ML20210S050
| ML20210S050 | |
| Person / Time | |
|---|---|
| Issue date: | 08/10/1999 |
| From: | Beckner W NRC (Affiliation Not Assigned) |
| To: | Jennifer Davis NUCLEAR ENERGY INSTITUTE (FORMERLY NUCLEAR MGMT & |
| References | |
| PROJECT-689 NUDOCS 9908170287 | |
| Download: ML20210S050 (85) | |
Text
August 10, 1999 Mr. James Davis, Director Operations' Department Nuclear Energy Institute 1776 I Street, N. W.
Suite 400 Washington, DC 20006-3708
Dear Mr. Davis:
Enclosed is a summary of ourjoint NRC/ Technical Specifications Task Force (TSTF)
Owners Group meeting at the Nuclear Regulatory Commission in Rockville, Maryland, on l July 15 and 16,1999. Should the TSTF have any comments or questions, please do not hesitate to contact me on 301-415-1161 or by e-mail at wdb@nrc. gov.
Sincerely, ,
1 Original signed by: 1 William D. Beckner, Chief Technical Specifications Branch Division of Regulatory improvement Programs Office of Nuclear Reactor Regulation Project No. 689 '
Enclosu v. hsstatez 7{ggg g cc: Those on enclosed Attendees List DISTRIBUTION:
FILE CENTER FBurrows TSB R/F PUBLIC JMitchell DMatthews EDO WITS No. 199900021 SNewberry TSB Staff JBirmingham DOCUMENT: G \RTS8VOHNSONWTGSUM07.99 WPO m OFFICE RTSB DRIP.NRR NRR/Proj 689 SC:R RR C:RTSB: DRIP:NRR NAME DLJohnson I JBirminaba RLDennia WDBeckner WN DATE 7/28/99 Of/ o 9/99 OYl8/99 0 l0/99 nFFICIAL RECORD COPY 9908170287 990810 PDR REVGP ERGNUMRC PDR 170027 MNNSW gg 141
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W atr ug g t UNITED STATES g j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066-4001 o
% ,, ,, August 10, 1999 I
i Mr. James Davis, Director l Operations Department I Nuclear Energy institute 1776 l Street, N. W.
Suite 400 !
Washington, DC 20006-3708 j l
Dear Mr. Davis:
Enclosed is a summary of ourjoint NRC/ Technical Specifications Task Force (TSTF) )
Owners Group meeting at the Nuclear Regulatory Commission in Rockville, Maryland, on July 15 and 16,1999. Should the TSTF have any comments or questions, please do not hesitate to contact me on 301-415-1161 or by e-mail at wdb@nrc. gov.
Sincerely, M /), d ./t - -- -
William D. Beckner, Chief 1 Technical Specifications Branch I Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Project No. 689
Enclosure:
As stated cc: Those on enclosed Attendees List j
l l:
Nuclear Energy Institute Project No. 689 l
cc: Mr. Ralph Beedle Ms. Lynnette Hendricks, Director Senior Vice President Plant Support and Chief Nuclear Officer Nuclear Energy Institute
. Nuclear Energy Institute Suite 400 Suite 400 ~ 1776 l Street, NW 1776 I Street, NW Washington, DC 20006-3708 Washington, DC 20006-3708 Mr. Alex Marion, Director Mr. Charles B. Brinkman, Director Programs ~ Washington Operations ,
Nuclear Energy Institute ABB-Combustion Engineering, Inc.
Suite 400 12300 Twinbrook Parkway, Suite 330 1776 l Street, NW. Rockville, Maryland. 20032 Washington, DC 20006-3708 Mr. David Modeen, Director Engineering Nuclear Energy institute Suite 400 1776 l Street, NW Washington, DC 20006-3708 Mr. Anthony Pietrangelo, Director Licensing Nuclear Energy Institute Suite 400 1776 i Street, NW Washington, DC 20006-3708 >
Mr. Nicholas J. Liparulo, Manager Nuclear Safety and Regulatory Activities Nucient and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, Pennsylvania 15230 Mr. Jim Davis, Director Operations-Nuclear Energy Institute l Suite 400 1776 i Street, NW -
Washington, DC 20006-3708
s 2 '*
TECHNICAL SPECIFICATIONS TASK FORCE MEETING
SUMMARY
July 15 and 16,1999 -
' Review of Outstandina Travelers TSTF-287 (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Allowed Outage Time)
The staff and industry held a discussion assisted by talking points (Attachment 1). The outcome of the discussion centered around industry providing a modification to include a basis for why 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is an appropriate time, a statement in the Bases about the compensatory measures to be used when entering the Action Statement intentionally or unintentionally, and a Reviewer's Note in the Bases stating that a commitment to have a compensatory measures program or procedure available prior to adoption of the proposed
~
action.
TSTF-036, Rev. 3, was being held up until submittal of TSB-023. NRC agreed to re-review the proposal to ensure there is no conflict.
TSTF-215 was withdrawn by the TSTF.
The TSTF and NRC agreed on a new revision package for TSTF-324 to exclude " trip" bypass.
TSTF-198 through TSTF-203 (Battery Technical Specifications)
A new draft revision has been composed, as a result of IEEE subcommittee discussions, and mailed to Kurt Uhlir in early July. This proposal was handed out to the TSTF (see Attachment 2). The TSTF will review the proposal and contact NRC to arrange a focus group meeting within two weeks.
A Draft Administrative Letter, provided during the meeting (see Attachment 3), discusses Guidance on Adoption of Generic Changes to NUREGs -1430, -1431, -1432, -1433, and -
1434, Standard Technical Specifications. The NRC will review and provide feedback to Donald Hoffman, EXCEL Services, Inc.
The remaining outstanding travelers were discussed in order of priority (see Attachment 4).
Denny Buschbaum, Westinghouse Owner's Group Chairman, stated that it appears that the proposed changes in TSB-020, Allowable Values, will be accepted. NRC notes that the schedule for industry comments to be received by NRC, under WITS ltem 199900021, is July 30,1999.
Publication of Revision 2 to the Standard Technical Soecificetion NRC plans to perform a final check of the Working Drafts and begin posting to the Web site the week of July 19,1999. Debbie Johnson will notify the group as the files are posted. The TSTF requested these files be posted in a PDF format, which requires special software. The acquisition of this software could delay the process, but NRC will Enclosure
c, e .
I w I i j . 1 NRC has developed a matrix table of all approved TSTF travelers by section, vendor and l spec or bases. This document was provided to the TSTF during the meeting and is
, . Included in this meeting summary as Attachment 5. The staff will use this matrix to perform
! ' an integrated, section-by-section review of Draft Revision 2 of the Standard Technical Specifications.
. The TSTF stated they plan to submit more revisions and some new travelers that could i number over TSTF.-355.
l-A list of editorial changes made by the staff during the Working Draft creation was handed l out (see Attachment 6). ,
The TSTF volunteered to note where RHR in 3.9 should reference Criteria 4 and provide this to NRC so that changes could be made before publication of Revision 2.
. It was suggested by the staff that acronyms were not needed in titles contained within the
. STS and that they be removed. The TSTF stated that they believed there was no benefit to removing them, and it was agreed that they should be retained.
