Section 3.2.4.
Change Request # TR-97-009.15 ITRM # 13.3.1 Reactor Trip System (RTS) instrumentation Response Times ITS Reference # 3.3.1 ITS Change # -
CTS # 3/4.3.1 CTRM # 1.1 Description of Change:
Changed the CTRM Bases Technical Requirement to the new ITS format and to support the time limits associated with Technical Specification SR 3.3.1.16 and the applicable Functions in Technical Specification Table 3.3.1-1.
BASES: )
l Existing information relocated verbatim. I Change Request # TR-97-009.16 .
ITRM # 13.3.2 Engineered Safety Feature Actuation System (ESFAS)
Instrumentation Response Times '
ITS Reference # 3.3.2 '
ITS Change # -
CTS # 3/4.3.2; 4.7.1.2.c.1; B3/4.7.1.2 CTRM # 1.2 1 1
Description of Change:
Changed the existing Technical Requirement to the new ITS format and to support the time limits associated with Technical Specification SR 3.3.2.10 and the applicable Functions in Technical Specification Table 3.3.2-1.
BASES:
CTRM Bases information relocated verbatim.
Change Request # ' TR-97-009.17 ITRM # 13.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation Response Times ITS Reference # 3.3.5 ITS Change # -
CTS # 3/4.3.2
Ch:ng] De:criptions for TRM R: vision 29 Attachment 1 to TXX-99202 Page 18 of 40 CTRM # 1.2 Description of Change:
Changed the existing Technical Requirement to the new ITS format and to support the time limits associated with Technical Specificatioa SR 3.3.5.4 and the applicable functions in Technical Specification Table 3.3.5-1.
BASES: {
CTRM Bases information has been relocated.
Change Request # TR-97-009.18 1 ITRM # 13.3.31 Seismic Instrumentation ITS Reference # -
ITS Change # -
CTS # -
CTRM # 1.4 Description of Change:
Changed the existing Technical Requirement to the new ITS format.
BASES:
CTRM Bases information relocated verbatim.
Change Request # TR-97-009.19 ITRM # 13.3.32 Source Range Neutron Flux ITS Reference # -
ITS Change # 3/4.3,1-38-R CTS # T3.3-1, 6.a.2 CTRM # -
Description of Change:
ITS Change # 1-38-R:
In MODES 3,4, and 5 when all control rods are fully inserted and the Rod Control System is incapable of rod withdrawal, the source range neutron flux function does not provide input to any reactor trip function nor is it credited for mitigation of any analyzed event. (At one time, the source range neutron flux signal was credited in the analysis of the inadvertent boron dilution event; however, as described in a previous license amendment [20/06), this analysis was revised to credit other alarms.) Because the source range neutron flux function in these conditions does not satisfy any of the four criteria of 10CFR50.36(c)(2)(ii), it is being deleted from the Technical Specifications. However, the operation of this function will continue to be maintained through plant procedures as it does
Ching3 D:scriptions for TRM Rmvision 29 Attachm:nt 1 to TXX-99202 1 Page 19 of 40 provide important alternate indication to the reactor operators. f I
This technical requirement was developed from a specific item out of an existing Technical Specification (i.e. CTS Table 3.3-1,6.a.2). This item can not stand alone, therefore a technical requirement LCO, Applicability, Actions, and Surveillances, and Bases were created as required.
BASES:
Added a reference to related information in Technical Specification Bases Section 3.3.1.
Change Request # TR-97-009.20 ITRM # 13.3.33 Turbine Overspeed Protection ITS Reference # -
ITS Change # 3/4.3,10-01-R CTS # 3/4.3.4 CTRM # -
Description of Change:
ITS Change # 10-01-R:
The Turbine Overspeed Protection System is relocated to a licensee controlled document.
Condition D was added to ITRM 13.3.33 to incorporate shutdown requirements from CTS 3.0.3 BASES:
The CTS BASES Section 3/4.3.4," Turbine Overspeed Protection,"is relocated verbatim to ITRM BASES 13.3.33," Turbine Overspeed Protection".
Change Request # TR-97-009.21 ITRM # 13.4.14 RCS Pressure Isolation Valves ITS Reference # 3.4.14 ITS Change # 3/4.4, 6-07-LG CTS # 3.4.5.2.f, 4.4.5.2.2, T3.4-1 CTRM # -
Description of Change:
ITS Change # 6-07-LG:
This change moves the listing of RCS Pressure Isolation Valves to a licensee controlled document as identified in the Conversion Comparison Table (enclosure 38). Moving this information is consistent with the NUREG-1431 philosophy of moving clarifying information and descriptive details out of the TS. The requirement to verify PlV leakage is moved to SR 3.4.14.1 in the improved TS.
Chinge Descriptions for TRM R; vision 29 Attachm:nt 1 to TXX-99202 Page 20 of 40 BASES:
Added a reference to related information in Technical Specification Bases Section 3.4.14.
Change Request # TR 97-009.22 ITRM # 13.4 31 Loose Parts Detection System ITS Reference # -
ITS Change # -
CTS # -
CTRM # 1.5 Description of Change:
Changed the existing Technical Requirement to the new ITS format.
BASES:
CTRM Bases information relocated verbatim.
Change Request # TR-97-009.23 ITRM # 13.4.32 Pressurizer Power Operated Relief Valves (PORVs)
ITS Reference # 3.4.11 ITS Change # 3/4.4, 4-04-LG CTS # 4.4.4.1.b, B3/4.4.4 CTRM # -
Description of Change:
ITS Change # 4-04-LG:
The automatic actuation of the PORVs is not credited in MODES 1,2, or 3.
Therefore performance of the channel calibration is unnecessary as a TS requirement and is moved to a licensee controlled document The portions of the PORV actuation circuitry required for [LTOP] are calibrated in accordance with improved TS SR 3.4.12.9. Moving this information is consistent with the NUREG-1431 philosophy of moving requirements, which are not required to satisfy accident analyses, out of tiie TS.
