HNP-97-009, Application for Amend to License NPF-63,requesting to Add New Entry 3.0.5 to 3/4.0 to Provide Specific Guidance for Returning Equipment to Service in Order to Demonstrate Operability
| ML18012A494 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 01/29/1997 |
| From: | Robinson W CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18012A495 | List: |
| References | |
| HNP-97-009, HNP-97-9, NUDOCS 9702100190 | |
| Download: ML18012A494 (13) | |
Text
CATEGORY 1 REGULAT INFORMATION DISTRIBUTIONSTEM (RIDS)
ACCESSION,ABR:9702100190 DOC.DATE: 97/01/29 NOTARIZED: YES FACIL:50-460 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME q
AUTHOR AFFILIATION ROBINSON,W.RE Carolina Power
& Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Application for amend to license NPF-63,requesting to add new entry 3.0.5 to 3/4.0 to provide specific guidance for returning equipment to service in order to demonstrate operability.
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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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TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
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I Carolina Power & Light Company PO Box 165 New Hill NC 27562 William R. Robinson Vice President Harris Nuclear Plant SERIAL: HNP-97-009 10 CFR 50.90 JAN 29 1997 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 EQUIPMENT RETURNED TO SERVICE IN ORDER TO DEMONSTRATE OPERABILITY
Dear Sir or Madam:
In accordance with the Code ofFederal Regulations, Title 10, Part 50.90, Carolina Power Ec Light Company (CP&L) hereby requests a revision to the Technical Specifications (TS) for the Harris Nuclear Plant (HNP). The requested change willadd a new entry 3.0.5 to 3/4.0 APPLICABILITY.The new 3.0.5 provides specific guidance for returning equipment to service under administrative control for the sole purpose ofperforming testing to demonstrate OPERABILITY.
Enclosure 1 provides a detailed 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.
<<j<< provides an environmental evaluation demonstrating that the proposed amendment
<<0 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 is required for approval ofthis amendment request. provides page change instructions for incorporating the proposed revisions.
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PDR State Road 1134 New Hill NC Tel 919 362-2502 Fax 919 362-2095
Document Control Desk HNP-97-009 / Page 2 provides the prop'osed Technical Specification pages.
In accordance with 10 CFR 50.91(b), CP&L is providing the State ofNorth Carolina with a copy ofthe proposed license amendment.
CP&L requests approval ofthe proposed amendment by March 15, 1997 to support the next HNP refueling outage, currently scheduled to begin in April 1997. In order to allow time for procedure revision and orderly incorporation into copies ofthe Technical Specifications, CP&L requests that the proposed amendment, once approved by the NRC, be implemented within 30 days of issuance ofthe amendment.
Please refer any questions regarding this submittal to Ms. D. B. Alexander at (919) 362-3190.
Sincerely, CSB/twk
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 &Light Company.
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Document Control Desk HNP-97-009 / Page 3 Mr. J. B. Brady, NRC Senior Resident Inspector Mr. Dayne H. Brown, N.C. DEHNR Mr. L. A. Reyes, NRC Regional Administrator Mr. N. B. Le, NRC Project Manager
Document Control Desk HNP-97-009 / Page 4 bc:
Ms. D. B. Alexander Ms. P. B. Brannan Mr. Charles S. Bohanan Mr. H. Chernoff (RNP)
Mr. G. W. Davis Mr. J. W. Donahue Ms. S. F. Flynn Mr. H. W. Habermeyer, Jr.
Mr. W. J. Hindman Ms. W. C. Langston (PEARAS File)
Mr. R. D. Martin Mr. W. S. Orser Mr. G. A. Rolfson Mr. R. S. Stancil Mr. D. L. Tibbitts Mr. M. A. Turkal (BNP)
Mr. T. D. Walt Nuclear Records File: HI/A-2D File: H-X-0511
ENCLOSURE TO SERIAL: HNP-97-009 ENCLOSURE 1
SHEARON HARRIS NUCLEARPOWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT
'QUIPMENT RETURNED TO SERVICE IN ORDER TO DEMONSTRATE OPERABILITY
Background
Action statements within the Technical Specifications provide guidance for compensatory actions and other restrictions to be taken when the requirements ofan LCO cannot be met. When equipment has been out ofservice it is necessary to demonstrate that it can perform its required function before it can be returned to an OPERABLE condition. Most testing can be done prior to returning the equipment to service, but in some cases it is necessary to return equipment to a functional status in order to demonstrate an activity required for OPERABILITY.
A particular example for HNP is Specification 3.3.3.1, RADIATIONMONITORINGFOR PLANT OPERATIONS. Items l.b and l.c ofTable 3.3-6 deal with containment airborne radioactivity monitors during normal and pre-entry purge operation.
Each ofthese items has an ACTIONstatement which requires the associated purge valves to be maintained closed in the event the radiation monitor is inoperable.
