ML20234D577

Application for Amend to License DPR-72,consisting of Tech Spec Change Request 159,revising Surveillance & Operabililty Requirements for post-accident Monitoring Instrumentation, Per Util Commitments to Reg Guide 1.97.Fee Paid

ML20234D577
Person / Time
Site:	Crystal River
Issue date:	12/31/1987
From:	Wilgus W FLORIDA POWER CORP.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20234D581	List: ML20234D577 ML20234D602
References
RTR-REGGD-01.097, RTR-REGGD-1.097 3FL287-27, NUDOCS 8801070095
Download: ML20234D577 (21)

Text

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Florida P. o. . w. . .e. . .r Walter S.Wilgus Vice President Nuclear Operations December 31, 1987 3F1287-27 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Technical Specification Change Request No. 159 Post-Accident Monitoring Instrumentation

Dear Sir:

Florida Power Corporation (FPC) hereby submits Technical Specification Change No. 159 requesting amendment to Appendix A of Operating License No. DPR-72. As part of this request, the proposed replacement pages for Appendix A and the bases are enclosed.

This submittal revises surveillance and operability requirements for post-accident monitoring instrumentation installed to satisfy FPC's commitments to Regulatory Guide 1.97, Revision 3. In determining which post-accident monitoring instruments should be included in Technical Specifications (T.S.), the Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors was utilized. The application of these criteria is consistent with the Babcock and Wilcox Owners Group Technical Specification Committee position.

This change request supercedes the previous technical specification post-accident monitoring update as submitted in Change Request No.

82.

8801070095 871231 I PDR ADOCK 05000302 p PDR

[0 tI 3201 Thirty fourth Street South W eVV P.O. Box 14042,St. Petersburg, Florida 33733 813 866 5202 gfD,OD

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December 31, 1987 3F1287-27 An amendment application fee, check number 19282 of one hundred fifty dollars ($150), as required by 10 CFR 170, has been included w'.th this change request.

0[ncerely, q .

1 U W.S. W' us Vice P esident Nuclear Operations JBC/dhd Enclosure xc: Dr. J. Nelson Grace Regional Administrator, Region II Mr. T.F. Stetka Senior Resident Inspector

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STATE OF FLORIDA COUNTY OF CITRUS W.S. Wilgus states that he is the Vice President, Nuclear Operations for Florida Powcr Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information, and belief.

W.S. Wilg O- Vice President Nuclear Operations Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 31st day of December 1987.

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f f N tary Public i

l Notary Public, State of Florida at Large, My Commission Expires: June 21, 1991 .J

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER )

) DOCKET NO. 50-302 FLORIDA POWER CORPORATION )

CERTIFICATE OF SERVICE W.S. Wilgus deposes and says that the following has been served on the Designated State Representative and Chief Executive of Citrus County, Florida, by deposit in the United States mail., addressed as follows:

Chairman, Administrator Board of County Commissioners Radiological Health Services of Citrus County Department of Health and Citrus County Courthouse Rehabilitative Services Inverness, FL 32650- 1323 Winewood Blvd.

Tallahassee, FL 32301 A copy of Technical Specification Change Request No. 159,. Revision 0 requesting Amendment to Appendix A of Operating Licensing No. DPR-72.

FLORIDA POWER CORPORATION 1

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W.S. Wil Vice President Nuclear rations SWORN TO AND SUBSCRIBED BEFORE ME THIS 31ST DAY OF DECEMBER 1987.

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Y' Notary Public, State of Florida at Large My Commission Expires: June 21, 1991 (NOTARY SEAL)

FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET No. 50-302/ LICENSE NO. DPR-72 REQUEST No. 159, REVISION O POST-ACCIDENT MONITORING INSTRUMENTATION LICENSE DOCUMENT INVOLVED: Technical Specifications PORTIONS: 3.3.3.6, Table 3.3-10 and Table 4.3-7 DESCRIPTION OF REQUESTr This submittal revises surveillance and. operability requirements for post-accident monitoring instrumentation installed to satisfy Florida Power Corporation's (FpC) commitments-to Regulatory Guide 1.97 (R.G. 1.97), Revision 3.

