ML20147D233

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Forwards Revised Steam Generator Tube Rupture (SGTR) Analysis Based on Westinghouse Owners Group Program. Discussion of Five Requirements Stated in SER & Addl SGTR Documentation Encl
ML20147D233
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 02/29/1988
From: Gucwa L
GEORGIA POWER CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML19341E001 List:
References
RTR-NUREG-1137 SL-4149, NUDOCS 8803030268
Download: ML20147D233 (11)
v • d • e


Text

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. Georgia Fbwer Company 333 Predmont Avenue A:tanta, Georg4 30308 Telephone 404 5264526 Mailing Address:

Fbst Off ce Box 4545 Atlanta, Georgia 30302 Georgia Power L T. Gucwa # ## "# ##

Manager Nuclear Safety.

and Licensing - $(_4]4g 0778m X7GJ17-V600 X7GJ17-V720 February 29, 1988 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D.C. 20555 PLANT V0GTLE - UNITS 1, 2 NRC DOCKETS 50-424, 50-425 OPERATING LICENSE NPF-68, CONSTRUCTION PERMIT CPPR-109 UNIT 1 LICENSE CONDITION 2.C.(5), UNIT 2 SER CONFIRMATORY ITEMS 48, 49 STEAM GENERATOR TUBE RUPTURE ANALYSIS Gentlemen:

Georgia Power Company hereby submits for NRC review a revised steam generator tube rupture (SGTR) analysis in accordance with License Condition 2.C.(5) for Plant Vogtle Unit 1 and Confirmatory Items 48 and 49 of the Safety Evaluation Report (SER), NUREG-1137, for Plant Vogtle Unit 2. The SGTR analysis is based on the Westinghouse Owners Group program, whose methodology was approved by the NRC in a letter from C.

Rossi (NRC) to A. Ladieu of the Westinghouse Owners Group dated March 30, 1987.

Enclosure 1 provides a discussion of each of the five requirements as stated in the NRC Safety Evaluation Report (SER). Each of the five items is restated alora with the Plant Vogtle specifle. response.

The documentation of this submittal is provided in the following enclosures:

Enclosure 2: 5 copies of "SGTR Event Operator Action Times Using Vogtle Simulator," NCA-7002, February 1987 Enclosure 3: 5 copies of "LOFTTR2 Analysis for a Steam Generator Tube Rupture Event for the Vogtle Electric Generating Plant Units 1 and 2," HCAP-11731 (Proprietary), January 1988 Enclosure 4: 5 copies of "LOFTTR2 Analysis for a Steam Generator Tube Rupture Event for the Vogtle Electric Generating Plant Units 1 and 2," HCAP-11732 (Non-Proprietary), January 1988 Enclosure 5: Comprehensive Equipment List for Procedure 19030-1 Rev. 4, October 26, 1987.

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l GeorgiaPower A U. S. Nuclear Regulatory Commission February 29, 1988 Page Two Enclosure 3 contains information proprietary to Hestinghouse Electric Corporation and is supported by an Application for Withholding (Attachment I to Enclosure 3) signed by Hestinghouse, the owner of the information. Attachment 1 includes the affidavit, AH-76-31, which sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.790 of the Commission's regulations.

Accordingly, it is respectfully requestcd that the information proprietary to Hestinghouse be withheld from public disclosure in accordance with 10 CFR Section 2.790 of the Commission's regulations.

Correspondence with respect to the proprietary aspects of the Application fe Withholding or the supporting Hestinghouse affidavit should reference CAH-88-Oli and should be addressed to R. A. Hiesemann, Manager, Regelatory and Legislative Affairs: Westinghouse Electric Corporation, P.O. Box 355, Pittsburgh, Pennsylvania 15230.

Additi>nally, the documentation of this revised SGTR analysis will be included in a FSAR amendment to Subsection 15.6.3.

Should you require any additional information, please contact this office.

Sincerely, fg m.

L. T. Gucwa EMB/im

Enclosures:

1. SGTR SER Response
2. SGTR Event Operator Action Times Using Vogtle Simulator
3. LOFTTR2 Analysis for a Steam Generator Tube Rupture Event for the Vogtle Electric Generating Plant Units 1 and 2
4. LOFTTR2 Analysis for a Steam Generator Tube Rupture Event for the Vogtle Electric Generating Plant Units 1 and 2
5. Comprehensive Equipment List for Procedura 19030-1 Rev. 4 c: (see next page) 0778m rm79

r- ,

GeorgiaPower A U. S. Nuclear Regulatory Commission February 29, 1988 Page Three c: Georaia Power Comoany-Mr. P. D. Rice Mr. G. Bockhold, Jr.