. There was a misunderstanding between the staff and EXCEL Services in how editorial changes known as EDITS were numbered. It was decided that this misunderstanding would be resolved outside the meeting.
. The TSTF requested that the next Owners Group meeting be held the aftemoon of August 30 and all day August 31, instead of the agreed to dates of September 1 and 2. The NRC will confirm availability.
TSTF Process
. The TSTF plans to develop and submit an outline of their process to NRC.
. NRC envisions continuing the process to review and approve post Revision 2 proposed changes.
Conversion
. A Conversion Guidance document is being developed by the TSTF. It should be ready for submittal to the staff for comment early in the year 2000. The Writer's Guide will be updated concurrently with this Guidance document.
Correction to June 16 and 17.1999 Meetina Summarv l
. After publication of Revision 2, the TSTF will not withdraw those travelers that have already I been submitted, to renumber and remark. If the proposed changes to the Revision 1 pages appear to be complicated, the TSTF will remark appropriate Revision 2 pages and resubmit them. NRC will continue to review those travelers already submitted, as numbered.
Enclosure l
l
L e
\
ATTENDEES LIST NRC/TSTF OWNER'S GROUP MEETING l July 15 and 16,1999 I NAME ORGANIZATION ADDRESS PHONE # E-MAIL ID No11 Clarkson Duke Energy Oconee Nuclear Site 864-885-3077 ntclarks@duk j (BWOG TSTF) 7800 Rochester Highway e-enerav.com Seneca, SC 29679 Tcm Weber CEOG-APS Palo Verde Nuclear 623 393-5764 tweber01 @ao Mail Station 7636 ,
sc.com 5801 South Wintersburg Road Tonapah, AZ 85354-7529 Vince Gilbert NEl Suite 400 202-739-8138 iva@nei. ora 17761 Street, NW Washington, DC 20006-3708 D. Buschbaum TSTF/WOG TU Electric 254-897-5851 dbuschb1@tu P. O. Box 1002, M.S. A08 electric.com Glen Rose, TX 76043 Donald Hoffman EXCEL /TSTF 11921 Rockville Pike 301-984-4400 donaldh@exc l Suite 100 elsvcs.com Rockville, MD 20852 Harold D. Comed /BWOG LaSalle County Station 815-357-6761 herold.d.conti Pontious, Jr. 2601 North 21 Road x2231 ousir@ucm.co Marseille, IL 61341 m Brian Mann EXCEL /TSTF 301-984-4400 bmann@erols, com Bill Beckner NRR/TSB NRC 301-415-1161 wdb@nrc.aov Bob Dennig NRR/TSB NRC 301-415-1156 rid @nrc.aov D:bbie Johnson NRR/TSB NRC 301-415-3060 dii@nrc.aov Bob Tjader NRR/TSB NRC 301-415-1187 trt@nrc.aov Carl Schulten NRR/TSB NRC 301-415-1192 css 1 @nrc.aov Robert Giardina NRR/TSB NRC 301-415-3152 Tommy Le NRR/TSB NRC 301-415-1458 nbl@nrc.aov J:hn Segala NRR/DSSA/SPLB NRC 301-415-1858 ios1 @nrc.aov Harold Walker NRR/DSSA/SPLB NRC 301-415 2827 hxw@nrc.aov Mark Reinhart NRR/DSSA/SPSB NRC 301-415-1185 fmr@nrc.aov Sttve LaVie NRR/DSSA/SPSB NRC 301-415-1081 ksw@nrc.aov i
Page 1 of 2
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ATTENDEES LIST NRC/TSTF OWNER'S GROUP MEETING July 15 and 16,1999 NAME ORGANIZATION ADDRESS PHONE # E Mall ID Jsnak Raval NRR/DSSA/SPLB NRC 301-415-2802 ihr@nrc.oov Stsve West NRR/DSSA/SPLB NRC 301-415-1220 ksw@nrc.aov Vin-Sien Guo NRR/DSSA/SPLB NRC 301-415-1816 iso @nrc.oov Dznnis Gordon NRR/DIPM/lOLB NRC 301-415-1162' dxa@nrc.oov Richard J. NRR/DIPM/lOHB NRC 301-415-3162 rie1 @nrc.aov i Eckenrode Gr:0 S. Galletti NRR/DIPM NRC 301-415-1831 aso@nrc.oov Ronald Young NRR/DSSA/SPLB NRC 301-415-2852 Kris Parczewski NRR/DE/EMCB NRC 301-415-2705 kio@nrc.oov Carolyn Lauron NRR/DE/EMCB NRC 301-415-2736 cll@nrc.oov j
. James Bongarra NRR/DIPM/lOLB NRC 301-415-1046 ixb@nrc.aov Jrck Hayes NRR/SPSB NRC 301-415-3167 lih@nrc.oov Jay Lee NRR/SPSB NRC 301-415-1080 ivl1 @nrc.oov DOCUMENT NAME: G:\RTSBVOHNSON\ATTENDO7.LST.WPD
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Page 2 of 2
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[ Reviewer's Note: Adoption of Condition B is dependant on a commitment from the licensee to have guidance available describing compensatory measures to be taken in the event of an intentional and unintentional entry into Condition B.]
If the control room boundary is inoperable in MODES 1,2,3, and 4 such that the CREVS trains cannot establish or maintain the required pressure, actions must be taken to restore an OPERABLE control room boundary with 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. During the period that the control room boundary is inoperable, attention should be given to protecting the control room operators to the extent possible from potential
. hazards such as radioactive contamination, toxic chemicals, smoke, temperature and relative humidity.
and physical security. Preplanned actions should be available to address these concerns for interdional entry into the condition and implemented as soon as practical on unintentional entry into the condition.
The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time is reasonable based on the low probability of a DBA occurring during this time period, the availability of the CREVS to provide a filtered environment (albeit with potential control room inleakage), and the use of compensatory measures. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time is a typically reasonable time to diagnose, plan, and possibly repair, and test most problems with the control room boundary, and to interface with the NRC, as necessary, to discuss regulatory alternatives.
p http1/irm25.ntc. gov /N RR/jlk/ref-docs /batta384rev i l
3.8 ELECTRICAL POWER SYSTEMS
.h 3.8.4 DC Sources---Operating 1
l LCO 3.8.4 The (Train A and Train B] [ Station Service and Diesel Generator] DC electrical power 1 subsystems shall be OPERABLE.
l APPLICABILITY: MODES 1,2, [and (BWR)] 3[, and 4 (PWR)].
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or mom battery A.1 Verify battery terminal voltage is 2 hrs and once chargers inoperable with greater than or equal to [# of per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> output voltage measured connected cells X 2.07] volts thereafter at the battery output g terminals less than [# of l connected cells X 2.22] A.2 Restore battery charger to 7 days volts but greater than or OPERABLE status l
equal to [# of connected cells X 2.07] volts CONDITION REQUIRED ACTION COMPLETION TIME B. One or more battery B.1 Restore voltage at the battery 4 hrs chargers inoperable with terminals to greater than or equal output voltage measured to [# of connected cells X 2.22]
at the battery output volts terminals less than [# of g connected cells X 2.07]
volts B.2 Verify battery float current is less 4 hrs than [10] amps t
l B.3 Restore battery float current to 24 hrs less than [2] amps ANI2 l B.4 Restore battery charger to 7 days OPERABLE status i
l l
l l
l 1 of 4 7/12/99 2:01 PM J
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~ ~
CONDITION REQUIRED ACTION COMPLETION TIME i
C. One or more batteries C.1 Restore battery float current to less 24 hrs with float current greater than [2] amps ,
than or equal to [2] amps j but less than [10] amps.
