L-2011-412, Response to Request for Supplemental Documentation

Response to Request for Supplemental Documentation

ML11298A179
Person / Time
Site:	Turkey Point
Issue date:	10/14/2011
From:	Kiley M Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2011-412
Download: ML11298A179 (7)

Text

OCT 1 4 2011 r-PIL. L-20111-412 POWERING TODAY.

EMPOWERING TOMORROW."

U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001 Re: Turkey Point Nuclear Generating Station Docket Nos. 50-250 and 50-251 License Amendment Request No. 214 Response to Request for Supplemental Documentation

References:

1) FPL letter L-2011-046 to the USNRC, dated August 17, 2011, License Amendment Request No. 214, Accident Monitoring Instrumentation Technical Specification Changes Regarding High Range-Noble Gas Effluent Monitors-Main Steam Lines Accident Monitoring Instrumentation

2) Email from J. Paige (NRC) to R. J. Tomonto (FPL), "ACCEPTANCE REVIEW:

Turkey Point Accident Monitoring Instrumentation TS Changes LAR (ME6891 and ME6892) dated September 13, 2011

3) FPL letter L-84-20 to the USNRC, dated January 26, 1984, "Turkey Point Units 3 and 4, Docket Nos. 50-250 and 50-25 1, Supplement I to NUREG 0737- Regulatory Guide 1.97 (Rev. 3)

On August 17, 2011, Florida Power and Light Company (FPL) submitted in letter L-2011-046, the License Amendment Request No. 214 (Reference 1) to relocate the Turkey Point Accident Monitoring Technical Specification and Surveillance Requirements for the High Range Noble Gas Effluent Monitor for the Main Steam Lines (RAD-6426) from the Technical Specifications (TS) to the Updated Final Safety Analysis Report (UFSAR) and related procedures. Reference 1, identifies RAD-6426 as a Type E variable per Regulatory Guide 1.97, Revision 3.

By electronic mail from the Nuclear Regulatory Commission (NRC) Project Manager (PM) dated September 13, 2011, the NRC requested Florida Power & Light Company (FPL) to provide supplemental documentation that justifies the classification of RAD-6426 as a Type E variable per Regulatory Guide 1.97, Revision 3.

an FPL Group company

L-201-412 Page 2 contains the NRC request and the FPL response. Enclosure 1 provides the documentation requested.

The supplemental information provided herein does not change the conclusions stated in Reference 1, and does not create any new commitments.

Should there be any questions, please contact Mr. Robert J. Tomonto, Licensing Manager at 305 246-7327.

Very truly yours, Michael Kiley Vice President Turkey Point Nuclear Plant SM Attachment Enclosure cc: Regional Administrator, USNRC Region II USNRC Senior Resident Inspector - Turkey Point Plant

L-2011-412 Attachment 1 Page 1 of 2 NRC Request (Reference 2):

In a letter dated January 26, 1984, the licensee provided an evaluation of the Turkey Point's existing accident monitoring instrumentation and control systems against the provisions of Regulatory Guide 1.97, Revision 3. [

Reference:

Letter from J.W. Williams (Florida Power and Light Company) to Darrell G. Eisenhut, "Turkey Point Units 3 and 4, Docket Nos. 50-250 and 50-251, Supplement 1 to NUREG 0737 - Regulatory Guide 1.97 (Rev. 3), L-84-20, January 26, 1984.] In the parameter listing summary sheets provided with the letter, the High Range Noble Gas Effluent Monitors for the Main Steam Lines (i.e., RAD-6426) was identified as a Type C, Category 2 variable. According to RG 1.97, Rev.3, Type C variables are "those variables that provide information to indicate the potential for being breached or the actual breach of the barriers to fission product release, i.e., fuel cladding, primary coolant pressure boundary, and containment". In the August 17, 2011, license amendment request, the licensee indicates that the RAD-6426 instrument that performs the function of being a High Range Noble Gas Effluent Monitor for the Main Steam Lines is a Type E, Category 2 variable that does not perform a function that would meet any of the 10 CFR 50.36(c)(2)(ii) criterion for being a limiting condition for operation.

Provide the documentation that changed the High Range Noble Gas Effluent Monitor on the Main Steam Lines function from a Type C to a Type E variable. If the variable is, in fact, a Type C variable, it would appear that an LCO may be appropriate for this instrument per 10 CFR 50.36(c)(2)(ii)(A).

FPL Response:

As stated in the NRC request, FPL submitted to NRC by FPL letter L-84-20 (Reference 3),

an evaluation of the Turkey Point's existing (at that time) accident monitoring instrumentation and control systems against the provisions of Regulatory Guide 1.97, Revision 3.

As indicated in the NRC request (Reference 2), in the Parameter Listing Summary Sheets, which were provided with the FPL letter L-84-20, the High Range Noble Gas Effluent Monitors for the Main Steam Lines (i.e., RAD-6426) was identified as a Type C, Category 2 variable.

FPL letter L-84-20, listed RAD-6426 in the Parameter Listing Summary Sheets as both a Type C and a Type E variable. Specifically, RAD-6426 was listed in the Parameter Listing Summary Sheets as Type C, Category 2 variable for Item C 14 [Containment Effluent Radioactivity-Noble Gas From Identified Release Points], and as Type E, Category 2 for Item E6 [Vent From Steam Generator Safety Relief Valve].

Regulatory Guide 1.97 Type E variables are those variables to be monitored as required for use in determining the magnitude of release of radioactive materials and continually assessing such releases.