GO-NORMS U. S. Nuclear Reaulatory Commission Dr. J. N. Grace, Regional Administrator Mr. J. B. Hopkins, Licensing Project Manager, NRR (2 copies)

Mr. J. F. Rogge, Senior Resident Inspector-0perations, Vogtle T

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r GeorgiaPower d ENCLOSURE 1 PLANT V0GTLE - UNITS 1, 2 NRC DOCKETS 50-424, 50-425 OPERATING LICENSE NPF-68, CONSTRUCTION PERMIT CPPR-109 LICENSE CONDITION 2.C.(5) (UNIT 1), CONFIRMATORY ITEMS 48 AND 49 (UNIT 2)

SGTR SER RESPONSE

1. "Each utility in the SGTR subgroup must confirm that they have in place simulators and training programs which provide the required assurance that the necessary actions and times can be taken consistent with those assumed for the HCAP-10698 design basis analysis. Demonstration runs should be performed to show that the accident can be mitigated within a period of time compatible with overfill prevention, using design basis assumptions regarding available equipment, and to demonstrate that the operator action times assumed in the analysis are realistic."

Discussion:

A Plant Vogtle referenced simulator is employed for on-site SGTR training. Licensed operators are trained in the proper use of Emergency Operating Procedures (E0Ps) relative to the SGTR event per procedure 19030-1 (ERG E-3). During the months of October and November 1986, various groups of students in operator training were tested on the simulator using eight different SGTR scenarios. This testing was performed specifically to obtain a data base of operator action times to be used in the SGTR analysis contained herein. As documented in Enclosure 2 "SGTR Event Operator Action Times Using Vogtle Simulator," NCA-7002, February 1987, the operator times are in good agreement with those of HCAP-1069a. The times used for the plant specific analysis are those noted in Table 8 of Enclosure 2 under the "MAXIMUM" column. At the time this report was prepared Plant Vogtle personnel were in operator training and had not yet then their NRC license examinations. This provides additional assurance that conservative operator action cimes were used for the SGTR analysis.

2. "A site specific SGTR radiation offsite consequence analysis which assumes the most severe failure identified in HCAP-10698, Supplement 1. The analysis should be performed using the methodology in SRP Section 15.6.3 as supplemented by the guidance in a letter from H. Berkow, NRC, to Alan Ladieu Chairman, SGTR Subgroup

' Acceptance for Referencing of Licensing Topical Report HCAP-10698 Supplement 1.'"

0778m El-1 02/29/88 SL-4149 7*775 _

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GeorgiaPower A ENCLOSURE 1 (Continued)

SGTR SER RESPONSE Discussion:

A site specific analysis has been performed and is documented in Enclosure 3, HCAP-11731, "LOFTTR2 Analysis for a Steam Generator Tube Rupture Event for the Vogtle Electric Generating Plant Units 1 and 2," January 1988 (Proprietary). This analysis assumes the most severe failure as identified in HCAP-10698 Supplement 1. The results are well within the 10 CFR 100 limits as required by the acceptance criteria in SRP Section 15.6.3.

As this enclosure contains information proprietary to Westinghouse Electric Corporation, it is supported by an Application for Hithholding, (Attachment 1 to Enclosure 3), signed by Hestinghouse, the owner of the information. Attachment 1 includes the affidavit, AH-76-31, which sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.790 of the Commission's regulations.

Accordingly, it is respectfully requested that the information proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR Section 2.790 of the Commission's regulations. Correspondence with respect to the proprietary aspects of the Application for Hithholding or the supporting Hestinghouse affidavit should reference CAH-88-Oli and should be addressed to R. A. Hiesemann, Manager, Regulatory and Legislative Affairs, Westinghouse Electric Corporation, P. O. Box 355, Pittsburgh, Pennsylvania 15230.

Enclosure 4 contains HCAP-11732, "LOFTTR2 Analysts for a Steam Generator Tube Rupture Event for the Vogtle Electric Generating Plant Units 1 and 2 January 1988 (Non-Proprietary).