)
i
)
CONDITION REQUIRED ACTION COMPLETION TIME D. One or more batteries D.1 Declare associated battery Immediately I with float current greater inoperable than [10] amps CONDITION REQUIRED ACTION COMPLETION TIME E. One DC electrical power E.1 Restore DC electrical power 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> subsystem inoperable for subsystem to OPERABLE l
reasons other than item A, B, C, status. l or D. I l
CONDITION REQUIRED ACTION COMPLETION TIME 1
F. Required Action and 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 /> associated Completion Time g i not met.
F.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery charger output voltage measured at the battery [31 days]
terminals is greater than or equal to [# of connected cells X 2.22]
volts on float charge SURVEILLANCE FREQUENCY SR 3.8.4.2 Verify battery float current is less than [2] amps 31 days 2 of 4 7/12/99 2:01 PM
GDEdI29.mc.govMligyAffMtteryErav l l SURVEILLANCE l FREQUENCY 1- .
7 i
. . . . . . . . .. .. . .----N OTE-----.-------
This Surveillance shall not be performed in MODE 1,2, [or (BWR)] 3[,
or 4 (PWR)]. However, credit may be taken for unplanned events that satisfy this SR.
SR 3.8.4.3 Verify each battery charger supplies greater than or equal to [400] [18 months) amps at greater than or equal to [# of cells X 2.22] volts for greater than or equal to [4] hours.
.QE -
Verify each battery charger can recharge the battery to the fully charged state within [24] hours while supplying the largest combined demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state.
l SURVEILLANCE FREQUENCY
. ... ......... .... . . . . .-N OTE--.--.---. ---
- 1. This Surveillance shall not be performed in MODE 1,2,
[or (BWR)] 3[, or 4 (PWR)]. However, credit may be taken for unplanned events that satisfy this SR.
- 2. The modified perfonnance test of SR 3.8.4.4 may be substituted for this SR.
SR 3.8.4.4 Verify battery capacity is adequate to supply, and maintain [18 months) in OPERABLE status, the required emergency loads for the design duty cycle when subjected to a service test.
l l
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Ettp:14rm15.nrc.g v/NRR/jlkhef-docs / battery 384rev SURVEILLANCE m . FREQUENCY ,
a.
NOTE-----------
This Surveillance shall not be performed in MODE 1,2, [or j (BWR)] 3[, or 4 (PWR)]. .
l SR 3.8.4.5 Verify battery capacity is greater than or equal to (60 months) l
[80]% of the manufacturer's rating when subjected l to a performance test or a modified performance M :
test. l 1
12 months when battery shows degradation or has reached [85]% of the expected life with l capacityless than 100% of manufacerer's rating i M
24 months when ,
battery has reached j
[85]% of the expected life with capacity greater than or equal to 100% of manufacturer's rating i
4 of 4 7/12/99 2:01 Pb
ueerwatunEREmeneryumv1 1
3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources---Shutdown
~
LCO 3.8.5 DC electrical power subsystem shall be OPERABLE to support the DC electrical power distribution subsystem (s) required by LCO 3.8.10. " Distribution Systems - Shutdown."
APPLICABILITY: MODES [5 and 6 (PWR)] [4&5(BWR)], During movement ofirradiated fuel assemblies.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more battery A.1 Verify battery terminal voltage is 2 hrs and once chargers inoperable with greater than or equal to [# of per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> output voltage measured connected cells X 2.07] volts thereafter at the battery output g terminals less than [# of connected cells X 2.22] A.2 Restore battery charger to 7 days volts but Freater than or OPERABLE status equal to [# of connected cells X 2.07] volts CONDITION REQUIRED ACTION COMPLETION TIME B. One or more battery B.1 Restore voltage at the battery 4 hrs chargers inoperable with terminals to greater than or equal output voltage measured to [# of connected cells X 2.22]
at the battery output volts terminals less than [# of g connected cells X 2.07]
volts B.2 Verify battery float current is less 4 hrs than [10] amps M
B.3 Restore battery float current to 24 hrs less than [2] amps M
B.4 Restore battery charger to 7 days OPERABLE status 1 of 2 7/12/99 2:01 PF
Y CONDITION REQUIRED ACTION COMPLETION TIME C. One or more required DC C.1 Declare affected required Immediately electrical power subsystem feature (s) inoperable inoperable for reasons other g than item A or B.
C.2.1 Suspend CORE Immediately ALTERATIONS.
C.2.2 Suspend movement of Immediately irradiated fuel assemblies. ,
t M '
)
C.2.3 Initiate action to suspend Immediately.
operations involving positive reactivity additions.
1 M
C.2.4 Initiate action to restore Immediately required DC electrical power subsystems to OPERABLE status.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY ;
............ NOTE--..-.-.---.---.---.---.--
The following SRs are not required to be performed:
SR 3.8.4.3, SR 3.8.4.4, and SR 3.8.4.5 SR 3.8.5.1 For DC sources required to be OPERABLE, the following SRs In accordance are applicable: with applicable SR 3.8.4.1, SR 3.8.4.2, SR 3.8.4.3, SR 3.8.4.4, and SR 3.8.4.5 SRs 2 of 2 7U2/99 2:01 Ph
l 7
L 3.8 ELECTRICAL POWER SYSTEMS 3.8.6 Battery Cell Parameters LCO 3.8.6 Battery cell parameters for the [ Train A and Train B] [ Station Service and diesel generator] I batteries shall be within limits i l
l l APPLICABILITY: When associated DC electrical power subsystems are required to be OPERABLE.
l l ACTIONS I
.... ...... ..... NOTE- - - . - . - - . - . . . . - . - - - - - - . - - - - .
Separate Conditions entry is allowed for each battery.
1 1 1
A. One or more batteries A.1 Verify battery voltage is greater 2 hrs with one or more cells than or equal to [# of connected with float voltage less cells X 2.22] volts than [2.07] volts g l
A.2 Verify float current is less than 2 hrs
[2] amps ANI2 A.3 Restore float voltage of all 24 hrs connected cells to within each cell's established design voltage limits CONDITION REQUIRED ACTION COMPLETION TIME B. One or more batteries B.1 Restore electrolyte level to within 8 hrs with electrolyte level of the cell's established design level one or more cells below limits the top of the plates g B.2 Following restoration of 2 hrs and once per 12 electrolyte level, verify float hrs thereafter for i voltage for affected cells is within 7 days the cell's established design l
voltage limits l l \
l .* l l
l l 1 of 2 7/12/99 2:02 Ph l; l
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[ CONDITION REQUIRED ACTION COMPLETION TIME C. One or more batteries C.1 Restore pilot cell (s) temperature to 8 hrs
- with electrolyte within the battery's established temperature of one or design temperature limits more cells less than the battery's established design temperature limits CONDITION REQUIRED ACTION COMPLETION TIME D. Required Actions and D.1 Declare associated battery Immediately associated completion inoperable time of Conditions A, B, or C not met SURVEILLANCE FREQUENCY SR 3.8.6.1 Verify the float voltage of each pilot cell is within the 31 days i cell's established design voltage limits l l
SURVEILLANCE FREQUENCY SR 3.8.6.2 Verify the float voltage of each connected cell is within 92 days the cell's established design voltage limits SURVEILLANCE FREQUENCY SR 3.8.6.3 Verify electrolyte level for each connected cell is within 31 days the cell's established design electrolyte levellimits l
SURVEILLANCE FREQpCY SR 3.8.6.4 Verify the electrolyte temperature of each pilot cell is 31 days within the battery's established design temperature limits 2 of 2 7/12/99 2:02 PM
9, f
DRAFT 7/12/99 NRC Administrative Letter 99-XX: Guidance on Adoption of Generic Changes to NUREGs 1430,1431,1432,1433 and 1434 (Improved Technical Specifications).