Instrument names, ranges and mirimum number channels operable have been revised to be consistent with FPC's response to R.G. 1.97. Some instruments were added and others were relocated to the FSAR.

REASON FOR REQUEST:

This revision is being requested to reflect changes which will result from the modification currently being installed. R.G. 1.97 instruments which meet the criteria for inclusion in Technical Specifications have been added. Instruments which did not meet the criteria for inclusion in Technical Specifications have been relocated to the FSAR as Supplemental Specifications (SS). The criteria utilized are specified in the Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors (52 Fed. Reg. 3788, 2/6/87).

EVALUATION OF REQUEST:

At the start of an accident, it may be difficult for the operator to determine immediately what accident has occurred or is occurring and therefore to determine l the appropriate response. For this reason, reactor trip and certain other safety l actions (e.g., emergency core cooling actuation, containment isolation, .or 4 depressurize. tion) have been designed to be performed automatically during the initial stages of an accident. Instrumentation is also provided to indicate information about plant variables required to enable the ' operation of manually initiated safety systems and other appropriate operator actions involving systems important to safety. The post-accident monitoring instrumentation, comprised of instrumentation displays to assess plant and environs conditions during and following an accident, provides this information.

In order to determine which post-accident monitoring. instruments should be included in Technical Specifications, the Commission policy Statement on Technical Specification Improvements for Nuclear Power Reactors was utilized. This policy statement addresses the scope and purpose of Technical Specifications. In doing so, it established a specific set of objective criteria for determining which 1 regulatory requirements and operating restrictions should be included in Technical Specifications. These criteria are as follows:

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l CRITERION 1: Installed instrumentation that is used to detect and indicate in the Control Room, a significant abnormal degradation of the reactor coolant pressure boundary; CRITERION 2: A process variable that is an initial condition of a design basis accident (DBA) or transient analyses that either assumes the failure of or presents a challenge to the integrity of a fission product barrier; CRITERION 3: A structure, system or component that is part of the primary success path and which functions or actuates to miticate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission barrier; In addition to those structures, systems, and components captured by the above criteria, it is the Commission's policy that Licensees retain in their technical specifications LCO's, Action Statements, and Surveillance Requirements for systems which operating experience and Probabilistic Risk Assessment have generally shown to be important to public health and safety.

The application of these criteria is shown in Attachment 1. The instruments which did meet the criteria have been located in Technical Specifications. For the instruments which did not meet the criteria, FPC proposes to remove them from the Technical Specification and relocate the instruments, their requirements and bases in the FSAR. These requirements will be termed Supplemental Specifications (SSs).

10CFR50.59 will be utilized as the control mechanism for the SSs as they will be placed in the FSAR. This would allow Florida Power Corporation (FPC) to make changes to these specifications if the change does not involve an unreviewed safety question. Plant Review Committee (PRC) and Nuclear General Review Committee (NGRC) review and approval will be required prior to implementation of changes. A report of changes to SSs, made utilizing the provisions of 10CFR50.59 will be furnished annually to Region II with a copy to the Director of Inspection and Enforcement.

Additionally, the FSAR will be updated annually, pursuant to 10CFR50.71 to reflect any changes to these specifications.

Maintenance of the instrumentation in the SS will not be affected by this Technical Specificat. ton change. FPC will continue to perform periodic testing to assure that the instrumentation is maintained operable. Relocating specific requirements for the instruments shown in the attached Table 15.3-1 will have no impact on their operability.

For any future changes to the instruments shown in Table 15.3-1, the provisions of 10CFR50.59 will be utilized. Additionally, a multidisciplinary review by the PRC and the NGRC will be performed. These controls are considered adequate for assuring these instruments are maintained operable.