3. "An evaluation of the structural adequacy of the main steam lines and associated supports under water-filled conditions as a result of SGTR overfi l l . "

Discussion:

The Vogtle specific analysis demonstrates that the steam generators do not overfill; however, the Vogtle main steam line structural design is adequate to support water-filled conditions as a result of 0778m El-2 02/29/88 SL-4149 a imm

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-t GeorgiaPower d ENCLOSURE 1 (Continued)

SGTR SER RESPONSE a postulated SGTR overfill. The stress analysis and support design for the Vogtle main steam lines considered a water filled pipe from the steam generator nozzle to the containment penetration. The piping stress analysis used the dead weight load assuming the line filled with water. The analytical results demonstrate that the piping stresses remain with code limits, and that the steam generator nozzle and containment penetration loads remain within vendor allowable values. The spring supports can accommodate the water filled line while remaining within their working range. The thermal loads and stresses are unaffected by having the main steam line filled with water. A seismic stress analysis was not performed with piping full of water. The main steam line outside containment between the containment penetration and the HSIV is supported by rigid type restraints. These supports are designed for water filled line loads. Plant Vogtle has two MSIVs for each steamline; therefore, water filled conditions need not be postulated beyond the HSIVs.

4. "A list of systems, components and instrumentation which are credited for accident mitigation in the plant specific SGTR E0P(s). Specify whether each system and component specified is safety grade. For primary and secondary PORVs and control valves specify the valve motive power and state whether the motive power and valve controls are safety grade. For non-safety grade systems and components state whether safety grade oackups are available which can be expected to function or provide the desired information within a time period compatible with preve*1 tion of SGTR overfill or justi fy that non-safety grade components can be utilized for the design basis event. Provide a list of all radiation monitors that could be used for the identification of the accident and the ruptured steam generator and specify the quality and reliability of this instrumentation if possible. If the E0Ps specify steam generator sampling as a means of ruptured SG identification, provide the expected time period for obtaining the sample results and discuss the effect on the duration of the accident."

Discussioni Enclosure 5 contains a list of all systems, components and instrumentation which are required to carry out each of the steps in the VEGP SGTR E0P, E-3. All systems and components listed under "Principal Equipment" required by the operator for execution of E-3 are safety grade. This includes valve motive power and controls for both the primary and secondary PORVs.

0778m El-3 02/29/88 SL-4149 rwm _ _ _ _ . . _.

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4 GeorgiaPower1 s

ENCLOSURE 1 (Continued)

SGTR SER RESPONSE Plant Vogtle 'provides radiation monitors for each 'of the main steam lines, the condenser air ejector, and the steam generator blowdown line, specifically:

o RE-13119, RE-13120, ~ RE-13121,- and RE-13122 are the main steam line monitors. The purpose of these monitors is to detect steam generator tube leakage and to monitor this potential release path. One detector is used on the each main steam line upstream of the main steam line isolation and atmospheric dump valves.

These monitors are safety grade.

o RE-12839A, RE-128398, and RE-12839C are the condenser particulate, iodine, and radiogas monitors, respectively. ~The purpose of these monitors is to continuously measure activity in the discharge from the air ejector exhaust header of the condenser (which is indicative of a primary to secondary system leak)-and steam packing exhauster monitor effluent path. These monitors are non-safety grade.

o RE-0019 is the steam generator sample liquid process monitor.

The purpose of this monitor is to monitor the liquid phase of the secondary side of the steam generators for activity and to provide backup information to the air ejector radiogas monitor

. RE-12839C. This monitor is non-safety grade.

The -E0Ps do not require sarpling as a means of identifying the

' ~

affected steam generator. Although the steam line monitors are l safety-grade and are listed in the E0Ps as one of the means of ,

identifying the affected SG, no credit is taken for them in the analysis. This is consistent with the methodology in HCAP-10698 and

, is an additional conservatism in the Vogtle analysis. '.

5. "A survey of plant primary and "balance-of-plant" systems design to determine the compatibility with the bounding plant analysis in HCAP-10698. Major design differences should be noted. The worst single failure should be identified if different from the HCAP-10698 analysis and the effect of the differences on the margin of overfill  ;

.should be provided." -

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GeorgiaPower A ENCLOSURE 1 (Ccntinued)

SGTR SER RESPONSE Discussion:

A Vogtle specific analysis was performed (see Enclosure 3,Section II) to determine the margin to overfill for a design basis SGTR for the Vogtle units. This analysis was performed using the LOFTTR2 code and the methodology of HCAP-10698. The analysis model used for item (2) above was used for this analysis, but the initial conditions and assumptions which are conservative with respect to overfill were used. This analysis used the operator action times established for item (1) above.