Addressees:
(_ All Holders of operating licenses for nuclear reactors l
l Purpose -
The U.S. Nuclear Regulatory Commission (NRC) is issuing this administrative letter to inform addressees of NRC staff expectations for the submittal and processing of Technical Specification i amendments adopting NRC approved generic changes to NUREGs 1430,1431,1432,1433 and i
1434 by licensees that have implemented Improved Technical Specifications (ITS). This administrative letter does not create any new or changed NRC requirements or staff positions; no specific action or written response is required.
Background
The goal of this letter is to streamline license amendment requests involving generic changes and l l to streamline the NRC staff review of these requests. Standardized ITS format and Bases I improve the ability of licensees to assess generic changes, and allow NRC reviewers to review I
the associated license amendment requests more efficiently. It is important to capitalize on these advantages.
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Generic changes to the ITS NUREGs are proposed to the NRC by the Nuclear Energy Institute l (NEI) sponsored Technical Specification Task Force (TSTF). The TSTF includes representatives l from the four U.S. commercial nuclear power plant owners groups and NEI. Generic changes are reviewed and prepared using a TSTF process that the TSTF and NRC have developed to correct l and improve the ITS NUREGs. After NRC approval, generic changes are available for adoption by plants who have implemented or are developing 1TS conversion submittals.
I The focus of the TSTF process to date has been to aid plants developing ITS for implementation.
Although NRC approved generic changes are available for adoption by licensees who have implemented ITS, the currently accepted level of information for NRC review and approval of proposed license amendments does not take advantage of potential savings in time and resources by crediting efforts expended to approve the associated generic changes. Due to the number of l plants that have implemented or will implement ITS soon, the focus of the effort to improve the i Technical Specifications in the industry has begun to shift from supporting ITS submittals to adopting changes to the ITS NUREGs by plants who have implemented ITS.
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.e Discussion The TSTF process can provide better technical evaluation of proposed license amendments based on broader industry review and a more focused, one time NRC generic review on each issue, rather than repeating the generic aspects of a review forindividual plants. Improving the quality of proposed license amendments and stmamlining the process for plant specific development and review for both licensees and the NRC is expected to promote higher quality Technical Specifications at all participating plants. This can 1ead to improved health and safety of the public, while providing Technical Specifications that allow safe improvements to operational efficiency. Licensees are encouraged to, but not required to, adopt applicable NRC approved generic changes to take advantage of approved corrections and improvements to the NUREGs, and to maintain consistency of Technical Specifications among licensees. Increased use of the TSTF process is expected to significantly reduce required resources for developirig and processing license amendments for both licensees and the NRC. The NRC recognizes that not all generic changes to Technical Specifications will be anticipated by the generic change process.
l I I2ad times required for NRC review and approval of generic changes may necessitate NRC l
approval of plant specific changes, in some cases, prior to generic change approval. In these cases, the NRC's review of the plant specific change will be used to support the generic change review.
As licensees cont;nue to adopt ITS, the NRC expects more license amendment requests will be submitted that are generic in nature because the Technical Specifications of the licensees will I _already be based on the ITS NUREGs. Plant specific issues will be more commonly addressed by Technical Specification Bases changes using the Bases Change process. The number of plant specific Technical Specification changes is expected to decline.
l Current Generic Change Development Process Licensees wl a identify a need for a generic change submit proposed generic changes to the ITS NUREGs through their respective Owners Group TSTF representative. After review by plant )
and owners group representatives, and subsequently by the TSTF, if approved, the proposed generic (hanges are prepared and submitted to the NRC Technical Specification Branch for
- review. After review, the NRC either approves the proposed generic changes, requests changes, or rejects the change. NRC approved generic changes are made immediately available for licensees to adopt via the NRC webpage.
Guidance for Adoption of Generic Changes Licensees are requested to evaluate NRC approved generic changes to verify that the generic ;
change technical justification applies to their plant. The license amendment requests adopting i generic changes should:
- - Reference the generic change justification, noting differences based on plant specific design and licensing basis as necessary Avoid deviations from the generic changes when possible (plant specific wording in the )
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Technical Specification Bases is expected, while deviations from generic changes to the Technical Specifications themselves should be avoided where possible)
Provide plant specific justifications for any deviations from approved generic changes Reference generic changes on the marked-up Technical Specification pages Adopt multiple generic changes per request Follow the attached guidance for the No Significant Hazards Considerations when possible NRC reviewers may use the generic changejustifications in the preparation of the Safety Evaluation Report approving the request,if the generic changes are accepted without any technically significant deviations. Deviations from the generic change should be justified based ,
on plant specific design or licensing basis. The NRC may disapprove a specific generic change requested based on significant deviation from the generic change without adequate plant justification, and approve of the remainder of the generic changes requested to maximize the ability of a licensee to adopt requested generic changes.
Criteria for Plant Specific NRC Approval of Generic Changes Prior to Approval the Generic Change for the Industry Licensees are encouraged to use the generic change process for necessary Technical Specification changes identified as being generic. However, the NRC is prepared to review a plant specific request,if the change is required by a licensee on a plant specific basis for reasons such as nuclear safety, dose reduction, or operational necessity to avoid a reduction of power or to allow the start of power operations, orif the if the proposed change meets the requirements of 10 CFR l 50.90 regarding NRC review under exigent or emergency circumstances. In such cases, the licensee is requested to clearly state in their submittal the generic aspects of the change, why the change could not be approved generically prior to the request, and that the licensee commits to submitting a proposed generic change.
If a licensee proposes a license amendment involving a generic change to the NUREGs that is currently under review by the NRC, the NRC will consider the licensee's request concurrently l with the NRC's review of the generic change.
WORDS TO CONSIDER ADDRESSING NON CONVERTED PLANTS Use of Generic Changes by Licensees not Converted to ITS l
1 Justifications used for Generic Changes to NUREGS 1430,1431,1432,1433 and 1434 may be evaluated by Licensees not converted to ITS to assist in their own plant specific justifications, if appropriate, in their Technical Specification change License Amendments. Using the Generic Changes as a reference may be helpful, but Licensees using generic changes in this manner are encouraged to consider the ITS specific characteristics of format and content, word usage and definitions, notation conventions, the use of expanded Bases,3.0 Limiting Conditions for
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Operation, and other factors. Such factors are an integral part of the ITS, and should be evaluated for non-ISTS based Technical Specification changes.