This technical requirement was developed from a specific item out of an existing Technical Specification (i.e. CTS 4.4.4.1.b, B3/4.4.4). This item can not stand alone, therefore a technical requirement LCO, Applicability, Actions, and Surveillances, and Bases were created as required.
BASES:
Added a reference to related information in Technical Specification Bases Section 3.4.11. Also relocated a paragraph from the CTS BASES 3/4.4.4," Relief Valves," which discusses the automatic circuitry.
l l
Change Descriptions for TRM R:: vision 29 Attachment 1 to TXX-99202 Page 21 of 40 Change Request # TR-97-009.24 ;
ITRM # 13.4.33 Reactor Coolant System (RCS) Chemistry j ITS Reference # -
ITS Change # 3/4.4, 7-01-R l CTS # 3/4.4.6 l CTRM # -
l Description of Change:
ITS Change # 7-01-R:
This change in conformance with NUREG-1431 Rev.1, removes the reactor coolant system chemistry specification from the Technical Specifications. The limits and required actions on reactor coolant system chemistry is being relocated to a licensee controlled document.
BASES:
The CTS BASES Section 3/4.4.6," Chemistry,"is relocated verbatim to ITRM BASES 13.4.33, " Chemistry".
Change Request # TR-97-009.25 ITRM # 13.4.34 Pressurizer j ITS Reference # -
ITS Change # 3/4.4, 9-05-R CTS # 3/4.4.8.2 CTRM # -
Description of Change:
ITS Change # 9-05-R:
This change in conformance with NUREG-1431 Rev.1, removes the pressurizer I specification from the Technical Specifications. The limits for the pressurizer will be relocated a licensee controlled document as identified in the Conversion Comparison Table (enclosure 3B)
Condition C was added to ITRM 13.4.34 to incorporate shutdown requirements from CTS 3.0.3.
BASES:
The applicable discussion related to the pressurizer is relocated from CTS BASES Section 3/4.4.8,
- Pressure / Temperature Limits," to ITRM BASES 13.4.34,
- Pressurizer".
Change Request # TR-97-009.26 ITRM # 13.4.35 Reactor Coolant System (RCS) Vents Specification ITS Reference # -
I
r 1 Change Descriptions for TRM R; vision 29 Attachment 1 to TXX-99202 Prge 22 of 40 l ITS Change # 3/4.4,11-01-R CTS # 3/4.4.10 CTRM # -
Description of Change:
ITS Change # 11-01-R:
This change in conformance with NUREG-1431 Rev.1, removes the reactor coolant system vents specification from the Technical Specifications. The requirements for the reactor coolant system vents will be relocated to a licensee controlled document as identified in the Conversion Comparison Table (enclosure 3B).
BASES:
The CTS BASES Section 3/4.4.10," Reactor Coolant System Vents," is relocated verbatim to ITRM BASES 13.4.35,
- Reactor Coolant System (RCS) Vents Specification".
Change Request # TR-97-009.27 ITRM # 13.5.31 ECCS - Containment Debris ITS Reference # 3.5.2, 3.5.3 ITS Change # 3/4.5, 2-09-LG CTS # 4.5.2.c-CTRM # -
Description of Change:
ITS Change # 2-09-LG:
The visual inspection surveillance performed when establishing containment integrity is moved to a licensee controlled document. CTS SR 4.5.2.c requires a visual inspection to verify that no loose debris is present in the containment which could be transported to the containment sump and cause restriction to the pump suction during LOCA conditions at the frequency specified. This ensures that during the process of performing maintenance or other work inside containment that debris is appropriately discarded. Existing procedures restrict containment entries and assure accountability of items entering containment such that they are removed at the completion of the containment entry. ITS SR 3.5.2.8 continues to require a visual inspection every 18 months on each of the ECCS train containment sump suction inlets to ensure that the sump suction inlet is not restricted by debris. Therefore, this detail is not required to be in the technical specifications and moving this requirement maintains consistency with NUREG-1431. '
This technical requirement was developed from a specific item out of an existing Technical Specification (i.e. CTS 4.5.2.c). This item can not stand alone, therefore a technical requirement LCO, Applicability, Actions, and Surveillances, and Bases were created as required.
Ching:) Descriptions for TRM R; vision 29 Att chment 1 to TXX-99202 Page 23 of 40 ;
I BASES:
Added a reference to related information in Technical Specification Bases Section 3.5.2 and 3.5.3.
Change Request # TR-97-009.28 ITRM # 13.5.32 ECCS - Pump Line Flow Rates ITS Reference # 3.5.2, 3.5.3 l iTS Change # 3/4.5, 2-15-LG f CTS # 4.5.2.h i CTRM # -
Description of Change:
ITS Change # 2-15 LG:
The surveillance requirement for the flow balance test following ECCS modifications is moved to a licensee controlled document. This requirement is not included in NUREG-1431. Plant procedures governing the restoration of equipment after maintenance specify the requirements for determining the appropriate post-maintenance testing. Any time the Operability of a system or component has been affected by repair, maintenance, or replacement of a component, post-maintenance testing is required to demonstrate Operability of the system or component. As such, the requirement to perform a flow balance test after modifications that alter ECCS subsystem flow characteristics is not required to be in the TS to provide adequate protection of the public health and safety. This requirement has been moved to the [F]SAR (for Callaway, Diablo Canyon, and Wolf Creek) or TRM (Comanche Peak). These licensee controlled documents containing the moved requirements will be maintained using the provisions of 10 CFR 50.59. Therefore, the descriptive information that has been moved continues to be maintained in an appropriately controlled manner.
This technical requirement was developed from a specific item out of an existing Technical Specification (i.e. CTS 4.5.2.h). This item can not stand alone, therefore a technical requirement LCO, Applicability, Actions, and Surveillances, and Bases were created as required.
BASES:
Added a reference to related information in Technical Specification Bases Section 3.5.2 and 3.5.3.