In order to return the radiation monitor to OPERABLE status it is necessary to demonstrate that the associated purge valves willbe automatically closed ifa trip setpoint is reached on the monitor. However the only way this test can be performed is by opening the associated valves to observe their closing as a result ofthe radiation monitor signal, and the valves cannot be opened because ofthe ACTIONstatement in force due to the INOPERABLE radiation monitor. This creates a situation in which it can become logically impossible to place the radiation monitor into an OPERABLE condition. The requested change clarifies that it is permissible to open a purge valve in order to observe its closure by the functional radiation monitor to declare the system OPERABLE. It should be noted that this change would not permit a pre-entry purge valve to be opened in Modes 1, 2, 3, or 4 because that system is not permitted to be OPERABLE in those MODES and therefore the testing would not be valid.
Carolina Power &Light Company therefore proposes a new general applicability specification 3.0.5 and associated bases which provide specific guidance on the ability to operate a component under administrative control ifnecessary to complete a test to demonstrate OPERABILITY.
Page El-1
ENCLOSURE TO SERIAL: HNP-97-009 This change has no impact on plant equipment or its operation.
This administrative change clarifies that testing necessary to declare equipment OPERABLE may be completed under administrative control. The exception may be used only for a specific purpose and only on equipment that the licensee believes has been repaired or is otherwise capable ofcarrying out its Technical Specification function. The need for a specific statement ofthis exception has been recognized by both the industry and the NRC staff and an essentially identical statement is incorporated into the current Standard Technical Specifications for Westinghouse Plants, NUREG-1431, Rev.
1 as LCO 3.0.5. The proposed HNP change has minor editorial changes to reflect the differences in wording of3.0.1 and 3.0.2 ofthe current HNP Technical Specifications and LCO 3.0.1 and 3.0.2 ofNUREG-1431.
The requested change revises the Technical Specifications to provide specific guidance that components may be operated under administrative control in order to demonstrate OPERABILITY. The change is functionally identical to the guidance provided on this issue in the current Standard Technical Specifications for Westinghouse Plants, NUREG-1431, Rev. 1.
Page El-2
ENCLOSURE TO SERIAL: HNP-97-009 ENCLOSURE2 SHEARON HARRIS NUCLEARPOWER. PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT EQUIPMENT RETURNED TO SERVICE IN ORDER TO DEMONSTRATE OPERABILITY V
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 facility in accordance with the proposed amendment would not: (I) involve a significant increase in the probability or consequences ofan 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:
Carolina Power &Light Company proposes to add a new general applicability specification 3.0.5 and associated bases which provide specific guidance on the ability to operate a component under administrative control ifnecessary to complete testing to demonstrate OPERABILITY.
This change clarification does not involve a significant hazards consideration for the following reasons:
The proposed amendment does not involve a significant increase in the probability or consequences ofan accident previously evaluated.
The proposed change does not affect the operation or design ofthe plant in any way.
Operation ofplant equipment under this change willnot differ in any way from its normal operational mode. The normal operation ofplant equipment is not a precursor to any accident.
The purpose oftests performed using this change are to demonstrate that Page E2-1
ENCLOSURE TO SERIAL: HNP-97-009 required automatic actions are carried out. Equipment willbe operated under administrative control for only a short period oftime.
Personnel willbe immediately available to take appropriate manual action ifit should be required.
Therefore operation ofequipment under this change is not expected to increase the probability or consequences ofan accident previously evaluated.
The proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed testing allowance does not involve any physical alterations or additions to plant equipment or alter the manner in which any safety-related system performs its function. Therefore, the proposed changes do not create the possibility ofa new or different kind ofaccident from any accident previously evaluated.
n 3.
The proposed amendment does not involve a significant reduction in the margin ofsafety.
Equipment willbe operated under administrative control for only a short period oftime.
Personnel willbe immediately available to take appropriate manual action ifit should be required.
The purpose ofthe testing is to restore required equipment to an OPERABLE state which increases the automatic protection available and reduces the reliance on the compensatory measures provided by ACTIONstatements.
Therefore, the proposed changes do not involve a significant reduction in a margin ofsafety.
Page E2-2
ENCLOSURE TO SERIAL: HNP-97-009 ENCLOSURE3 SHEARON HARRIS NUCLEARPOWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT EQUIPMENT RETURNED TO SERVICE IN ORDER TO DEMONSTRATE OPERABILITY V
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 if operation ofthe 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 ofany 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:
Carolina Power 4 Light Company proposes to add a new general applicability specification 3.0.5 and associated bases which provide specific guidance on the ability to operate a component under administrative control ifnecessary to complete testing to demonstrate OPERABILITY.
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.
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.
Page E3-I
ENCLOSURE TO SERIAL: HNP-97-009 The proposed change does not involve any new equipment or require existing systems to perform a different type offunction 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 ofany effluents that may be released offsite.
3.
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 which would require additional personnel entry into radiation controlled areas.
Therefore, the amendment has no affect on either individual or cumulative occupational radiation exposure.
Page E3-2
ENCLOSURE 4 SHEARON HARRIS NUCLEARPOWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT EQUIPMENT RETURNED TO SERVICE IN ORDER TO DEMONSTRATE OPERABILITY ve 3/4 0-1 B 3/4 0-2 B 3/4 0-2a 3/4 0-1 B 3/4 0-2 B 3/4 0-2a and B 3/4 0-2b