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l This administrative letter requires no specific action or written msponse. If you have any ,
questions about this mttter, please contact the lead project manager listed below or your appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
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- Suggested Format for No Significant Hazards Considerations for Adoption of Generic Changes to the ITS NUREG 10 CFR 50.92 EVALUATION FOR
' ADMINISTRATIVE CHANGES The [Name] Power Station is adopting NRC approved TSTF XXX, TSTF-XXX, and TSTF-XXX generic changes to the Improved Standard Technical Specifications (ISTS) as outlined in NUREG-143X, " Standard Technical Specifications, [Name] Plants." The proposed changes involve reformatting, renumbering, and rewording of Technical Specifications with no change in intent. These changes, since they do not involve technical changes to the Technical Specifications, are administrative. -
This type of change is connected with the movement of requirements within the current requirements, or with the modification of wording that does not effect the technical content of the current Technical Specifications. Ther.e changes will also include nontechnical modifications of requirements to conform to the Writer's Guide or provide consistency with the improved Standard Technical Specifications in NUREG-143X. Administrative changes are not intended te add, delete, or relocate any technical requirements of the current Technical Specifications. I
~ In accordance with the criteria set forth in 10 CFR 50.92, [name] Company has evaluated these proposed Technical Specification changes and determined they do not represent a significant hazards consideration. The following is provided in support of this conclusion.
- 1. Does the change involve a significant increase in the probability or consequences of an accident ]
previously evaluated? ,
The proposed change involves reformatting, renumbering, and rewording the existing Technical Specifications. The reformattia;,, s.nbering, and rewording process involves no technical changes to the existing Technical Specificatiot.a. As such, this change is administrative in nature and does not effect initiators of analyzed events c assumed mitigation of accident or transient events. Therefore, this change does not involve a significart increase in the probability or consequences of an accident previously evaluated.
" 2. Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?
The proposed change does not involve a physical alteration of the plant (no new or different type of equipment will be installed) or changes in methods governing normal plant operation. The proposed change will not impose any new or eliminate any old requirements. Thus, this change does not create the ,
possibility of a new or different kind of accident from any accident previously evaluated. j
- 3. Does this change involve a significant reduction in a margin of safety?
The proposed change will not reduce a margin of safety because it has no effect on any safety analyses assumptions. This change is administrative in nature. Therefore, the change does not involve a significant i
reduction in a margin of safety,
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10 CFR 50.92 EVALUATION FOR MORE RESTRICTIVE CHANGES The [Name] Power Station is adopting NRC approved TSTF-XXX, TSTF-XXX, and TSTF-XXX generic changes to the Improved Standard Technical Specifications (ISTS) as outlined in NUREG-143X, " Standard Technical Specifications, [Name] Plants." The proposed changes involve adding more restrictive requirements to the existing Technical Specifications by either making current requirements more stringent or by adding new requirements that currently do not exist.
These changes include additional commitments that decrease allowed outage times, increase the frequency of j surveillances, impose additional surveillances, increase the scope of specifications to include additional plant I equipment, increase the applicability of specifications, or provide additional ar,tions. These changes have been !
evaluated to not be detrimental to plant safety. I l
In accordance with the criteria set forth in 10 CFR 50.92, the [name] Company har evaluated these proposed i Technical Specification changes and determined they do not represent a significant hazards consideration. The following is provided in support of this conclusion.
- 1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?
The proposed change provides more stringent requirements for operation of the fscility. These more stringent requirements have been evaluated and determined to not result in operation that will increase the probability of initiating an analyzed event and do not alter assumptions relative to nitigation of an accident or transient event. The more restrictive requirements continue to ensure process variables, structures, systems, and components are maintained consistent with the safety analyses and licensing basis. Therefore, this change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?
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I The proposed change does not involve a physical alteration of the plant (no new or different type of equipment will be installed) or changes in methods governing normal plant operation. The proposed change does impose different requirements. However, these changes are consistent with the assumptions in the safety analyses and licensing basis. Thus, this change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does this change involve a significant reduction in a margin of safety?
The imposition of more restrictive requirements either has no effect on or increases the margin of plant safety. As provided in the justification, each change in this category is, by definition, providing additional restrictions to enhance plant safety. The change maintains requirements within the safety analyses and licensing basis. Therefore, this change does not involve a significant reduction in a margin of safety.
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10 CFR 50.92 EVALUATION FOR RELOCATED SPECIFICATIONS The [Name] Power Station is adopting NRC approved TSTF-XXX, TSTF-XXX, and TSTF-XXX generic changes to the Improved Standard Technical Specifications (ISTS) as outlined in NUREG-143X, " Standard Technical Specifications, [Name] Plants." Some of the proposed changes involve relocating existing Technical Specification LCOs to licensee controlled documents.
The [name] Company has evaluated the current Technical Specifications using the criteria set forth in 10 CFR 50.36.
Specifications identified by this evaluation that did not meet the retention requirements specified in the regulation are not included in the Improved Standard Technical Specifications (ISTS). These specifications have been relocated from the current Technical Specifications to the Updated Final Safety Analysis Report.
In accordance with the criteria set fonh in 10 CFR 50.92, the [name] Company has evaluated these proposed Technical Specification changes and determined they do not represent a significant hazards consideration. The following is provided in support of this conclusion. ,
- 1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?
The proposed change relocates requirements and surveillances for structures, systems, components or variables that do not meet the criteria of 10 CFR 50.36 (c)(2)(ii) for inclusion in Technical Specifications as identified in the Application of Selection Criteria to the [name] Technical Specifications. The effected structures, systems, components or variables are not assumed to be initiators of analyzed events and are not assumed to mitigate accident or transient events. The requirements and surveillances for these effected structures, systems, components or variables will be relocated from the Technical Specifications to an appropriate administratively controlled document which will be incorporated into the UFSAR, thus it will be maintained pursuant to 10 CFR 50.59. In addition, the effected structures, systems, components or variables are addressed in existing surveillance procedures which are also controlled by 10 CFR.50.59 and subject to the change control provisions imposed by plant administrative procedures, which endorse applicable regulations and standards. Therefore, this change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the change create the possibility of a new or different Idad of accident from any accident previously evaluated?
The proposed change does not involve a physical alteration of the plant (no new or different type of equipment will be installed) or change in the methods governing normal plant operation. The proposed change will not impose or eliminate any requirements and adequate control of existing requirements will be maintained. Thus, this change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does this change involve a significant reduction in a margin of safety?
The proposed change will not reduce a margin of safety because it has no effect on any safety analyses assumptions. In addition, the relocated requirements and surveillances for the effected structure, system, component or variable remain the same as the existing Technical Specifications. Since any future changes to these requirements or the surveillance procedures will be evaluated per the requirements of 10 CFR l 50.59, no reduction in a margin of safety will be permitted.
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10 CFR 50.92 EVALUATION FOR I.ESS RESTRICTIVE CHANGES - REMOVED DETAIL The [Name] Power Station is adopting NRC approved TSTF-XXX, TSTF-XXX, and TSTF-XXX generic changes to the Improved Standard Technical Specifications (ISTS) as outlined in NUREG-143X, " Standard Technical Specifications. [Name] Plants." The proposed changes involve moving details out of the Technical Specifications and into the Technical Specifications Bases, the UFSAR, the (Technical Requirement Manual] or other documents under regulatory control such as the Quality Assurance Policy. The removal of this information is considered to be less restrictive because it is no Icnger controlled by the Technical Specification change process. Typically, the information moved is descriptive in nature and its removal conforms with NUREG-143X for format and content.