Change Request # TR-97-009.29 ITRM # 13.6.3 Containment Isolation Valves ITS Reference # 3.6.3 ITS Change # -
CTS # 3/4.6.3 CTRM # 2.1 l
I
Chang] D:scriptions for TRM R: vision 29 Attachm:nt 1 to TXX-99202 Page 24 of 40 Description of Change:
Changed the existing Technical Requirement to the new ITS format and to support the isolation time limits associated with Technical Specification 3.6.3 and SR 3.6.3.5.
BASES:
CTRM Bases information ro!ocated verbatim.
Change Request # TR-97-009.30 ITRM # 13.6.6 Contninment Spray System ITS Reference # 3.6.6 ITS Change # -
CTS # 3/4.6.2.1 CTRM # 2.2 Description of Change:
Relocated the existing Technical Requirement of the Containment Spray Purnp to the new ITRM Section and noted the new ITS Reference (SR 3.6.6.4).
BASES:
Added a reference to related information in Technical Specification Bases Section 3.6.6.
Change Request # TR-97-009.31 ITRM # 13.6.31 Hydrogen Recombiners - Instrumentation and Control Circuits ITS Reference # 3.6.8 {
ITS Change # 3/4.6,13-04-LG CTS # 4.6.4.2.b.1 CTRM # -
4 1
Description of Change:
ITS Change # 13-04-LG:
The surveillance requirement to perform a Channel calibration on all the hydrogen recombiner instrumentation is moved to a licensee controlled document. These calibrations and any necessary compensatory measures (i.e.,
substitute test instrumentation) will be controlled administra'ively by the plant preventive maintenance and operational procedures. This change is acceptable based on the system redundancy, available alternate means of controlling hydrogen, the fact the recombiners are controlled manually, and the instrumentation does not provide essential control or interlock function. In addition the functional test required by the TS every [18) months verifies the operation of the hydrogen recombiner instrumentation. This change is consistent :
I with NUREG-1431.
l l
j
Ch nge Descriptions for TRM R: vision 29 Attachment 1 to TXX-99202 Page 25 of 40 This technical requirement was developed from a specific item out of an existing Technical Specification (i.e. CTS 4.6.4.2.b.1). This item can not stand alone, therefore a technical requirement LCO, Applicability, Actions, and Surveillances, and Bases were created as required.
BASES:
Added a reference to related information in TecMical Specification Bases Section 3.6.8.
Change Request # TR-97-009.32 ITRM # 13.7.31 Steam Generator Atmospheric Relief Valves (ARVs)- Air Accumulator Tank ITS Reference # 3.7.4 ITS Change # 3/4.7, 06-06-LG CTS # 4.7.1.7.a CTRM # -
Description of Change:
ITS Change # 06-06-LG:
This change moves the requirements for the surveillance to the Bases. The details of the specific test requirements such as those dealing with the " remote manual controls" are not included in the STS, but are included in the Bases section for the SR. [ Accumulator testing is moved to licensee controlled documents.) This change is acceptable because it removes details from the TS that are not required to protect the health and safety of the public while retaining the basic limiting condition for operation. J l
This technical requirement was developed from a specific item out of an existing l Technical Specification (i.e. CTS 4.7.1.7.a). This item can not stand alone, therefore a technical requirement LCO, Applicability, Actions, and Surveillances, and Bases were created as required.
BASES:
Added a reference to related information in Technical Specification Bases Section 3.7.4.
Change Request # TR-97-009.33 ITRM # 13.7.32 Steam Generator Pressure / Temperature Limitation ITS Reference # -
ITS Change # 3/4.7,14-01-R CTS # 3/4.7.2 ,
CTRM # -
Description of Change: l ITS Change # 14-01-R:
i l
j
Changs D:scriptions 'or TRM Rsvision 29 Attachment 1 to TXX-99202 Page 26 of 40 The Steam Generator Pressure / Temperature Limitation TS is relocated to a licensee controlled document. This change is consistent with NUREG-1431 since this specification is not included in the ISTS.
BASES:
The CTIBASES Section 3/4.7.2, " Steam Generator Pressure / Temperature Limitation,"
is relocated verbatim to ITRM BASES 13.4.35, " Steam Generator Pressure /
Temperature Limitation" Change Request # TR-97-009.34 ITRM # 13.7.33 Ultimate Heat Sink - Sediment and SSI Dam ITS Reference # 3.7.9 3/4.7,13-03-R {
ITS Change #
CTS # 3.7.5.c, ACTION b,4.7.5.b,c CTRM # -
Description of Change:
ITS Change # 13-03-R:
s The LCO for sedimentation depth and the Surveillance Requirements for SSI Dam inspections and for sedimentation depths are relocated to a licensee controlled document.
' This technical requirement was developed from a specific item out of an existing Technical Specification (i.e. CTS 3.7.5.c, ACTION b,4.7.5.b,c). This item can not stand alone, therefore a technical requirement LCO, Applicability, Actions, and Surveillances, and Bases were created as required.
BASES: I i
The applicable discussion related to the SSI Dam is relocated from CTS BASES Section 3/4.7.5, " Ultimate Heat Sink," to ITRM BASES 13.7.33, "Ulitimate Heat Sink - Sediment and Safe Shutdown impoundment (SSI) Dam".
)
i Change Request # TR-97-009.35 l ITRM # 13.7.34 Flood Protection ITS Reference # -
ITS Change # 3/4.7,15-01-R CTS # 3/4.7.6 CTRM # -
Description of Change:
ITS Change # 15-01-R:
The Flood Protection TS is relocated to a licensee controlled document. This change is consistent with NUREG-1431 since this specification is not included in
Ch nge Descriptions for TRM Rsvision 29 Attachment 1 to TXX-99202 Page 27 of 40 the ISTS.
Condition A of ITRM 13.4.34 was modified to incorporate shutdown requirements from CTS 3.0.3.
l BASES:
The CTS BASES Section 3/4.7.6," Flood Protection,"is relocated verbatim to ITRM BASES 13.7.34," Flood Protection".
