HNP-96-172, Application for Amend to License NPF-63,revising TSs Re Ultimate Heat Sink Level & Temp
| ML18012A414 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 10/31/1996 |
| From: | Robinson W CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18012A415 | List: |
| References | |
| HNP-96-172, NUDOCS 9611060148 | |
| Download: ML18012A414 (15) | |
Text
CATEGORY 1 iREGULAT INFORMATION DZSTRIBUTIOhit'.STEM (RIDE)
ACCESS'jO'N NBR:9611060148 DOC.DATE: 96/10/31 NOTARIZED: YES FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME 'UTHOR AFFILIATION ROBINSON,W.R.
Carolina Power 6 Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Application for amend to license NPF-63,revising TSs re ultimate heat sink level 6 temp.
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TITLE: OR Submittal: General Distribution NOTES:Application for permit renewal filed.
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E NOTE TO ALL "RIDS" RECIPIENTS:
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Carolina Power &Light Company PO Box 165 New Hill NC 27562 William R. Robinson Vice President Harris Nuclear Plant SERIAL: HNP-96-172 10 CFR 50.90 OCT 3> 1996 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEARPOWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT ULTIMATEHEAT SINKLEVELANDTEMPERATURE
Dear Sir or Madam:
In accordance with the Code ofFederal Regulations, Title 10, Part 50.90, Carolina Power &
Light Company (CP&L) requests a revision to the Technical Specifications (TS) for the Harris Nuclear Plant (HNP). The proposed amendment to TS 3/4.7.5, Ultimate Heat Sink, willreduce the maximum allowable water temperature from 95'F to 94'F and willincrease the minimum main reservoir level from 205.7 feet mean sea level to 215 feet mean sea level.
These changes are based on calculations and analyses revised or created during review ofNRC Generic Letter 89-13 implementation and the Self-Service Water Operational Performance Inspection (SSWOPI) conducted by CP&L and outside consultants at HNP.
Enclosure 1 provides a description ofthe proposed changes and the basis for the changes. details, in accordance with 10 CFR 50.91(a), the basis for the Company's determination that the proposed changes do not involve a significant hazards consideration. provides an environmental evaluation which demonstrates that the proposed amendment meets the eligibilitycriteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Therefore, pursuant to 10 CFR 51.22(b), no environmental assessment needs to be prepared in connection with the issuance ofthe amendment. provides page change instructions for incorporating the proposed revisions. provides the proposed Technical Specification pages.
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PDR State Road 1134 New Hill NC Tel 919 362-2502 fax 919 362-2095 (Lol
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Document'ontrol Desk HNP-96-172 / Page 2 In accordance with 10 CFR 50.91(b), CPkL is providing the State ofNorth Carolina with a copy of the proposed license amendment.
COL requests that the proposed amendment be issued such that implementation willoccur within 60 days of issuance to allow time for procedure revision and orderly incorporation into copies ofthe Technical Specifications.
Please refer any questions regarding this submittal to Ms. Donna Alexander at (919) 362-3190.
Sincerely, LSR/lsr
Enclosures:
- 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 first duly 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 of his information are employees, contractors, and agents ofCarolina Power A Light Company.
Mycommission expires:
c:
Mr. J. B. Brady, NRC Senior Resident Inspector Mr. Dayne H. Brown, N.C. DEHNR Mr. S. D. Ebneter, NRC Regional Administrator Mr. N. B. Le, NRC Project Manager Notary (S al)
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ENCLOSURE TO SERIAL: HNP-96-172 ENCLOSURE 1
SHEARON HARRIS NUCLEARPOWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT ULTIMATEHEATSINKLEVELANDTEMPERATURE BASIS FOR CHANGE RE UEST Pro osed Chan e
The proposed amendment to TS 3/4.7.5, Ultimate Heat Sink, willreduce the maximum allowable water temperature as measured at the respective intake structures from 95'F to 94'F and will increase the minimum main reservoir level from 205.7 feet mean sea level to 215 feet mean sea level.
These changes are based on calculations and analyses revised or created during review of NRC Generic Letter 89-13 implementation and the Self-Service Water Operational Performance Inspection (SSWOPI) conducted by CP&L and outside consultants at the Harris Nuclear Plant (HNP).
Basis As defined in NRC Regulatory Guide 1.27, the ultimate heat sink (UHS) is that complex ofwater sources, including necessary retaining structures, and the canals or conduits connecting the sources within, but not including, the cooling water system intake structures for a nuclear power unit. The UHS performs two principal safety functions: (1) dissipation ofresidual heat after reactor shutdown, and (2) dissipation ofresidual heat after an accident. At HNP, the sources of water for normal and emergency cooling are the Cooling Tower and the Main or Auxiliary Reservoirs.