In accordance with the criteria set forth in 10 CFR 50.92, the [name] Company has evaluated these proposed Technical Specification changes and determined they do not represent a significant hazards consideration. The following is provided in support of this conclusion.
- 1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated' l
The proposed change relocates certain details from the Technical Specifications to other documents under regulatory control. The Bases, UFSAR, and [ Technical Requirement Manual] will be maintainea in accordance with 10 CFR 50.59. In addition to 10 CFR 50.59 provisions, the Technical Specification Bases are subject to the change control provisions in the Administrative Controls Chapter of the Technical Specification. The UFSAR is subject to the change control provisions of 10 CFR 50.71(c). Other documents are subject to controls imposed by Technical Specifications or regulations. Since any changes to i these documents will be evaluated, no significant increase in the probability or consequences of an accident !
previously evaluated will be allowed. Therefore this change does not involve a significant increase in the j probability or consequences of an accident previously evaluated. l
- 2. Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?
The proposed change does not involve a physical alteration of the plant (no new or different type of equipment will be installed) or a change in the methods governing normal plant operating. The proposed change will not impose or eliminate any requirements, and adequate control of the information will be maintained. Thus, this change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does this change involve a significant reduction in a margin of safety?
The proposed change will not reduce a margin of safety because it has no effect on any safety analysis assumptions. In addition, the details to be moved from the Technical Specifications to other documents are the same as the existing Technical Specifications. Since any future changes to these details will be evaluated, no significant reduction in a margin of safety will be allowed. A significant reduction in the margin of safety is not associated with the elimination of the 10 CFR 50.92 requirement for NRC review and approval of future changes to the relocated details. The proposed change is consistent with the [name]
Standard Technical Specifications, NUREG-143X, issued by the NRC Staff, revising the Technical Specifications to reflect the approved level of detail, which indicates that there is no signiticant reduction in l the margin of safety.
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10 CFR 50.92 EVALUATION FOR I LESS RESTRICTIVE CHANGES - CATEGORY 1 RELAXATION OF LCO REQUIREMENTS The (Name] Power Station is adopting NRC approved TSTF-XXX, TSTF-XXX, and TSTF-XXX generic changes to the Improved Standard Technical Specifications (ISTS) as outlined in NUREG-143X, " Standard Technical Specifications, [Name] Plants." The proposed changes involve relaxation of the current Technical Specification (TS) Limiting Conditions for Operation (LCOs) by the elimination of specific items from the LCO or Tables referenced in the LCO, or the addition of exceptions to the LCO.
These changes reflect the ISTS approach to provide LCO requirements that specify the protective conditions that are required to meet safety analysis assumptions for required features. These conditions replace the lists of specific l devices used in the TS to describe the requirements needed to meet the safety analysis assumptions. The ISTS also include LCO Notes which allow exceptions to the LCO for the performance ::f testing or other operational deeds. l The change provides the protection required by the safety analysis and provides flexibility for meeting the conditions i without adversely effecting operations since equivalent features are required to be OPERABLE. The change is also consistent with the plant current licensing basis, and these changes have been evaluated to not be detrimental to plant safety, In accordance with the criteria set forth in 10 CFR 50.92, the [name] Company has evaluated these proposed Technical Specification changes and determined they do not represent a significant hazards consideration. The following is provided in support of this conclusion.
- 1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?
The proposed change provides less restrictive LCO requirements for operation of the facility. These less restrictive LCO requirements do not result in operation that will increase the probability of initiating an analyzed event and do not alter assumptions relative to mitigation of an accident or transient event in that l the requirements continue to ensure process variables, structures, systems, and components are maintained l consistent with the current safety analyses and licensing basis. Therefore, this change d es not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the change create the possibility of a new or different Idnd of accident from any accident previously evaluated?
The proposed change does not involve a physical alteration of the plant (no new or different type of equipment will be installed) or a change in the methods governing normal plant operation. The proposed change does impose different requirements. However, the change is consistent with the assumptions in the current safety analyses and licensing basis. Thus, this change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does this change involve a significant reduction in a margin of safety?
The imposition of less restrictive LCO requirements does not involve a significant reduction in the margin of safety. As provided in the justification, this change has been evaluated to ensure that the current safety analyses and licensing basis requirements are maintained. Therefore, this change does not involve a significant reduction in a margin of safety.
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10 CFR 50.92 EVALUATION FOR LESS RESTRICTIVE CHANGES - CATEGORY 2 RELAXATION OF APPLICABILITY The [Name) Power Station is adopting NRC approved TSTF-XXX, TSTF-XXX, and TSTF-XXX generic changes to the Improved Standard Technical Specifications (ISTS) as outlined in NUREG-143X, " Standard Technical Specifications, [Name] Plants." The proposed changes involve relaxation of the applicability of current Technical Specification (TS) Limiting Conditions for Operation (LCOs) by reducing the conditions under which the LCO requirements must be met.
TS requirements may also be climinated during conditions for which the safety function of the specified safety system is met because the feature is performing its intended safety function. Deleting applicability requirements that are indeterminate or which are inconsistent with application of accident analyses assumptions is acceptable because when LCOs cannot be met, the TS may be satisfied by exiting the applicability which takes the plant out of the conditions that require the safety system to be OPERABLE.
This change provides the protection required by the safety analysis and provide flexibility for meeting limits by restricting the application of the limits to the conditions assumed in the safety analyses. The change is also consistent with the plant current licensing basis, as may be modified in the discussion of individual changes. The change is generally made to conform with NUREG-143X and has been evaluated to not be detrimental to plant safety.
In accordance with the criteria set forth in 10 CFR 50.92, the [name] Company has evaluated these proposed Technical Specification changes and determined they do not represent a significant hazards consideration. The following is provided in support of this conclusion.
- 1. Does the change involve a significant lacrease in the probability or consequences of an accident previously evaluated?
The proposed change relaxes the conditions under which the LCO requirements for operation of the facility must be met. These less restrictive applicability requirements for the LCOs do not result in operation that will increase the probability ofinitiating an analyzed event and do not alter assumptions relative to mitigation of an accident or transient event in that the requirements continue to ensure that process variables, structures, systems, and components are maintained in the MODES and other specified conditions assumed in the safety analyses and licensing basis. Therefore, this change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?
The proposed change does not involve a physical alteration of the plant (no new or different type of equipment will be installed) or a change in the methods governing normal plant operation. The proposed ,
change does impose different requirements. However, the requirements are consistent with the assumptions in the safety analyses and licensing basis. Thus, this change does not create the possibility of a new or different kind of accidert from any accident previously evaluated.
- 3. Does this change involve a significant reduction in a margin of safety?
The relaxed applicability of LCO requirements does not involve a significant reduction in the margin of safety. As provided in the justification, this change has been evaluated to ensure that the LCO requirements l are applied in the MODES and specified conditions assumed in the safety analyses and licensing basis. l Therefore, this change does not involve a significant reduction in a margin of safety.