Change Request # TR-97-009.36 l ITRM # 13.7.35 Snubbers l ITS Reference # various ITS Change # 3/4.7,16-01-R CTS # 3/4.7.9 CTRM # 3.1 l Description of change:
l l ITS Change # 16-01-R: ,
l w l The Snubbers TS is relocated to a licensee controlled document. This change is consistent with NUREG-1431 since this specification is not included in the ISTS l
BASES:
The CTS BASES Section 3/4.7.9," Snubbers,"is relocated verbatim to ITRM BASES 13.7.35, " Snubbers". j Change Request # TR-97-009.37 I ITRM # 13.7.36 Area Temperature Monitoring l ITS Reference # -
ITS Change # 3/4.7,17-01-R I
CTS # 3/4.7.10 CTRM # -
l J
l Description of Change:
ITS Change # 17-01-R:
The Area Temperature Monitoring TS is relocated to a licensee controlled l
document. This change is consistent with NUREG-1431 since this specification is not included in the ISTS.
BASES:
The CTS BASES Section 3/4.7.10. " Area Temperature Monitoring,"is relocated verbatim to ITRM BASES 13.7.36," Area Temperature Monitoring".
Change Descriptions for TRM R vision 29 Attachment 1 to TXX-99202 Page 28 of 40 Change Request # TR-97-009.38 ITRM # 13.7.37 Safety Chilled Water System - Electrical Switchgear Area Emergency i an Coil Units ITS Reference # 3.7.19 l
ITS Change # 3/4.7,18-02-LG CTS # 4.7.12.b CTRM # -
Description of change:
ITS Change # 18-02-LG:
The surveillance of the CPSES electrical switchgear area emergency fan coil units is moved to a licensee controlled document. The change is acceptable I
because it removes detail no longer required in the TS to protect the health and safety of the public while retaining the basis limiting condition for operation.
This technical requirement was developed from a specific item out of an existing Technical Specification (i.e. CTS 4.7.12.b). This item can not stand alone, therefore a technical requirement LCO, Applicability, Actions, and Surveillances, and Bases were created as required.
BASES:
Added a reference to related information in Technical Specification Bases Section 3.7.19 and clarified the requirements of ITRM 13.7.37 with respect to Technical Specification 3.7.19.
Change Request # TR-97-009.39 ITRM # _13.7.38 Main Feedwater Isolation Valve Pressure / Temperature Limit ITS Reference # -
l ITS Change # 3/4.7,19-01-R CTS # 3/4.7.13 CTRM # -
l Description of Change:
1 ITS Change # 19-01-R:
The Main Feed Water Pressurefremperature Limit TS is relocated to a licensee controlled document. This change is consistent with NUREG-1431 since this l specification is not included in the ISTS.
l BASES:
l The CTS BASES Section 3/4.7.13, " Main Feedwater isolation Valve Pressure /
. Temperature Limit,"is relocated verbatim to ITRM BASES 13.7.38," Main Feedwater 1
Ch nge Descriptions for TRM R:; vision 29 Attachment 1 to TXX-99202 Page 29 of 40 Isolation Valve Pressure / Temperature Limit".
Change Request # TR-97-009.40 ITRM # 13.7.39 Tomado Missile Shields ITS Reference # various ITS Change # -
CTS # various CTRM # TSI-003-Revision 4 Description of Change:
Changed the existing Technical Specification interpretation (TSI) 003, Revision 4, to the new ITS format.
BASES:
Existing information from TSI-003-R4 relocated to the ITRM BASES 13.7.39.
Change Request # TR-97-009.41 ITRM # 13.7.40 Feedwater Control Valves (FCVs) and Associated Bypass Valves ITS Reference # --
ITS Change # -
CTS # Existing Technical Evaluation CTRM # -
Description of Change:
Added new Technical Requirement based on an existing technical evaluation for the feedwater control valves and associated bypass valves.
BASES:
Bases information to be provided later.
Change Request # TR-97-009.42 ITRM # 13.8.31 AC Sources (Diesel Generator Requirements)
ITS Reference # 3.8.1, 3.8.2 ITS Change # 3/4.8,1-20-LG,1-38-LG,1-39-LG CTS # 4.8.1.1.2.a.6,f.1,8,13,h CTRM # -
Description of Change:
ITS Change # 1-20-LG Several SRs would be moved to licensee-controlled documents. Moving these requirements would allow changes to these requirements without prior Commission approval and will further the Commission's goal of TS
Ch nge Descriptions for TRM Revision 29 Attachm:nt 1 to TXX-99202 Page 30 of 40 improvements, as delineated in NRC policy statements, without reducing the level of plant safety. The SRs that are being moved reflect normal design, maintenance or line-up activities / descriptions rather than features specifically needed to successfully mitigate a DBA or design transient. These proposed changes are consistent with NUREG-1431.
ITS Change # 1-38-LG The fuel oil storage tank cleaning SR would be moved to licensee controlled documents. This change is consistent with NUREG-1431.
ITS Change # 01-39-LG The fuel oil transfer piping leak test SR would be moved to licensee controlled documents. This change is consistent with NUREG-1431.
This technical requirement was developed from a specific item out of an existing Technical Specification (i.e. CTS 4.8.1.1.2.a.6, f.1,8,13, h). This item can not stand alone, therefore a technical requirement LCO, Applicability, Actions, and Surveillances, and Bases were created as required.
BASES:
Added a reference to related information in Technical Specification Bases Section 3.8.1 and clarified the requirements of ITRM 13.8.31.
Change Request # TR-97-009.43 ITRM # 13.8.32 Containment Penetration Conductor Overcurrent Protection Devices ITS Reference # various ITS Change # 3/4.8, 4-01-R CTS # 3/4.8.4 CTRM # 4.1 Description of Change:
ITS Change # 4-01-R:
The Containment Penetration Conductor Overcurrent Protective Devices TS would be relocated to licensee-controlled documents. This change is consistent with NUREG-1431.
