HNP-96-031, Application for Amend to License NPF-63,relocating TS 3.3.3.2, Movable Incore Detectors & Associated Bases, Consistent w/NUREG-1431 & GL 95-10
| ML18012A180 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 03/20/1996 |
| From: | Robinson W CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18012A182 | List: |
| References | |
| RTR-NUREG-1431 GL-95-10, HNP-96-031, HNP-96-31, NUDOCS 9603250343 | |
| Download: ML18012A180 (11) | |
Text
CATEGORY 1 "REGULATO ~ INFORMATION DISTRIBUTION STEM (RIDS)
ACCESSION NBR:9603250943 DOC.DATE: 96/03/20 NOTARIZED: YES, FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME AUTHOR AFFILIATION ROBINSON,W.R.
Carolina Power
& Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Application for amend to license NPF-63,relocating TS 3.3.3.2, "Movable Incore Detectors"
&.'associated
- bases, consistent w/NUREG-1431
& GL 95-10.
DISTRIBUTION CODE:
AOOZD. COPIES RECEIVED:LTR i
ENCLi SIZE:
TITLE: OR Submittal: General Distribution NOTES:Application for permit renewal filed.
DOCKET 05000400 05000400 E
RECIPIENT ID CODE/NAME PD2-1 LA LE,N INTERNAL: ACRS NRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT EXTERNAL: NOAC COPIES LTTR ENCL 1
1 1
1 6
6 1
1 1
1 1
1 1
1 RECIPIENT ID CODE/NAME PD2-1 PD LE CENTER 01 NR /5M'/HTCM NRR/DSSA/SRXB OGC/HDS2 NRC PDR COPIES LTTR ENCL 1
1
]
ii
]
1 1
1 1
1 0
1 1
D E
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!
CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415-2083)
TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDt TOTAL NUMBER OF COPIES REQUIRED:
LTTR 18 ENCL i 17
Carolina Power & Light Company PO Box 165 New Hill NC 27562 William R. Robinson Vice President Harris Nuclear Plant MAR 20 1996 SERIAL: HNP-96-031 10 CFR 50.90 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEARPOWER PLANT DOCKETNO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT MOVABLEINCORE DETECTORS Gentlcmcn:
In accordance with thc Code ofFederal Regulations, Title 10, Parts 50.90 and 2.101, Carolina Power &Light Company (CP&L)hereby requests a revision to the Technical Specifications (TS) for the Harris Nuclear Plant (HNP). This amendment proposes to relocate Tcchnical Specification 3.3.3.2, "Movable Incorc Detectors," and associated Bases, consistent withNUREG-143 land NRC Generic Letter 95-10. The proposed relocation is also consistent with the Commission's Final Policy Statement for the relocation ofTechnical Specifications.
Enclosure 1 provides a detailed description of thc proposed changes and thc basis for the changes. details, in accordance with 10 CFR 50.91(a), the basis for thc Company's determination that the proposed changes do not involve a significant hazards consideration. provides an environmental evaluation which demonstrates that thc proposed amcndmcnt meets thc eligibilitycriteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Thcrcforc, pursuant to 10 CFR 51.22(b), no cnvironmcntal asscssmcnt needs to be prcparcd in connection with the issuance ofthe amendmcnt. provides page change instructions for incorporating the proposed revisions. provides the proposed Technical Specification pages.
In accordance with 10 CFR 50.91(b), CP&Lis providing thc State ofNorth Carolina with a copy ofthc proposed license amendment.
9603250343
'F60320 PDR ADQCK 05000400 P
PDR State Road 1134 New Hill NC Tel 919362-2502 Fax 919362-2095
Document Control Desk HNP-96-031 / Page 2 Please refer any questions regarding this submittal to Mr. T. D. Walt at (919) 362-2711.
LSR/lsr Sincerely,
'nclosures:
- 1. Basis for Change Request 2.
10 CFR 50.92 Evaluation
- 3. Environmental Considerations
- 4. Page Change Instructions
- 5. Technical Specification Pages W. R. Robinson, having been firstduly sworn, did depose and say that the information contained herein is true and correct to the best ofhis information, knowledge and belief; and the sources ofhis information are employees, contractors, and agents ofCarolina Power 4 Light Company.