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1 10 CFR 50.92 EVALUATION FOR LESS RESTRICTIVE CHANGES - CATEGORY 3 RELAXATION OF COMPLETION TIME The [Name) Power Station is adopting NRC approved TSTF-XXX TSTF-XXX, and TSTF-XXX generic changes to the Improved Standard Technical Specifications (ISTS) as outlined in NUREG-143X, " Standard Technical Specifications, [Name) Plants." The proposed changes involve relaxation of the Completion Times for Required Actions in the current Technical Specifications (TS).
Upon discovery of a failure to meet an LCO, the TS specifies times for completing Required Actions of the associated TS Conditions. Required Actions of the associated Conditions are used to establish remedial measures that must be taken within specified Completion Times. These times define limits during which operation in a degraded condition is permitted. Adopting these Completion Times is acceptable because the Completion Times take into account the operability status of the redundant systems of required features, the capacity and capability of remaining features, a reasonable time for repairs or replacement of required features, and the low probability of a DB A occurring during the repair period. In addition, the ISTS provides consistent Completion Times for similar conditions. These changes have been evaluated to not be detrimental to plant safety.
In accordance with the criteria set forth in 10 CFR 50.92, the [name] Company has evaluated these proposed Technical Specification changes and determined they do not represent a significant hazards consideration. The following is provided in support of this conclusion.
- 1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?
The proposed change relaxes the Completion Time for a Required Action. Required Actions and their associated Completion Times are not initiating conditions for any accident previously evaluated and the accident analyses do not assume that required equipment is out of service prior to the analyzed event.
Consequently, the relaxed Completion Time does not significantly increase the probability of any accident previously evaluated. The consequences of an analyzed accident during the relaxed Completion Time are the same as the consequences during the existing Completion Time. As a result, the consequences of any accident previously evaluated are not significantly increased. Therefore, this change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the change create the possibility of a new or different Idad of accident from any accident previously evaluated?
The proposed change does not involve a physical alteration of the plant (no new or different type of equipment will be installed) or a change in the method governing normal plant operation. The Required i Actions and associated Completion Times have been evaluated to ensure that no new accident initiators are introduced. Thus, this change does not create the possibility of a new or different kmd of accident from any accident previously evaluated.
- 3. Does this change involve a significant reduction in a margin of safety?
The relaxed Completion Time for a Required Action does not involve a significant reduction in the margin of safety. As provided in the justification, the change has been evaluated to ensure that the allowed Completion Time is consistent with safe operation under the specified Condition, c:ensidering the operability status of the redundant systems of required features, the capacity and capability of remaining features, a reasonable time for repairs or replacement of required features, and the low probability of a DB A occurring during the repair period. Therefore, this change does not involve a significant reduction in a margin of safety.
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RELAXATION OF REQUIRED ACTION The [Name) Power Station is adopting NRC approved TSTF-XXX, TSTF-XXX, and TSTF-XXX generic changes to j the Improved Standard Technical Specifications (ISTS) as outlined in NUREG-143X, " Standard Technical j Specifications, [Name] Plants." The proposed changes involve relaxation of the Required Actions in the current l Technical Specifications (TS). l Upon discovery of a failure to meet an LCO, the TS specifies Required Actions to complete for the associated Conditions. Required Actions of the associated Conditions are used to establish remedial measures that must be I taken in response to the degraded conditions. These actions minimize the risk associated with continued operation while providing time to repair inoperable features. Some of the Required Actions are modified to place the plant in a MODE in which the LCO does not apply. Adopting Required Actions from these change is acceptable because the Required Actions take into account the operability status of redundant systems of required features, the capacity and capability of the remaining features, and the compensatory attributes of the Required Actions as compared to the LCO requirements. These changes have been evaluated to not be detrimental to plant safety.
In accordance with the criteria set forth in 10 CFR 50.92, the [name) Company has evaluated these proposed Technical Specification changes and determined they do not represent a significant hazards consideration The following is provided in support of this conclusion.
- 1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?
l The proposed change relaxes Required Actions. Required Actions and their associated Completion Times I are not initiating conditions for any accident previously evaluated and the accident analyses do not assume that required equipment is out of service prior to the analyzed event. Consequently, the relaxed Required Actions do not significantly increase the probability of any accident previously evaluated. The Required Actions in the change have been developed to provide assurance that appropriate remedial actions are taken in response to the degraded condition considering the operability status of the redundant systems of required features, and the capacity and capability of remaining features while minimizing the risk associated with continued operation. As a result, the consequences of any accident previously evaluated are not significantly increased. Therefore, this change does not involve a significant increase in the probab:lity or consequences of an accident previously evaluated.
- 2. Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?
The proposed change does not involve a physical alteration of the plant (no new or different type of equipment will be installed) or a change in the methods governing normal plant operation. The Required Actions and associated Completion Times in the change have been evaluated to ensure that no new accident initiators are introduced. Thus, this change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does this change involve a significant reduction in a margin of safety?
The relaxed Required Actions do not involve a significant reduction in the margin of safety. As provided in '
the justification, this change has been evaluated to minimize the risk of continued operation under the specified Condition, considering the operability status of the redundant systems of required features, the capacity and capability of remaining features, a reasonable time for repairs or replacement of required features, and the low probability of a DBA occurring during the repair period. Therefore, this change does not involve a significant reduction in a margin of safety.
10 CFR 50.92 EVALUATION FOR I l
l LESS RESTRICTIVE CHANGES - CATEGORY 5 DELETION OF SURVEILLANCE REQUIREMENT The'[Name] Power Station is adopting NRC approved TSTF-XXX TSTF-XXX, and TSTF-XXX generic changes to the Improved Standard Technical Specifications (ISTS) as outlined in NUREG-143X, " Standard Technical Specifications, [Name] Plants." The proposed changes involve deletion of Surveillance Requirements in the current Technical Specifications (TS).
The TS require safety systems to be tested and verified Operable prior to entering applicable operating conditions.
These changes climinate unnecessary TS Surveillance Requirements that do not contribute to verification that the equipment used to meet the LCO can perform its required functions. Thus, appropriate equipment continues to be
~ tested in a manner and at a frequency necessary to give confidence that the equipment can perform its assurged safety function. These changes have been evaluated to not be detrimental to plant safety.
In accordance with the criteria set forth in 10 CFR 50.92, the [name) Company has evaluated these proposed Technical Specification changes and determined they do not represent a significant hazards consideration. The following is provided in support of this conclusion.
- 1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?
The proposed change deletes Surveillance Requirements. Surveillances are not initiators to any accident previously evaluated. Consequently, the probability of an accident previously evaluated is not significantly increased. The equipment being tested is still required to be Operable and capable of performing the accident mitigation functions assumed in the accident analysis. As a result, the consequences of any accident previously evaluated are not significantly effected. Therefore, this change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?
The proposed change does not involve a physical alteration of the plant (no new or different type of equipment will be installed) or a change in the methods governing normal plant operation. The remaining Surveillance Requirements are consistent with industry practice and are considered to be sufficient to prevent the removal of the subject Surveillances from creating a new or different type of accident. Thus, this change does not create the possibility of a new or different kind of accident from any accident
, previously evaluated.
- 3. Does this change involve a significant reduction in a margin of safety?