BASES:
The CTS BASES Section 3/4.8.4," Electrical Equipment Protective Devices," is relocated verbatim to ITRM BASES 13.8.32, " Containment Penetration Conductor Overcurrent Protection Devices," which captures CTRM Bases Information.
Change Request # TR-97-009.44
n Ch:ngs Descriptions for TRM R: vision 29 Att chment 1 to TXX-99202 Page 31 of 40 ITRM # 13.9.31 Decay Time ITS Reference # -
ITS Change # 3/4.9, 3-01-R CTS # 3/4.9.3 CTRM # -
Description of Change:
ITS Change # 3-01-R:
Consistent with NUREG-1431. Rev.1, the subcriticality requirement prior to irradiated fuel movement is relocated to a licensee controlled document. This CTS requirement ensured that sufficient time had elapsed to allow the radioactive decay of short-lived fission products prior to movement of irradiated fuel. This change is acceptable based on the schedule requirements following shutdown to attain plant conditions for movement of irradiated fuel. These schedule requirements provide assurance that the requirements of the decay time LCO would not be exceeded.
This proposed TS revision relocates requirements, which do not meet the TS criteria in 10CFR50.36(c)(2)(ii), to documents with established control programs.
This regulation addresses the scope and purpose of TS. In doing so, it sets forth a specific set of objective criteria for determining which regu!atory requirements and operating restrictions should be included in the TS. Relocation of these requirements allows the TS to be reserved only for those conditions or limitations upon reactor operation which are necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety thereby focusing the scope of the TS. An evaluation of the applicability of these criteria to this specification is provided in Attachment 21.
To ensure an appropriate level of control, these requirements will be relocated to
- 1) documents that are subject to the provisions of 10 CFR 50.59,2) other licensee documents which have similar regulatory controls (e.g., the Quality Assurance Plan, as described in the FSAR, which is controlled by 10CFR50.54a),
or 3) to programs that are controlled via the Administrative Controls section of the improved TS. The identification of the specific licensee controlled document containing this requirement is provided in Enclosure 3B of the conversion submittal.
Compliance with the relocated requirements will not be affected by this proposed change to the current Technical Specifications. The required periodic surveillances will continue to be performed to ensure that liraits on parameters are maintained. Therefore, relocation of these requirements wi,1 have no impact on system operability or the maintenance of controlled parameters within limits.
BASES:
The CTS BASES Section 3/4.9.3," Decay Time,"is relocated verbatim to ITRM BASES !
13.9.1, " Decay Time".
r Ch nge Descriptions for TRM R: vision 29 Attachment 1 to TXX-99202 Page 32 of 40 i
Change Request # TR-97-009.45 ITRM # 13.9.32 Refueling Operations / Communications ITS Reference # -
ITS Change # 3/4.9, 5-01-R CTS # 3/4.9.5 '
CTRM # -
l Description of Change:
ITS Change # 5-01-R:
I This change relocates the current TS section dealing with maintaining direct communication between the control room and the refueling station to a licensee controlled document as part of the conversion of the current Technical Specification to the format and expanded Bases of the improved Standard Technical Specifications. The specification requires communication between the control room and the refueling station to ensure that any abnormal change in the facility status or core reactivity observed on the control room instrumentation can be communicated to the refueling station personnel during core alterations.
This proposed TS revision relocates requirements, which do not meet the TS criteria in 10CFR50.36(c)(2)(ii), to documents with established control programs.
This regulation addresses the scope and purpose of TS. In doing so, it sets forth a specific set of objective criteria for determining which regulatory requirements and operating restrictions should be included in the TS. Relocation of these requirements allows the TS to be reserved only for those conditions or limitations upon reactor operation which are necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety thereby focusing the scope of the TS. An evaluation of the applicability of these criteria to this specification is provided in Attachment 21.
To ensure an appruriate level of control, these requirements will be relocated to
- 1) documents that ce subject to the provisions of 10 CFR 50.59,2) other licensee documents which have similar regulatory controls (e.g., the Quality Assurance Plan, as described in the FSAR, which is controlled by 10CFR50.54a),
or 3) to programs that are controlled via the Administrative Controls section of the improved TS. The identification of the specific licensee controlled document containing this requirement is provided in Enclosure 3B of the conversion submittal.
Compliance with the relocated requirements will not be affected by this proposed change to the current Technical Specifications. The required periodic surveillances will continue to be performed to ensure that limits on parameters are maintained. Therefore, relocation of these requirements will have no impact on system operability or the maintenance of controlled parameters within limits.
BASES:
p L
Change Descriptions for TRM R: vision 29 ' Attachment 1 to TXX-99202 Page 33 of 40 The CTS BASES Section 3/4.9.5, " Communications," is relocated verbatim to ITRM BASES 13.9.2, " Refueling Operations / Communications".
Change Request # TR-97-009.46 ITRM # 13.9.33 Refueling Machine ITS Reference # -
ITS Change # . 3/4.9, 6-01-R CTS # 3/4.9.6~
CTRM # -
Description of Change:
ITS Change # 6-01-R:
This change relocates the current TS section for the Refueling Machine to a
. licensee controlled document as part of the conversion of the current Technical Specification to the format and expanded Bases of the improved Standard Technical Specifications. The OPERABILITY requirements for the refueling
. machine main hoist and auxiliary monorail hoist ensure that: (1) the main hoist will be used for movement of fuel assemblies, (2) the auxiliary monorail hoist will be used for latching, unlatching and movement of control rod drive shafts, (3) the main hoist has sufficient load capacity to lift a fuel assembly (with control rods),
(4) the auxiliary monorail hoist has sufficient load capacity to latch, unlatch and move the control rod drive shafts, and (5) the core intemals and reactor vessel are protected from excessive lifting force in the event they are inadvertently 4 engaged during lifting operations. I
- This proposed TS revision relocates requirements, which do not meet the TS criteria in 10CFR50.36(c)(2)(ii), to documents with established control programs.