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The proposed amendment incorporates operability and surveillance requirements for additional post-accident monitoring instruments consistent with FPC's commitment to R.G. 1.97. These additional instruments are: Containment Sump Level (Narrow Range), Core Exit Thermocouple, Emergency Feedwater Tank Level and Containment l High Range Radiation Monitor. These instruments were added as a result of applying l the T.S. criteria discussed previously, j l

This amendment also revises some existing T.S. instrument names and minimum number channels operable consistent with FPC's specific commitments to R.G. 1.97. Ranges were also changed, where necessary, to be consistent with FPC's commitment and the intent of R.G. 1.97. Instruments whose range changed have been designed to meet or exceed the existing design requirements. This instrumentation is capable of surviving the accident environment in which it is located for the length of time its function is required. Instruments have also been designed to continue to function following a seismic event. Therefore, the post-accident instrumentation is designed to withstand the effect of an earthquake. As such, better assurance is provided that these instruments will be available for operator use following an accident.

The NRC has, in their SER dated June 16, 1987, approved FPC's specific commitments for ranges with regard to compliance to R.G. 1.97, revision 3.

Operability and surveillance requirements have been relocated to SSs in the FSAR for the following instruments: Reactor Building Pressure, Reactor Coolant Total Flow, Startup Feedwater Flow, PORV Position Indicator (Primary and Backup Detectors), PORV Block Valve Position Indicator, Safety Valve Position Indicator (Primary and Backup Detectors), and Emergency Feedwater Flow. These instruments have been relocated as a result of T.S. criteria application discussed above, Additionally, references to instrument recorders have been removed from Technical Specifications. This information is considered to be part of the design basis and therefore, it would be more appropriate to describe them and relocate them to the FSAR. The FSAR will be revised to reflect recorder information specifically provided for in FPC's commitment to R.G. 1.97. 10CFR50.59 will be utilized as the control process for changes to recorder design.

These proposed changes will not affect the design basis of the system or components, as instrumentation will still be available to assess plant and environmental conditions during and following an accident.

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SEOLLY EVALUATION OF REQUEST:

Florida Power Corporation (FpC) proposes the change to the surveillance and oper-ability requirements for post-accident monitoring instrumentation does not involve a significant hazards consideration,

1. Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability of occurrence or conse -

quences of an accident previously evaluated. The proposed amendment ensures operability of instrumentation installed to monitor selected plant variables and systems during and following the postulated' accidents previously analyzed and has no affect on the probability of occurrence or consequences of these previously evaluated accidents.

2. Operation of the facility in accordance with the proposed amendment would not create the possibility of a new or different kind of accident fros' any acci-dent previously evaluated. The proposed amendment has no affect on the possi-bility of creating a new or different kind of accident from any accident pre-viously evaluated. The proposed amendment ensures operability of instruments-tion installed to monitor selected plant variables and systems during and following the postulated accidents previously analyzed and is unrelated to the possibility of creating a new or different kind of accident.

3. Operation of the facility in accordance with the proposed amendment would not involve a significant reduction in a margin of safety. The proposed amendment constitutes an additional control not presently included in the Technical Specifications. Additionally, all instruments are now qualified in accordance with Regulatory Guide 1.97. Therefore, the overall margin of safety for the plant is increased.

FPC proposes that relocation of operability and surveillance requirements for the nine (9) instruments, which do not meet the criteria for Technical Specification inclusion, does not involve a significant hazards consideration. .The requirements and surveillance for those instruments will continue to be maintained and per-formed, Based on the above, Fpc finds that this change will not:

1. Involve a significant increase in the probability or consequence of an acci-dent previously evaluated because the instrument operability and ' surveillance requirements will not be affected. The proposed change relocates requirements and surveillance for post-accident monitoring instruments which did not meet the criteria for inclusion 'in Technical Specifications. These instruments will be relocated from the Technical Specifications to the FSAR. These operability requirements and surveillance will continue to be maintained pursuant to 10 CFR 50.59.

2. Create the possibility of a new or different kind of accident from any acci-dent previously evaluated because adequate controls for the relocated require-ments exist under the provisions of 10 CFR 50.59,

3. Involve a significant reduction in the margin of safety because the instrument requirements and surveillance are the same or more restrictive than the existing Technical Specification. For any future changes to the post-accident requirements, the provisions of 10 CFR 50.59 and 50.71 will be upheld.

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