ML20154N215: Difference between revisions

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| number = ML20154N215
| number = ML20154N215
| issue date = 03/12/1986
| issue date = 03/12/1986
| title = Forwards Rev 1 to Main Steam Tunnel Flooding Analysis, as Addl Info in Response to SER Confirmatory Issue 28.Revised Analysis Includes Feedwater Crosstie Isolation Valve Installed Subsequent to 850524 Ltr
| title = Forwards Rev 1 to Main Steam Tunnel Flooding Analysis, as Addl Info in Response to SER Confirmatory Issue 28.Revised Analysis Includes Feedwater Crosstie Isolation Valve Installed Subsequent to
| author name = Mcneill C
| author name = Mcneill C
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
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| contact person =  
| contact person =  
| document report number = NUDOCS 8603170236
| document report number = NUDOCS 8603170236
| title reference date = 05-24-1985
| package number = ML20154N219
| package number = ML20154N219
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
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MAIN STEAM TUNNEL FLOODING ANALYSIS, REVISION 1 SER CONFIRMATORY ISSUE 28 HOPE CREEK GENERATING STATION DOCKET NO. 50-351 Main Steam Tunnel Flooding Analysis, Revision 1, is attached for NRC review as additional information for Public Service Electric and Gas Company's response to SER Confirmatory                                          ,
MAIN STEAM TUNNEL FLOODING ANALYSIS, REVISION 1 SER CONFIRMATORY ISSUE 28 HOPE CREEK GENERATING STATION DOCKET NO. 50-351 Main Steam Tunnel Flooding Analysis, Revision 1, is attached for NRC review as additional information for Public Service Electric and Gas Company's response to SER Confirmatory                                          ,
       ,          Issue 28 (see letter dated May 24, 1985, R.L. Mittl, PSE&G to W. Butler, NRC).
       ,          Issue 28 (see {{letter dated|date=May 24, 1985|text=letter dated May 24, 1985}}, R.L. Mittl, PSE&G to W. Butler, NRC).
This revised analysis includes a feedwater crosstic isolation                                          ,
This revised analysis includes a feedwater crosstic isolation                                          ,
valve which has been installed within the main steam tunnel subsequent to the May 24, 1985 submittal.
valve which has been installed within the main steam tunnel subsequent to the May 24, 1985 submittal.
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i                                SER' ISSUE C-28 (SER SUPP. 3, SECTION 8.3.3.1.4) l                              . MAIN STEAM TUNNEL ~ FLOODING ANALYSIS In Section 8.3.3.1.4 of'the SER, the staff documented the applicant's commitment to perform an analysis to verify that Hope Creek could be shut down safely after a main steam tunnel flooding event.
i                                SER' ISSUE C-28 (SER SUPP. 3, SECTION 8.3.3.1.4) l                              . MAIN STEAM TUNNEL ~ FLOODING ANALYSIS In Section 8.3.3.1.4 of'the SER, the staff documented the applicant's commitment to perform an analysis to verify that Hope Creek could be shut down safely after a main steam tunnel flooding event.
The applicant submitted the main steam t.unnel flooding analysis by letter dated May 24, 1985. This analysis identifies all Class 1E equipment and components in the main steam tunnel, Room 4316, that will be subject to the worst-case submergence that results from a break in a main feedwater line.  (Flood level is elevation 126 ft of this room.)
The applicant submitted the main steam t.unnel flooding analysis by {{letter dated|date=May 24, 1985|text=letter dated May 24, 1985}}. This analysis identifies all Class 1E equipment and components in the main steam tunnel, Room 4316, that will be subject to the worst-case submergence that results from a break in a main feedwater line.  (Flood level is elevation 126 ft of this room.)
Also, this report analyzes whether the equipment or. component is qualified for submergence. If not qualified, a determination is made whether the equipment of component circuitry has
Also, this report analyzes whether the equipment or. component is qualified for submergence. If not qualified, a determination is made whether the equipment of component circuitry has
                                 . primary and backup protective devices located in a hazard-free area. The purpose of this analysis is to demonstrate that the plant can be safely shut down after both the primary and backup protective device open as a result of the failure of unprotected equipment or component together with the worst-case single _ failure.
                                 . primary and backup protective devices located in a hazard-free area. The purpose of this analysis is to demonstrate that the plant can be safely shut down after both the primary and backup protective device open as a result of the failure of unprotected equipment or component together with the worst-case single _ failure.