This regulation addresses the scope and purpose of TS. In doing so, it ,ets forth a specific set of objective criteria for determining which regulatory requirements and operating restrictions should be included in the TS. Relocation of these requirements allows the TS to be reserved only for those conditions or limitations upon reactor operation which are necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety thereby focusing the scope of the TS. An evaluation of the applicability of these criteria to this specification is provided in Attachment 21.
To ensure an appropriate level of control, these requirements will be relocated to
- 1) documents that are subject to the provisions of 10 CFR 50.59,2) other licensee documents which have similar regulatory controls (e.g., the Quality
' Assurance Plan, as described in the FSAR, which is controlled by 10CFR50.54a),
or 3) to programs that are controlled via the Administrative Controls section of the
- improved TS. The identification of the specific licensee controlled document containing this requirement is provided in Enclosure 3B of the conversion submittal.
Compliance with the relocated requirements will not be affected by this proposed change to the current Technical Specifications. The required periodic
L l
Ching3 Descriptions for TRM R: vision 29 Attachment 1 to TXX-99202 Page 34 of 40 surveillances will continue to be performed to ensure that limits on parameters are maintained. Therefore, relocation of these requirements will have no impact on system operability or the maintenance of controlled parameters within limits.
BASES:
The CTS BASES Section 3/4.9.6, " Refueling Machine," is relocated verbatim to ITRM i BASES 13.9.33, " Refueling Machine". !
Change Request # TR-97-009.47 ITRM # 13.9.34 Refueling - Crane Travel - Spant Fuel Storage Areas ITS Reference # -
ITS Change # 3/4.9, 7-01-R CTS # 3/4.9.7 CTRM # -
Description of Change:
l ITS Change # 7-01-R:
This change relocates the TS section dealing with crane travel to a licensee controlled document as part of the conversion of the current Technical ,
Specification to the format and expanded Bases of the improved Standard Technical Specifications. The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in a storage pool ensures that in the event this load is dropped: (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the safety analyses.
This proposed TS revision relocates requirements, which do not meet the TS criteria in 10CFR50.36(c)(2)(ii), to documents with established control programs.
This regulation addresses the scope and purpose of TS. In doing so, it sets forth a specific set of objective criteria for determining which regulatory requirement.
and operating restrictions should be included in the TS. Relocation of these requirements allows the TS to be reserved only for those conditions or limitations upon reactor operation which are necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety thereby focusing the scope of the TS. An evaluation of the applicability of these criteria to this specification is provided in Attachment 21.
To ensure an appropriate level of control, these requirements will be relocated to
- 1) documents that are subject to the provisions of 10 CFR 50.59,2) other licensee documents which have similar regulatory controls (e.g., the Quality Assurance Plan, as described in the FSAR, which is controlled by 10CFR50.54a),
or 3) to programs that are controlled via the Administrative Controls section of the improved TS. The identification of the specific licensee controlled document containing this requirement is provided in Enclosure 3B of the conversion
Ching) D:scriptions for TRM R: vision 29 Attachment 1 to TXX-99202 Page 35 of 40 I submittal.
Compliance with the relocated requirements will not be affected by this proposed change to the current Technical Specifications. The required periodic surveillances will continue to be performed to ensure that limits on parameters are maintained. Therefore, relocation of these requirments will have no impact on system operability or the maintenance of controlled parameters within limits.
BASES:
The CTS BASES Section 3/4.9.6," Crane Travel- Spent Fuel Storage Areas,"is relocated verbatim to ITRM BASES 13.9.34, " Refueling - Crane Travel - Spent Fuel Storage Areas".
Change Request # TR-97-009.48 ITRM # 13.9.35 Water Level, Reactor Vessel, Control Rods ITS Reference # -
ITS Change # 3/4.9,10-01-R CTS ~# 3/4.9.9.2 CTRM # -
Description of Change:
ITS Change # 10-01-R: !
This change relocates the current TS requirements concerning reactor vessel i water level for movement of [ control rods] to a licensee controlled document. l l
This specification places a lower limit on the amount of water above the top of the i fuel assemblies in the reactor vessel during movement of control rods. The i Bases state that this ensures the water removes 99 percent of the assumed 10 percent iodine gap activity released from the rupture of an irradiated fuel assembly in the event of a fuel handling accident (FHA) during core alterations.
However, the movement of control rods is not associated with the initial conditions of an FHA, and the Bases do not address any concerns regarding inadvertent criticality which could lead to a breach of the fuel rod cladding.
Inadvertent criticality during Mode 6 is prevented by maintaining proper boron concentration in the coolant in accordance with LCO 3.9.1.
This proposed TS revision relocates requirements, which do not meet the TS criteria in 10CFR50.36(c)(2)(ii), to documents with established control programs.
This regulation addresses the scope and purpose of TS. In doing so, it sets forth a specific set of objective criteria for determining which regulatory requirements and operating restrictions should be included in the TS. Relocation of these requirements allows the TS to be reserved only for those conditions or limitations upon reactor operation which are necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety thereby focusing the scope of the TS. An evaluation of the applicability of these criteria to this specification is provided in Attachment 21.
Chinge Descriptions for TRM R: vision 29 Attachment 1 to TXX-99202 Page 36 of 40 To ensure an appropriate level of control, these requirements will be relocated to
- 1) documents that are subject to the provisions of 10 CFR 50.59,2) other licensee documents which have similar regulatory controls (e.g., the Quality Assurance Plan, as described in the FSAR, which is controlled by 10CFR50.54a),
or 3) to programs that are controlled via the Administrative Controls section of the improved TS. The identification of the specific licensee controlled document containing this requirement is provided in Enclosure 3B of the conversion submittal.
Compliance with the relocated requirements will not be affected by this proposed change to the current Technical Specifications. The required periodic surveillances will continue to be performed to ensure that limits on parameters are maintained. Therefore, relocation of these requirements will have no impact on system operability or the maintenance of controlled parameters within limits.