The deleted Surveillance Requirements do not result in a sigr.ificant reduction in the margin of safety. As provided in the justification, the change has been evaluated to ensure that the deleted Surveillance Requirements are not necessary for verification that the equipment used to meet the LCO can perform its required functions. Thus, appropriate equipment continues to be tested in a manner and at a frequency necessary to give confidence that the equipment can perform its assumed safety function. Therefore, this change does not involve a significant reduction in a margin of safety.
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10 CFR 50.92 EVALUATION FOR LESS RESTRICTIVE CHANGES - CATEGORY 6 RELAXATION OF SURVEILLANCE REQUIREMENT ACCEPTANCE CRITERIA The-[Name] Power Station is adopting NRC approved TSTF-XXX, TSTF XXX, and TSTF-XXX generic changes to the Improved Standard Technical Specifications (ISTS) as outlined in NUREG-143X, " Standard Technical Specifications, [Name] Plants." The proposed changes involve the relaxation of Surveillance Requirements acceptance criteria in the current Technical Specifications (TS).
The TS require safety systems to be tested and verified Operable prior to entering applicable operating conditions.
The changes eliminate or relax the Surveillance Requirement acceptance criteria that do not contribute to verification that the equipment used to meet the LCO can perform its required functions. When combined, remaining Surveillance Requirement acceptance criteria include Operability verification of all TS required components, for the features specified in the TS. Changes which provide exceptions to Surveillance Requirements to provide for variations which do not effect the results of the test are also included in this category. These changes have been evaluated to not be detrimental to plant safety.
In accordance with the criteria set forth in 10 CFR 50.92, the [name] Company has evaluated these proposed Technical Specification changes and determined they do not represent a significant hazards consideration. The following is provided in support of this conclusion.
- 1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?
The proposed change relaxes the acceptance criteria of Surveillance Requirements. Surveillances are not initiators to any accident previously evaluated. Consequently, the probability of an accident previously evaluated is not significantly increased. The equipment being tested is still required to be Operable and capable of performing the accident mitigation functions assumed in the accident analysis. As a result, the consequences of any accident previously evaluated are not significantly effected. Therefore, this change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the change create the possibility of a new or different kind of accident from any accident l previously evaluated?
i The proposed change does not involve a physical alteration of the plant (no new or different type of equipment will be installed) or a change in the methods governing normal plant operation. Thus, this change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does this change involve a significant reduction in a margin of safety?
The relaxed acceptance enteria for Surveillance Requirements do not result in a significant reduction in the margin of safety. As provided in the justification, the relaxed Surveillance Requirement acceptance criteria have been evaluated to ensure that they are sufficient to verify that the equipment used to meet the LCO can perform its required functions. Thus, appropriate equipment continues to be tested in a manner that gives confidence that the equipment can perform its assumed safety function. Therefore, this change does not involve a significant reduction in a margin of safety.
10 CFR 50.92 EVALUATION FOR LESS RESTRICTIVE CHANGES - CATEGORY 7 RELAXATION OF SURVEILLANCE FREQUENCY The [Name] Power Station is adopting NRC approved TSTF-XXX, TSTF-XXX, and TSTF-XXX generic changes to the Improved Standard Technical Specifications (ISTS) as outlined in NUREG-143X, " Standard Technical Specifications [Name] Plants." The proposed changes involve the relaxation of Surveillance Frequencies in the current Technical Specifications (TS).
Surveillance Frequencies specify time interval requirements for performing surveillance testing. Increasing the time interval between Surveillance tests results in decreased equipment unavailability due to testing which also increases equipment availability. Reduced testing can result in a safety enhancement because the unavailability due to testing is reduced and; in turn, reliability of the effected structure, system or component should temain constant or increase.
Reduced testing is acceptable where operating experience, industry practice or the industry standards such as manufacturers' recommendations have shown that these components usually pass the Surveillance when performed at the specified interval, thus the frequency is acceptable from a reliability standpoint. These changes have been found to be acceptable based on a combination of the above criteria and have been evaluated to not be detrimental to plant safety.
In accordance with the criteria set forth in 10 CFR 50.92, the [name] Company has evaluated these proposed r Technical Speci^ation changes and determined they do not represent a significant hazards consideration. The following is pro %d in support of this conclusion.
{
Does L change involve a significant increase in the probability or consequences of an accident l
- 1. l pres 'ly evaluated?
The proposed change relaxes Surveillance Frequencies. The relaxed Surveillance Frequencies have been established based on achieving acceptable levels of equipment reliability. Consequently, equipment which could initiate an accident previously evaluated will continue to operate as expected and the probability of the initiation of any accident previously evaluated will not be significantly increased. The equipment being 1 tested is still required to be Operable and capable of performing any accident mitigation functions assumed I in the accident analysis. As a result, the consequences of any accident previously evaluated are not l significantly effected. Therefore, this change does not involve a significant increase in the probabihty or ;
consequences of an accident previously evaluated.
l
- 2. Does the change create the possibility of a new or different kind of accident from any accident !
previously evaluated?
The proposed change does not involve a physical alteration of the plant (no new or different type of equipment will be installed) or a change in the methods governing normal plant operation. Thus, this change does not create the possibility of a new or different kind of ac'c ident from any accident previously evaluated.
- 3. Does this change involve a significant reduction in a margin of safety?
The relaxed Surveillance Frequencies do not result in a significant reduction in the margin of safety. As provided in the justification, the relaxation in the Surveillance Frequency has been evaluated to ensure that it provides an acceptable level of equipment reliability. Thus, appropriate equipment continues to be tested at a Frequency that gives confidence that the equipment can perform its assumed safety function when required. Therefore, this change does not involve a significant reduction in a margin of safety.
F , . -
- 10 CFR 50.92 EVALUATION l.
FOR LESS RESTRICTIVE CHANGES
[SECTION XX / SPECIFICATION XX]
ONLY TO BL USED IF CHANGE DOES NOT FIT ONE OF THE 7 SPECIFIC CATEGORIES ABOVE The (Name) Power Station is adopting NRC approved TSTF-XXX TSTF-XXX, and TSTF-XXX generic changes to the Improved Standard Technical Specifications (ISTS) as outlined in NUREG-143X, " Standard Technical Specifications, (Name) Plants." The proposed change involves making the current Technical Specifications (TS) less restrictive. Below is the description of this less restrictive change and the determination of No Significant Hazards Considerations for conversion to NUREG-143X.
Copyjustification here.
In accordance with the criteria set forth in 10 CFR 50.92, the [name) Company has evaluated these proposed Technical Specification changes and determined they do not represent a significant hazards consideration. The following is provided in support of this conclusion.
l '
i
- 1. Does the change involve a significant increase in the probabliity or consequences of an accident previously evaluated?
(Use generic changejustification to develop discussion)
As a result, the change does not significantly increase the probability or consequences of an accident l
- previously analyzed.
- 2. Does the change create the possibility of a new or different kind of accident from any accident j previously evaluated? !
l l
The change does not introduce a new mode of plant operation and does not involve physical modification to the plant. The change will not introduce new accident initiators. Therefore, it does not create the j possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does this change involve a significant reduction in a margin of safety?
(Use generic change justification to develop discussion)
As a result, the change does not significantly increase the probability or consequences of an accident previously analyzed.
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