Mycommission eryires:
c:
Mr. Dayne H. Brown Mr. S. D. Ebneter Mr. N. B. Le Mr. D. J. Roberts Notary(S s
ggQSl Iftgpg~
g~+
y~OIARy o.
SK gag A~
Cl X'
"~~7 COuo~:"
AI!0III'E11
f II N
<> f Ilk iepr A,,l, c
ENCLOSURE TO SERIAL: HNP-96-031 ENCLOSURE 1
SHEARON HARRIS NUCLEARPOWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT MOVABLEINCORE DETECTORS BASIS FOR CHANGE RE UEST The proposed revision would relocate Tcchnical Specification (TS) 3.3.3.2, Movable Incorc Detectors, to the Harris Nuclear Plant Core Operating Limits Rcport (COLR). Future changes to the relocated provisions willbc evaluated in accordance with 10 CFR 50.59.
2.0
~Back round Section 182a ofthe Atomic Energy Act (thc Act) requires that Technical Specifications (TS) bc included as part of a liccnscc's nuclear power plant operating license. The Commission's regulatory rcquircments rclatcd to the content ofthc TS are sct forth in 10 CFR 50.36. That regulation requires that thc TS include items in five specific categories including: (1) safety limits, limitingsafety system settings and limitingcontrol settings; (2) limitingconditions for operation; (3) survcillancc rcquircments; (4) design fcaturcs; and (5) administrative controls. It also states that the Commission may include such additional TS as it finds appropriate.
However, the regulation docs not specify the particular TS to bc included in a plant's license.
The Commission has provided guidance for thc contents ofTS in its "Final Policy Statement on Technical Specification Improvements forNuclear Power Reactors" (Final Policy Statement), issued on July 22, 1993 (58 FR 39132), in which the Commission indicated that compliance with the Final Policy Statcmcnt satisfies Section 182a ofthe Act. In particular, the Commission indicated that certain items could bc relocated from the TS to licensee-controlled documents, and consistent with this approach, thc Final Policy Statement identified four criteria to bc used in determining whether a particular matter is required to bc included in the TS, as follows: (1) installed instrumentation that is used to detect, and indicate in thc control room, a significant abnormal degradation ofthc reactor coolant prcssure boundary; (2) a process variable, design fcaturc, or operating restriction that is an initialcondition of a design basis accident or transient analysis that assumes cithcr the failure of, or presents a challenge to, thc integrity of a fission product barrier; (3) a structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that cithcr assumes thc failure ofor presents a challenge to thc integrity ofa fission product barrier; (4) a structure, system, or component which operating expcricncc or probabilistic safety assessment has shown to bc significant to public health and safety. As a result, thc existing LimitingCondition for Operation (LCO) requirements that fallwithin or satisfy any ofthc criteria in the Final Policy Statcmcnt must be retained in thc TS, while those LCO rcquircmcnts which do not fall within or satisfy these criteria may be rclocatcd to other appropriate liccnsec-controlled documents.
3.0 Evaluation In November 1987, the Westinghouse Owners Group submitted to thc NRC, WCAP-11618, "Methodically Enginecrcd, Restructured and Improved Tcchnical Specifications, MERITS Program - Phase IITask 5, Criteria Application." That topical rcport applied thc Commission's screening criteria to thc Wcstinghousc Page El-1
ENCLOSURE TO SERIAL: HNP-96-031 Standard Technical Specifications (NUREG-0452, Revision 4 and Draft Revision 5). Thc NRC staff documented the results oftheir review ofWCAP-11618 in a letter dated May 9, 1988 to R.A. Newton, Chairman ofthc Westinghouse Owners Group. Among the specifications to which the scrccning criteria were applied was Standard TS Section 3/4.3.3.2, Movable Incorc Detectors.
Thc Movable Incorc Detector system is used periodically to calculate power peaking factors to verifynuclear design predictions, cnsurc operation within established fuel performance limits, and calibrate other nuclear instrumentation.
The mcasuremcnts are used in a confirmatory manner and do not provide direct input to reactor protection system or cnginecrcd safety features actuation system functions. The system is neither used for, nor capable of, dctccting a significant abnormal degradation ofthe reactor coolant pressure boundary before a design basis accident, nor does it function as a primary success path to mitigate cvcnts which assume a failure or a challenge to thc integrity offission product barriers.