BASES:
The CTS BASES Section 3/4.9.9," Water Level- Reactor Vessel and irradiated Fuel Storage," is relocated verbatim to ITRM BASES 13.9.35, " Water Level, Reactor Vessel, Control Rods".
Change Request # TR-97-009.49 ITRM # 13.9.36 Fuel Storage Area Water Level ITS Reference # -
ITS Change # 3/4.9,11-01-LG,11-04-LG CTS # 3/4.9.10 CTRM # -
Description of Change:
ITS Change # 11-01-LG The Applicability is revised to require the water level be maintained only when moving irradiated fuel. The bounding design basis fuel handling accident in the fuel storage [ area) assumes an irradiated fuel assembly is dropped onto an array of irradiated fuel assemblies seated in the fuel storage racks. The revised Applicability is consistent with this design basis accident (DBA). The water level requirement is necessary to mitigate the consequences of this DBA. Moving the requirement to maintain fuel storage [ area] water level whenever irradiated fuel assemblies are in the fuel storage [ area) provides for conservative plant operations. Moving this information maintains consistency with NUREG-1431.
The information is moved to a licensee controlled document which is controlled by a 10 CFR 50.59 change process.
ITS Change # 11-04-LG This change moves the restriction on crane operation to a licensee controlled document. The requirement to suspend crane operations over the spent fuel pool
Ching) Descriptions for TRM R5 vision 29 Attachment 1 to TXX-99202 Page 37 of 40 in the event pool water level is <23 feet, has been removed from the ACTION of CTS 3/4.9.11 (CTS 3/4.9.10 for Comanche Peak) in corresponding ITS 3.7.5, for the fuel pool water level. The bounding design basis fuel handling accident in the spent fuel pool assumes an irradiated fuel assembly is dropped onto [an array of irradiated fuel assemblies seated in) the spent fuel poo;. Crane operations that could adversely affect fuel stored in the spent fuel pool are controlled in accordance with plant procedures as analyzed in the review of heavy loads movements. Administrative controls are employed to prevent the handling of loads that have a greater potential energy than those which have been analyzed.
Also see licensees responses to NRC Bulletin 96-02, " Movement of Heavy Loads Over Spent Fuel, Over Fuel in the Reactor Core, or Over Safety-Related Equipment." Moving this information maintains consistency with NUREG-1431.
The information is moved to a licensee controlled document which is controlled by a 10 CFR 50.59 change process.
This technical requirement was developed from a specific item out of an existing Technical Specification (i.e. CTS 3/4.9.10). This item can not stand alone, therefore a technical requirement LCO, Applicability, Actions, and Surveillances, and Bases were created as required.
BASES:
Adds information to support the new ITRM.
Change Request # TR-97-009.50 ITRM # 13.10.31 Explosive Gas Monitoring Instrumentation ITS Reference # 5.5.12a ITS Change # 3/4.3, 9-01-LG CTS # 3/4.3.3.4, TSI-005-RO i CTRM # - l Description of Change:
ITS Change # 9-01-LG:
The explosive gas monitoring in instrumentation will be controlled by the Explosive Gas Monitoring Program established in accordance with ITS 5.5.12. l l
BASES: 1 The CTS BASES Section 3/4.3.3.4," Explosive Gas Monitoring Instrumentation,"
and Technical Specification Interpretation (TSI) 005, Revision 0, are relocated verbatim to ITRM BASES 13.10.31, " Explosive Gas Monitoring Instrumentation". ,
i Change Request # TR-97-009.51 ITRM # 13.10.32 Gas Storage Tanks ,
ITS Reference # 5.5.12b ITS Change # 3/4.11,1-03-LG
Chinge Descriptions for TRM R: vision 29 Attachment 1 to TXX-99202 Page 38 of 40 L CTS # 3/4.11.2.2
' CTRM # -
Description of Change:
ITS Change # 1-03-LG:
The underlying requirements of this TS are now in ITS 5.5.12," Explosive Gas Storage and Storage Tank Radioactivity Monitoring Program," which includes the requirement to comply with [BTP ETSB 11-5, Rev. 0]. The details of the LCO, Action and surveillance will be incorporated into the Explosive Gas Storage and Storage Tank Radioactivity Monitoring program. This change is consistent with NUREG-1431 BASES:
The CTS BASES Section 3/4.11.2.2, " Gas Storage Tanks,"is relocated verbatim to ITRM BASES 13.10.32, " Gas Storage Tanks".
Change Request # TR-97-009.52 ITRM # 13.10.33 Liquid Holdup Tanks ITS Reference # 5.5.12c ITS Change # 3/4.11,1-01-LG CTS # 3/4.11.1 CTRM # -
Description of Change:
ITS Change # 1-01-LG: j
' The underlying requirements of this TS are now in ITS 5.5.12, " Explosive Gas Storage and Storage Tank Radioactivity Monitoring Program", which includes the I requirement to limit liquid radwaste quantities per [SRP 15.7.3, Rev. 2]. The details of the LCO, Action and surveillance will be incorporated into the Explosive Gas Storage and Storage Tank Radioactivity Monitoring program. This change is consistent with NUREG-1431.
BASES:
The CTS BASES Section 3/4.11.1, " Liquid Holdup Tanks,"is relocated verbatim to ITRM BASES 13.10.33, " Liquid Holdup Tanks".
_ Change Request # - TR-97-009.53
- ITRM # 13.10.34 Explosive Gas Mixture ITS Reference # 5.5.12a ITS Change # 3/4,11,1-02-LG CTS # 3/4.11.2.1 CTRM # -
Ch:nge D:scriptions for TRM R vision 29 Attachment 1 to TXX-99202 Page 39 of 40 l Description of Change:
ITS Change # 1-02-LG: 1 1
i The underlying requirements of this TS are now in ITS 5.5.12, " Explosive Gas Storage and Storage Tank Radioactivity Monitoring Program," which includes the
)
requirement to comply with the system's design criteria. The details of the LCO, Action and surveillance will be incorporated into the Explosive Gas Storage and Storage Tank Radioactivity Monitoring program. This change is consistent with NUREG-1431.
