HNP-98-112, Application for Amend to License NPF-63,deleting SR 4.9.12.d.4 Which Requires Verifying That Filter Cooling Bypass Valve for Fuel Handling Bldg Emergency Exhaust Sys Is Locked in Balanced Position at Least Once Per 18 Months
| ML18016A503 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 08/14/1998 |
| From: | Scarola J CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18016A504 | List: |
| References | |
| HNP-98-112, NUDOCS 9808190129 | |
| Download: ML18016A503 (4) | |
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CATEGORY j.
REGULA RY INFORMATION DISTRIBUTIO SYSTEM (RIDS)
AlCESSION NBR:9808190129 DOC.DATE: 98/08/14 NOTARIZED: YES FACIL':50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME AUTHOR AFFILIATION SCAROLA,J.
Carolina Power
&. Light Co.
RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)
SUBJECT:
Submits response to NRC 980707 RAI re method
& assumptions used to determine temp increase of charcoal in FHB EES.
Supporting calculation info encl.
DISTRIBUTION CODE:
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General Distribution II NOTES:Application for permit renewal filed.
DOCKET 05000400 05000400 G
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Carolina Power 8 Light Company PO Box 165 New Hill NC 27562 James Scarola Vice President Harris Nuclear Plant AUG 14 1998 SERIAL:
HNP-98-112 10CFR50.90 United States Nucleiir Regulator Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEARPOWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT TECHNICALSPECIFICATIONS 3/4.9. 12 SUPPLEMENTALINFORMATION
Dear Sir or Madam:
By letter d Ited M Irch l 2, l 998, Carolina Power 8. Light Company (CPS;L) submitted a Request for License Amendment for the Harris Nuclear Plant (HNP). The proposed amendinent revises Technical Specification 3/4.9.12, "Fuel Handling Building Emergency Exhaust System".
Specifically, Harris Nuclear Plant (HNP) proposes to delete Surveillance Requirement 4.9.12.d.4 which requires verifying that the filter cooling bypass valve for the Fuel Handling Building Emergency Exhaust System is locked in the balanced position at least once per 18 months. By letter dated July 7, 1998, the NRC requested additional information regarding the method and assumptions used to determine the temperature increase ofthe charcoal in the Fuel Handling Building Emergency Exhaust System (R-IBEES). Additionally, the NRC questioned "does the method and assumptions used conform with the Chapter 15 Fuel Handling Accidents".
Enclosure 1 in conjunction with Enclosure 2 provides the response for the request for additional InfOI'n1at IOn.
These changes do not affect the conclusions of either the 10 CFR 50.92 Evaluation or the Environmental Considerations submitted as part of CPAL's March 12, 1998 letter. The proposed Technical Specification page from the March 12, 1998 letter is not affected by these changes.
Please refer any questions regarding this submittal to Mr. J. H. Eads at (919) 362-2646.
Sincerely, James Scarola 9808i90129 9808i4 PDR ADDCK 05000400 P
/oh 5413 Shearon Harris Road New Hill, NC Tel 919 362-2502 Fax 919 362-2095
MSE/mse
Enclosures:
1.
Narrative Response to Request for Additional Information 2.
Temperature Increase In Charcoal Beds Without Bleed Flow (Calculation HNP-M/FHB-1002)
James Scarola, 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. LightCompany.
Notary (Seal)
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Mr. J. B. Brady, NRC Sr. Resident Inspector Mr. Mel Fry, Acting Director, N.C. DEHNR Mr. S. C. Flanders, NRC Project Manager Mr. L. A. Reyes, NRC Regional Administrator
ENCLOSURE 1 TO SERIAL: HNP-98-112 SHEARON HARRIS NUCLEARPOWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT TECHNICALSPECIFICATION TS 3/4.9.12 SUPPLEMENTALINFORMATION NRC uestion In your submittal, you state that the maximum temperature increase of the charcoal in the Fuel Handling Building Emergency Exhaust System was calculated to be 26'F. Please explain the method and assumptions used to determine the temperature increase of the charcoal. Also, please state whether the method and assumptions used conform with the Chapter 15 Fuel Handling Accidents.
Harris Nuclear Plant Res onse The temperature increase in the charcoal of the Fuel Handling Building Emergency Exhaust System (FHBEES) was calculated based on iodine decay following a Fuel Handling Accident. The purpose of the calculation was to verify that the charcoal in the FHBEES willnot exceed either the iodine liberation (desorption) temperature or the auto-ignition temperature.
The calculation for the temperature increase in the charcoal for FHBEES is included in Enclosure 2. The method and assumptions for the calculation are also included in Enclosure 2.
In addition, Harris Nuclear Plant (HNP) has updated the calculation that provided input to the March 12, 1998 letter submitted to the NRC. HNP had originally calculated a 15.7 BTU/hr initial heat generation rate due to iodine decay. This heat generation rate resulted in a temperature increase in the charcoal of 26"F. HNP has re-calculated this heat generation rate during the preparation of a separate license amendment which will clarify the required spent fuel pool water level in HNP Technical Specifications. This submittal is currently under development and will be submitted separately. The revised calculation includes additional conservatisms that were not in the original calculation submitted on March 12, 1998. The new calculation reflects a different initial heat generation rate of approximately 16 BTU/hr and a FHBEES charcoal temperature increase of approximately 27"F. Assuming an initial charcoal temperature of 150"F coupled with a 27'F increase would result in a FHBEES charcoal temperature of approximately 177'F. The calculated FHBEES cllal'coill telnperature remains less than 200'F, which is significantly below the 300'F desorption temperature and the 356'F auto-ignition temperature.
The method and assumptions used for the revised temperature calculation are more conservative than the current FSAR Chapter 15 Fuel Handling Accident Analysis. The method and assumptions used conform with a draft Final Safety Analysis Report (FSAR) Chapter 15 Fuel Handling Accident Analysis
. The draft Fuel Handling Accident Analysis was prepared in support of a pending Technical Specification change associated with spent fuel pool water level changes.
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