Thus, thc detectors arc not an active design fcaturc needed to preclude analyzed accidents or transients.
This specification was screened against the Commission's criteria and a probabilistic risk asscssmcnt in WCAP-11618. The results are as follows:
The Movable Incore Detector Instrumentation is not installed instrumentation that is used to detect, and indicate in thc control room, a significant abnormal degradation ofthe reactor coolant pressure boundary.
The Movable Incore Detector Instrumentation does not satisfy Criterion 1; The Movable Incorc Detector Instrumentation is not a process variable that is an initial condition of a Design Basis Accident (DBA)or Transient Analysis that either assumes the failure ofor presents a challenge to thc integrity ofa fission product barrier. The Movable Incore Detector Instrumentation docs not satisfy Criterion 2; The Movable Incorc Detector Instrumentation is not a system that is part ofthc primary success path and which functions or actuates to mitigate a DBAor Transient that cithcr assumes thc failure ofor prcscnts a challenge to the integrity ofa fission product barrier.
The Movable Incore Detector Instrumentation docs not satisfy Criterion 3.
Based upon a Probabilistic Risk Assessment (PRA) Summary Rcport for thc MERITS Program contained in Section 4 ofWCAP-11618, thc Movable Incore Dctcctors werc not identified as a significant risk contributor. Thcrcforc, the Movable Incore Detector Instrumentation does not satisfy Criterion 4 for retention in the TS.
The screening criteria applied in WCAP-11618 were subscqucntly sanctioned in thc Commission's Final Policy Statcmcnt issued in July 1993. Also, thc NRC issued Generic Letter 95-10, "Relocation ofSelected Technical Specifications Rcquircmcnts Related to Instrumentation" on Dcccmber 15, 1995. The purpose of the Generic Lcttcr was to advise liccnsces that they may request license amcndmcnts to relocate sclectcd instrumentation requirements from their TS to a licensee-controlled document.
The Harris Nuclear Plant was liccnscd based on the Standard Tcchnical Specifications for Westinghouse Pressurized Water Reactors (NUREG-0452, Draft Revision 5), which was used as onc ofthc bases for application ofthc screening criteria in WCAP-11618. Thcreforc, Carolina Power &Light Company has concluded, based on the considerations discussed above, that thc Movable Incorc Detector rcquircments may bc relocated to a licensee-controlled document, subject to the provisions of 10 CFR 50.59.
Page E1-2
ENCLOSURE TO SERIAL: HNP-96-031 Thc TS requirements for TS 3.3.3.2 ivillbe relocated to plant procedure PLP-106, "Tcchnical Specification Equipment List Program and Core Operating Limits Rcport." In relocating these rcquircments to a plant procedure, CPkL >villcontinue to maintain appropriate controls to ensure that thc Movable Incore Dctcctor System is maintained operable svith a specified minimum number ofdetector thimbles availablc.
Changes to this procedure, as necessary, >villbc subjected to the requirements of,10 CFR 50.59.
TS 6.5.2, "Plant Nuclear Safety Committee (PNSC), " requires that the PNSC review proposed changes to the HNP TS. The PNSC is composed ofseven to nine members representing the engineering, operations, maintenance, health physics/chemistry, nuclear asscssmcnt, and regulatory affairs functions. A quorum consists ofthe Chairman or his designated alternate and four members, including alternates.
PNSC review and approval ofthc proposed TS change xvas coinpleted on March 13, 1996.
Page El-3
ENCLOSURE TO SERIAL: HNP-96-031 ENCLOSURE 2 SHEARON HARRIS NUCLEARPOWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT MOVABLEINCORE DETECTORS 10 CFR 50.92 EVALUATION The Commission has provided standards in 10 CFR 50.92(c) for determining whether a significant hazards consideration exists. A proposed amendment to an operating license for a facilityinvolves no significant hazards consideration ifoperation ofthe facilityin accordance with the proposed amendment would not: (1) involve a significant incrcasc in the probability or conscqucnccs ofan accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously cvaluatcd, or (3) involve a significant reduction in a margin ofsafety.
Carolina Power &LightCompany has reviewed this proposed license amendment request and determined that its adoption would not involve a significant hazards determination.