BASES:
The CTS BASES Section 3/4.11.2.1, " Explosive Gas Mixture,"is relocated to ITRM BASES 13.10.34, " Explosive Gas Mixture".
Change Request # TR-97-009.54 ITRM # 15.5.17 Administrative Controls ITS Reference # 5.5.17 ITS Change # -
CTS # 6.8.1.1 CTRM # 0 Description of change:
The information in this section has been relocated from the CTRM Section 0.
Change Request # TR-97-009.55 ITRM # 15.5.31 Snubber Augmented Inservice inspection Program ITS Reference # various ITS Change # -
CTS # -
CTRM # 3.1 Description of change: l The information in this section has been relocated from the CTRM Section 3.1. See Change Request # TR-97-009.36 for related information.
l Change Request # TR-97-009.56 i ITRM # -
l ITS Reference # -
ITS Change # -
CTS # -
1 CTRM # 3.2, 3.3 (Deleted)
CTRM Sections 3.2 and 3.3 were deleted by a previous TRM Revision, and have not been included in the ITRM.
l
/
Chinga Descriptions for TRM Rsvision 29 Attachment 1 to TXX-99202 Page 40 of 40
References:
- 1. TXU Electric letter logged TXX-97105, from C. L. Terry to the NRC dated May 15,1997
- 2. TXU Electric letter logged TXX-98182, from C. L. Terry to the NRC dated August 5,1998 toTXX-99202 CPSES - TECHNICAL REQUIREMENTS MANUAL REVISION - 30 DETAILED DESCRIPTION Prefix Page Page 1 (as a.aended) Group Description 13.3- 20 2 Adds the following Applicability note for TR 13.3.32," Source Range Neutron Flux," "While this LCO is not met, MODE changes are not permitted unless required to comply with Actions of other TS LCOs."
Clarification TRM Revision 29 relocated some of the Current Technical Specifications (CTS) to the TRM. In Revision 29 the relocated and existing items were also converted to the new Improved Technical Specifications (ITS) format. The ITS changes (currently scheduled for inglementation in .luly 1999) include clarification of LCO 3.0.4 and SR 3.0.4 for transitioning between MODES of operation and other specified conditions in the Applicability of Technical Specification. The use of hte modified 3.0.4 results in removing some restrictions on MODE changes imposed by the LCO 3.0.4 contained in CTS.
The removal of MODE change restrictions is a relaxation of CTS requirements, and the changes were evaluated during the converstion to ITS.
During the development of the CPSES Improved Technical Requirements Manual (ITRM), the allowances of the ITS LCO 3.0.4 and SR 3.0.4 are being applied with the " rules of usage" for the ITRM requirements. The need for a review of the TRM is consistent with the review performed for modification ofITS requirements. The review was performed and determined that specific restrictions on MODE changes should be included for a few Technical Requirements. These changes prevent an increased allowance in fiexibility and are made for consistency with the new ITS format.
Change Request Number TR 5 . 1 Related SER . SSER SER/SSER Impact N 13.7- 09 2 Adds the following Applicability note for TR 13.7.35, " Snubbers," "While this LCO is not met, MODE changes shall be restricted to those MODE changes allowed by the applicable TS LCO's for the equipment which may be potentially inoperable as a result of the inoperable snubber."
Clarification See justification for Change Request Number TR-99-005.1 on page 13.3-21.
Change Request Number TR 5 . 2 Related SER SSER ,
SER/SSER Impact N 13.7- 11 2 Adds the following Applicability note for TR 13.7.36, " Area Temperature Monitoring," "While this LCO is not met due to the maximum temperature 1
l 4
l toTXX-99202 CPSES - TECHNICAL REQUIREMENTS MANUAL REVISION - 30 DETAILED DESCRIPTION Prefix Page Page 2 (as amended) G l oup Description limit for abnormal conditions not met, MODE changes are not permitted unless required to comply with Actions of other TS LCOs."
Clarification Seejustification for Change Request Number TR-99-005.1 on page 13.3-21.
Change Request Number TR 5 . 3 Related SER SSER SER/SSERImpact N i
13.9- 07 2 Adds the following Applicability note for TR 13.9.36, " Fuel Storage Area Water Level," "While this LCO is not met, do not commence crane operations with loads over irradiated fuel in the storage racks."
Clarification See justification for Change Request Number TR-99-005.1 on page 13.3-21.
Change Request Number TR 5 . 4 Related SER - SSER .
SER/SSER Impact N 13.10- 02 2 Condition D of TR 13.10.3, " Explosive Gas Monitoring Instrumentation," is revised from "..the same recombiner(s)." to " . the inservice recombiner." I Clarification As currently stated, Condition D implies that it is goes with Condition C, that is if both the inlet and outlet monitors were out on the same recombiner.
Ilowever, Condition E addresses the condition of both the inlet and outlet oxygen monitors being inoperable. Therefore Condition C is reworded similar to Conditions C and E.
Change Request Number TR 5 . 5 Related SER SSER SER/SSER Impact N l
1 Enclosure to TXX-99202 s
e
COMANCHE PEAK STEAM ELECTRIC STATION UNITS 1 & 2 TECWICAL REQUIREMENTS MANUAL (TRM) INFORMATION ONLY INSTRUCTION SHEET (Page 1 of 1)
The following instructional information and checklist is being furnished to help insert Revisions 29 and 30 TRM pages into the Comanche Peak Steam Electric Station TRM.
All pages and tabs should be removed and discarded with the exception of the TRM TAB and the EPL-TAB.
Insert the new sheets into the " TECHNICAL REQUIREMENTS MANUAL".
Insert the TRM-TAB at the beginning of the Technical Requirements Manual.
Insert the EPL-TAB between page "B 13.10 4". and page "EPL-1".
Note: Please complete the entry for insertion of Revisions 29/30 on the " Record of Changes" form located at the beginning of the TRM.
1 I
.