L-2011-412 Attachment 1 Page 2 of 2 Section 7.5.4 of the Turkey Point Updated Final Safety Analysis Report (UFSAR) incorporated the plant commitments to meet Regulatory Guide 1.97 Revision 3 requirements.

The UFSAR Tables 7.5-1 and 7.5-2, Parameter Listing Summary Sheets listed the instrumentation required for post-accident monitoring for Turkey Point Units 3 and Unit 4 respectively.

The Regulatory Guide 1.97, Revision 3 licensing commitments identified in the Turkey Point submittal to the NRC (Reference 3) were subsequently revised (under 10 CFR 50.59) in 1991 to more accurately reflect the as-built plant conditions. The engineering package, Plant Change Modification (PC/M) No.90-391, Revision 1, FSAR Revision of Regulatory Guide 1.97 Commitments, provided the revision to the Parameter Listing Summary Sheets (UFSAR Tables 7.5-1 and 7.5-2) to incorporate the re-established design and licensing requirements for certain SPING monitors, which included revisions for the Main Steam Line monitor, RAD-6426.

The design and licensing requirements for monitor RAD-6426 were revised to delete this monitor from the list of monitors identified in the Parameter Listing Summary Sheets for Item C14 [Containment Effluent Radioactivity-Noble Gas From Identified Release Points].

PC/M 90-391 justifies the deletion of monitor RAD-6426 from Item C14, since the range of RAD-6426 did not meet the Regulatory Guide 1.97 range requirements (of 1E-6 to 1E-2 micro Ci/CC) for performing the function of a Type C, Category 2 variable. The relevant pages of PC/M 90-391 that justify the deletion of monitor RAD-6426 from C14, are found in . The UFSAR Tables 7.5-1 and 7.5-2 were subsequently updated to reflect the deletion of RAD-6426 from Item C14 and conforming changes to reflect the monitor's corrected range in Item E6 [Vent From Steam Generator Safety Relief Valve].

As mentioned above, RAD-6426 is listed in these UFSAR Tables (Parameter Listing Summary Sheets) as Regulatory Guide 1.97, Revision 3, Type E, Category 2 variable.

Accordingly, FPL's License Amendment Request 214, submitted by FPL letter L-2011-046, dated August 17, 2011 (Reference 1) identifies RAD-6426 as Regulatory Guide 1.97, Revision 3, Type E, Category 2 variable, and not as a Type C, Category 2 variable.

References:

1) FPL letter L-2011-046 to the USNRC, dated August 17, 2011, License Amendment Request No. 214, Accident Monitoring Instrumentation Technical Specification Changes Regarding High Range-Noble Gas Effluent Monitors-Main Steam Lines Accident Monitoring Instrumentation

2) Email from J. Paige (NRC) to R. J. Tomonto (FPL), "ACCEPTANCE REVIEW: Turkey Point Accident Monitoring Instrumentation TS Changes LAR (ME6891 and ME6892) dated September 13, 2011

3) FPL letter L-84-20 to the USNRC, dated January 26, 1984, "Turkey Point Units 3 and 4, Docket Nos. 50-250 and 50-25 1, Supplement I to NUREG 0737 - Regulatory Guide 1.97 (Rev. 3)

L-2011-412 Enclosure 1 Supplemental Documentation Relevant Pages From PC/M 90-391, Revision 1 FSAR Revision of Regulatory Guide 1.97 Commitments

FLORIDAPOWER AND LIGHT COMPANY PC/MHNo.: 90-391 TURKEY POINT UNIT 3 Attah.hment: 2 Revision: 0 R.G. 1.97 JUSTIFICATION REPORT Page: 366 of 616

SUMMARY

SHEET ITEM NO.: C14 TAG NO.: RAD-6426 COLUMN REQUIRING CHANGE REASNOFOR CHANGE RAD-6426 for main steam line radiat"ion monitoring hits been deleted. The existing range of the present radiation monitoring system is IEO to 1E5 micro Ci/CC as~confirmed by EPH in a discussion with the manufacturer (Eberline). This does not meet the RG 1.97 range of IE-6 to IE-2 micro Ci/CC. Detection of a steam generator tube rupture within the lower range of radiation identified by the Rogulatory Guide is credited using the detection system associated with the condenser air i)jector exhaust (i.e., RAD 6.417). The detection. associated with RAD 6417 has a range of 1E-7 to IES micro Ci/CC which envelops the IG 1.97 required range.. RAD 6417 is presently identified in the Paraeter 4iSt4ng Summary Shet-s under Item C14.

FLORIDA POWER AND LIGHT COMPANY PC/M No.: 90-391 TURKEY POINT UNIT 4

Attachment:

3 Revision: 0 R.G. 1.97 JUSTIFICATION REPORT Page: 366 of 6i6

SUMMARY

SHEET ITEM NO.: C14 TAG NO.: RAD-6426 COLUMN REQUIRING CHANGE REASON :FOR CHANGE RAD-6426 for mnain steam line radiation monitoring has been deleted. The existing range of the present radiation monitoring system is 1EO to 1E5 micro fi/CC as ;confirmed by EPM in a discussion with the manufacturer (Eberline). This does nut meet the RG 1.97 range of IE-6 to IE-2 micro.:Ci/CC. Detection uf a steam generator tube rupture within thelower range of radiation identified by the Regulatory Guide is credited usirg the detection system associated with the condenser air ejector.

exhaust (i.e., RAD 6417). The detection:as~sociated with RVD 6417 has a range of IE-7 to 1E5 micro Ci/CC which envelops the RG 1.97 required range. RAO 6417 is presently identified in the Parameter Listing Summary Sheets under Item C14.