The normal source ofplant service water is the circulating water Cooling Tower.
The preferred sources ofemergency cooling water, ifthe Cooling Tower is not available, is the AuxiliaryReservoir.
The backup source ofemergency service water is the Main Reservoir.
Emergency service water from either source is discharged to the AuxiliaryReservoir.
During late 1994, CP&Linitiated two detailed reviews of the Emergency Service Water System (ESWS) at HNP. The first review focused on the status ofthe NRC Generic Letter 89-13 program.
Concurrent with that effort, a Self-Service Water System Operational Performance Inspection (SSWOPI) was conducted.
The SSWOPI followed NRC Temporary Instruction 2515/118, "Service Water System Operational Performance Inspection" and NRC Inspection Procedure 40501, "Licensee Self-Assessments Related to Area-of-Emphasis Inspections."
During both of these reviews, issues were raised regarding the techniques and acceptance criteria used in the ESWS flow balance procedure.
Accordingly, CP&Lperformed an indepth review of the Technical Specification requirements for UHS level and temperature.
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ENCLOSURE TO SERIAL: HNP-96-172 A calculation was performed using a hydraulic model ofthe ESWS to determine flowrates to safety-related heat exchangers cooled by the ESWS. The calculation provided the minimum test flow requirement for each heat exchanger as a function of reservoir level which would ensure adequate heat removal. Required test flow was determined for a range ofreservoir levels, including the current Technical Specification minimum reservoir level of 205.7 feet mean sea level and at an assumed administrative limitof215 feet mean sea level. This administrative limitwas chosen based on historical data on main reservoir level. Under worst case conditions, at the Technical Specification minimum of205.7 feet and a maximum inlet temperature of95'F (the plant equipment design limit),ESWS flow would be inadequate to ensure design required heat removal by safety-related heat exchangers.
However, a minimum main reservoir level of 215 feet would ensure adequate heat removal under worst case conditions (inlet temperature of95'F).
Therefore, a plant administrative limitof215 feet has been established, pending NRC approval to change the minimum allowable main reservoir level from 205.7 feet to 215 above mean sea level in the HNP Technical Specifications.
Additionally, CP&Lwillrevise the Final Safety Analysis Report to clarify the difterence between the analyzed minimum main reservoir level necessary for heat sink dependability and the minimum main reservoir level needed to ensure adequate flow to safety-related heat exchangers cooled by the ESWS.
With respect to reservoir temperature, a new analysis was performed using meteorological conditions that would maximize inlet water temperature: high solar heating, high ambient air temperature, high relative humidity, and low wind speed.
The analysis used as input the worst meteorology for a one day period, which occurred on June 27, 1952, and the worst meterology for a one month period, which occurred between July 18 and August 15, 1949. Based on this input, average values for the meteorological conditions for 1-day and 30-day periods were used to estimate the maximum service water inlet temperature.
The limiting analysis calculated a maximum pre-accident reservoir temperature of94.2'F using a composite 10-day period including the worst 9-day consecutive meteorology (July 22, 1949 to July 30, 1949) plus the worst 1-day meteorology (June 27, 1952). The analysis also determined that a pre-accident reservoir temperature of94.2'F would result in a final temperature of95.12'F 30 days after a LOCA.
Conservatively assuming a 1.0'F temperature drop due to thermal stratification, the final temperature would be 94.97'F, which is less than the current equipment design limitof95'F.
Therefore, a maximum pre-accident temperature of94'F was also imposed as a plant administrative limit, pending NRC approval ofthe change from 95'F to 94'F in the HNP Technical Specifications.
Conclusions Based upon calculations and analyses peformed as a result ofthe NRC Generic Letter 89-13 review and the Self-Service Water System Operational Performance Inspection, COL proposes to revise the Technical Specification 3/4.7.5 to reduce the maximum allowable water temperature as measured at the respective intake structures from 95'F to 94'F and to increase the minimum main reservoir level from 205.7 feet mean sea level to 215 feet mean sea level.
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ENCLOSURE TO SERIAL: HNP-96-172 ENCLOSURE 2 SHEARON HARRIS NUCLEARPOWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT ULTIMATEHEAT SINKLEVELANDTEMPERATURE 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 facility involves no significant hazards consideration ifoperation ofthe facilityin accordance with the proposed amendment would not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility ofa new or different kind ofaccident from any accident previously evaluated, or (3) involve a significant reduction in a margin ofsafety.