The bases for this determination are as follows:
Pro osed Chan e
The proposed revision would relocate Technical Specification (TS) 3.3.3.2, Movable Incore Detectors, to thc Harris Nuclear Plant Core Operating Limits Report (COLR). Future changes to the located provisions will be evaluated in accordance with 10 CFR 50.59.
Basis This change does not involve a significant hazards consideration for the followingreasons:
1.
The proposed amendment does not involve a significant increase in thc probability or consequences ofan accident previously evaluated.
The proposed change willsimplifythe Tcchnical Specifications, while implementing thc recommendations ofthc Commission's Final Policy Statcmcnt on TS Improvements.
The changes are administrative in nature and do not involve any modifications to plant cquipmcnt or affect plant operation.
Since the TS provisions are being relocated to a licensee-controlled document, any future changes willbe controlled under 10 CFR 50.59. Thcrcfore, there would be no increase in the probability or consequences ofan accident previously evaluated.
The proposed amendment does not crcatc the possibility ofa new or different kind ofaccident from any accident previously evaluated.
The proposed change is a relocation ofexisting Technical Specification provisions. It does not involve any physical alterations to plant cquipmcnt or alter thc method by which any safety-related system performs its function. Thercforc, thc proposed changes do not create the possibility of a ncw or different kind ofaccident from any accident previously cvaluatcd.
Page E2-1
ENCLOSURE TO SERIAL: HNP-96-031 Thc proposed amcndmcnt docs not involve a significant reduction in the margin ofsafety.
Thc proposed change docs not affect any Final Safety Analysis Report (FSAR) Chapter 15 accident analyses or have any impact on margin as dcfincd in thc Bases to thc Technical'Specifications.
Therefore, the proposed changes do not involve a significant reduction in a margin ofsafety.
Page E2-2
ENCLOSURE TO SERIAL: HNP-96-031 ENCLOSURE 3 SHEARON HARRIS NUCLEARPOWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT MOVABLEINCORE DETECTORS ENVIRONMENTALCONSIDERATIONS 10 CFR 51.22(c)(9) provides criterion for and identification oflicensing and regulatory actions eligible for categorical exclusion from performing an environmental asscssmcnt.
A proposed amendment to an operating license for a facilityrequires no environmental assessment ifoperation ofthe facilityin accordance with the proposed amendment would not: (I) involve a significant hazards consideration; (2) result in a significant change in thc types or significant increase in thc amounts ofany efflucnts that may be rclcased offsitc; (3) result in a significant increase in individual or cumulative occupational radiation cxposurc.
Carolina Power &
Light Company has reviewed this rcqucst and determined that the proposed amcndmcnt meets the eligibility criteria for categorical exclusion sct forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental asscssmcnt needs to be prepared in connection with thc issuance ofthe amcndmcnt.
Thc basis for this dctcrmination follows:
Pro osed Chan c
The proposed revision would relocate Tcchnical Specification (TS) 3.3.3.2, Movable Incore Detectors, to thc Harris Nuclear Plant Core Operating Limits Rcport (COLR). Future changes to the located provisions will bc evaluated in accordance with 10 CFR 50.59.
Basis The change mccts thc eligibilitycriteria for categorical exclusion sct forth in 10 CFR 51.22(c)(9) for the followingreasons:
1.
As demonstrated in Enclosure 2, thc proposed amcndmcnt docs not involve a significant hazards consideration.
The proposed amcndmcnt docs not result in a significant change in the types or significant incrcasc in the amounts ofany efflucnts that may bc rclcascd offsitc.
The proposed changes are administrative in nature and do not involve any ncw equipment, or rcquirc existing systems to perform a different type offunction than they are currently designed to perform.
The change does not introduce any new cffluents or incrcasc thc quantitics ofexisting cfflucnts. As such, the change can not affect thc types or amounts ofany effluents that may be released offsitc.
Page E3-I
ENCLOSURE TO SERIAL: HNP-96-031 The proposed amendment docs not result in a significant increase in individual or cumulative occupational radiation exposure.
The proposed changes do not result in any physical plant changes or ncw surveillanccs.
Thc relocation ofTcchnical Specification (TS) provisions to liccnscc-controlled documents ivillhave no impact on radiation exposure since thc clcrncnts ofthese TS ivillbc retained and controlled under 10 CFR 50. 59.
Thcrcforc, thc amendmcnt has no affect on either individual or cumulative occupational radiation exposure.
Page E3-2