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0778m El-5 02/29/88 SL-4149 mm

_. . _ .. : . . . _ . . - . . . _ . ~ ~ _ -

Gec:gra Power Company 333 Piedmont Avenue Atlanta, Georgia 30308 Telephone 404 526-6526 Mailing Address:

Post Off.ce Box 4545 Atlanta, Georgia 30302 Georgia Power L. T. Gucws N ##" # 3'"

Manager Nuclear Safety and ucensino SL-4149 0778m X7GJ17-V600 X7GJ17-V720 February 29, 1988 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D.C. 20555 PLANT V0GTLE - UNITS 1, 2 '

NRC DOCKETS 50-424, 50-425 OPERATING LICENSE NPF-68, CONSTRUCTION PERMIT CPPR-109 UNIT 1 LICENSE CONDITION 2.C.(5), UNIT 2 SER CONFIRMATORY ITEMS 48, 49 STEAM GENERATOR TUBE RUPTURE ANALYSIS Gentlemen:

Georgia Power Company hereby submits for NRC review a revised steam generator tube rupture (SGTR) analysis in accordance with License Condi tion 2.C.(5) for Plant Vogtle Unit I and Confirmatory Items 48 and 49 of the Safety Evaluation Report (SER), NUREG-1137, for Plant Vogtle Unit 2. The SGTR analysis is based on the Westinghouse Owners Group program, whose methodology was approved by the NRC in a letter from C.

Rossi (NRC) to A. Ladieu of the Hestinghouse Owners Group dated March 30, 1987.

Enclosure 1 provides a discussion of each of the five requirements as stated in the NRC Safety Evaluation Report (SER). Each of the five items is restated along with the Plant Vogtle specific response.

The documentation of this submittal is provided in the following enclosures:

Enclosure 2: 5 copies of "SGTR Event Operator Action Times Using Vogtle Simulator," NCA-7002, February 1987 Enclosure 3: 5 copies of "LOFTTR2 Analysis for a Steam Generator Tube Ruptuie Event for the Vogtle Electric Generating Plant Units 1 and 2," HCAP-11731 (Proprietary), January 1988 Enclosure 4: 5 copies of "LOFTTR2 Analysis for a Steam Generator Tube Rup t'.# re Event for the Vogtle Electric Generating Plant Unics 1 and 2," HCAP-11732 (Non-Proprietary), January 1988 Enclosure 5: Comprehensive Equipment List for Procedure 19030-1 Rev. 4, October 26, 1987. I AP CH4NGG: 8I LPDR Ns C. New P U P *wY u AC. PD

GeorgiaPower A U. S. Nuclear Regulatory Commission February 29, 1988 Page Two Enclosure 3 contains information proprietary to Westinghouse Electric Corporation and is supported by an Application for Hithholding (Attachment 1 to Enclosure 3) signed by Hestinghouse, the owner of the information. Attachment 1 includes the affidavit, AH-76-31, which sets forth the basis on which the information may be withheld from public .

disclosure by the Commission and addresses with specificity t.he considerations listed in paragraph (b)(4) of Section 2.790 of th'e '

Commission's regulations.

Accordingly, it is respectfully requested that the information propri etary to Westinghouse be withheld from public disclosure in accordance with 10 CFR Section 2.790 of the Commission's regulations.

Correspondence with respect to the proprietary aspects of the Application for Withholding or the supporting Hestinghouse affidavit should reference CAH-88-011 and should be addre. sed to R. A. Hiesemann, Manager, Regulatory and Legislative Affairs, Westinghouse Electric Corporation, P.O. Box 355, Pittsburgh, Pennsylvania 15230.

Additionally, the documentation of this revised SGTR analysis will be included in a FSAR amendment to Subsection 15.6.3.

Should you require any additional information, please contact this office.

Sincerely, fgm L. T. Gucwa EMB/Im

Enclosures:

1. SGTR SER Response
2. SGTR Event Operator Action Times Using Vogtle Simulator
3. LOFTTR2 Analysis for a Steam Generator Tube Rupture Event for the Vogtle Electric Generating Plant Units 1 and 2
4. LOFTTR2 Analysis for a Steam Generator Tube Rupture Event for the Vogtle Electric Generating Plant Units 1 and 2
5. Comprehensive Equipment List for Procedure 19030-1 Rev. 4 c: (see next page) 0778m sema .

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o GeorgiaPower A U. S. Nuclear Regulatory Commission February 29, 1988 Page Three c: Georaia Power Comoany Mr. P. D. Rice Mr. G. Bockhold, Jr.

GO-NORMS U. S. Nuclear Regulatory Commission Dr. J. N. Grace, Regional Administrator -

Mr. J. B. Hopkins, Licensing Project Manager, NRR (2 copies)

Mr. J. F. Rogge, Senior Resident Inspector-0perations, Vogtle 0778m rzm

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