Carolina Power &Light Company 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 amendment to TS 3/4.7.5, Ultimate Heat Sink, willreduce the maximum allowable water temperature as measured at the respective intake structures from 95'F to 94'F and will increase the minimum main reservoir level from 205.7 feet mean sea level to 215 feet mean sea level.
These changes are based on calculations and analyses revised or created during review of NRC Generic Letter 89-13 implementation and the Self-Service Water Operational Performance Inspection (SSWOPI) conducted by CP&Land outside consultants at the Harris Nuclear Plant (HNP).
Basis This change does not involve a significant hazards consideration for the followingreasons:
1.
The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
Since the proposed change does not affect the operation of any accident initiating systems, the probability ofoccurrence of an accident previously evaluated willnot increase.
- Also, none ofthe proposed changes willcause plant systems to operate outside their design limits or create the likelihood ofa radioactive release.
Therefore, there would be no increase in the consequences of an accident previously evaluated.
2.
The proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
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ENCLOSURE TO SERIAL: HNP-96-172 No new component or system level interactions willbe created by the proposed change in ultimate heat sink level and temperature, and no design limits willbe exceeded.
This change to Specification 3/4.7.5 is more conservative than the current Specification limits and willserve only to restrict operation to a higher reservoir level and lower temperature than was previously allowed.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
3.
The proposed amendment does not involve a significant reduction in the margin of safety.
The proposed amendment willestablish a more conservative minimum main reservoir level such that safety-related heat exchangers served by Emergency Service Water willcontinue to remove their design-basis accident heat loads.
Establishing a higher minimum reservoir level, combined with a more conservative reservoir temperature assumption, willinvolve an increase in the margin ofsafety.
Also, the proposed change in maximum reservoir temperature from 95'F to 94'F willnot result in any reduction in the margin ofsafety. A maximum pre-accident initial water temperature of94'F is necessary to yield a post-accident (30-day) calculated maximum inlet temperature less than or equal to the design basis temperature of95'F. Therefore, the proposed change does not involve a significant reduction in the margin ofsafety.
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ENCLOSURE TO SERIAL: HNP-96-172 ENCLOSURE 3 SHEARON HARRIS NUCLEARPOWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT ULTIMATEHEAT SINKLEVELANDTEMPERATURE ENVIRONMENTALCONSIDERATIONS 10 CFR 51.22(c)(9) provides criterion for and identification of licensing and regulatory actions eligible for categorical exclusion from performing an environmental assessment.
A proposed amendment to an operating license for a facilityrequires no environmental assessment ifoperation of the facilityin accordance with the proposed amendment would not: (1) involve a significant hazards consideration; (2) result in a significant change in the types or significant increase in the amounts of any effluents that may be released offsite; (3) result in a significant increase in individual or cumulative occupational radiation exposure.
Carolina Power &Light Company has reviewed this request and determined that the proposed amendment meets the eligibilitycriteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance ofthe amendment.
The basis for this determination follows:
Pro osed Chan e
The proposed amendment to TS 3/4.7.5, Ultimate Heat Sink, willreduce the maximum allowable water temperature as measured at the respective intake structures from 95'F to 94'F and will increase the minimum main reservoir level from 205.7 feet mean sea level to 215 feet mean sea level.
These changes are based on calculations and analyses revised or created during review of NRC Generic Letter 89-13 implementation and the Self-Service Water Operational Performance Inspection (SSWOPI) conducted by CP&L and outside consultants at the Harris Nuclear Plant (HNP).
Basis The change meets the eligibilitycriteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) for the followingreasons:
1 ~
As demonstrated in Enclosure 2, the proposed amendment does not involve a significant hazards consideration.
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ENCLOSURE TO SERIAL: HNP-96-172 2.
The proposed amendment does not result in a significant change in the types or significant increase in the amounts ofany effluents that may be released offsite.
The proposed change does not introduce any new equipment or require existing systems to perform a different function than they are currently designed to perform. The change does not introduce any new effluents or increase the quantities ofexisting effluents. As such, the change can not affect the types or amounts of any effluents that may be released offsite.
The proposed amendment does not result in a significant increase in individual or cumulative occupational radiation exposure.
The proposed change does not result in any physical plant changes or new surveillances and willnot require additional personnel entry into the radiation-controlled areas ofthe plant. Therefore, the amendment has no affect on either individual or cumulative occupational radiation exposure.
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ENCLOSURE4 SHEARON HARRIS NUCLEARPOWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT ULTIMATEHEAT SINKLEVELANDTEMPERATURE PAGE CHANGE INSTRUCTIONS Removed Pa e 3/4 7-13 Inserted Pa e
3/4 7-13