Latest revision as of 04:28, 10 December 2021

Forwards Rev 1 to Main Steam Tunnel Flooding Analysis, as Addl Info in Response to SER Confirmatory Issue 28.Revised Analysis Includes Feedwater Crosstie Isolation Valve Installed Subsequent to
ML20154N215
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 03/12/1986
From: Corbin McNeil
Public Service Enterprise Group
To: Adensam E
Office of Nuclear Reactor Regulation
Shared Package
ML20154N219 List:
References
NUDOCS 8603170236
Download: ML20154N215 (2)


Text

w- ,

I' Public Service Electric and Gas Company Corbin A. McNeill, Jr. Pubhc Service Electric and Gas Company P O. Box 236, Hancocks Bridge, NJ 08038 609 339-4800 Vics President -

Nucrar March 12, 1986 Director of Nuclear Reactor ~ Regulation United States Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Attention: Ms. Elinor Adensam, Director Project Directorate 3 Division of BWR Licensing

Dear Ms. Adensam:

MAIN STEAM TUNNEL FLOODING ANALYSIS, REVISION 1 SER CONFIRMATORY ISSUE 28 HOPE CREEK GENERATING STATION DOCKET NO. 50-351 Main Steam Tunnel Flooding Analysis, Revision 1, is attached for NRC review as additional information for Public Service Electric and Gas Company's response to SER Confirmatory ,

, Issue 28 (see letter dated May 24, 1985, R.L. Mittl, PSE&G to W. Butler, NRC).

This revised analysis includes a feedwater crosstic isolation ,

valve which has been installed within the main steam tunnel subsequent to the May 24, 1985 submittal.

This valve will be included in the appropriato equipment qualification section of the HCGS FSAR in a future amendment.

Sincerely, w+.

- Ygn EDA"I E N !a* .

Attachment OI C. D.H. Wagner j g USNRC Licensing Project Manager R.W. Borchardt USNRC Senior Resident Inspector m

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i SER' ISSUE C-28 (SER SUPP. 3, SECTION 8.3.3.1.4) l . MAIN STEAM TUNNEL ~ FLOODING ANALYSIS In Section 8.3.3.1.4 of'the SER, the staff documented the applicant's commitment to perform an analysis to verify that Hope Creek could be shut down safely after a main steam tunnel flooding event.

The applicant submitted the main steam t.unnel flooding analysis by letter dated May 24, 1985. This analysis identifies all Class 1E equipment and components in the main steam tunnel, Room 4316, that will be subject to the worst-case submergence that results from a break in a main feedwater line. (Flood level is elevation 126 ft of this room.)

Also, this report analyzes whether the equipment or. component is qualified for submergence. If not qualified, a determination is made whether the equipment of component circuitry has

. primary and backup protective devices located in a hazard-free area. The purpose of this analysis is to demonstrate that the plant can be safely shut down after both the primary and backup protective device open as a result of the failure of unprotected equipment or component together with the worst-case single _ failure.

The results of the analysis show that none of the components that are flooded and are not qualified for submergence are required for safe shutdown of the plant, nor will their failure _ prevent safe shutdown. Because of the redundancy of_the equipment / systems that are required to safely shut i down.the plant, no single failure can prevent safe shutdown.

On the basis of its evaluation of this report, the staff

! finds that the analysis satisfies its concerns and, therefore, this confirmatory item is acceptably resolved.

RESPONSE

The attached report entitled, " Main Steam Tunnel Flooding l Analysis", Revision 1, for Hope Creek Generating Station, dated February 1986 includes the flooding analysis of motor operated feedwater crosstie isolation valve, 1AE-HV-4144, r which has been installed subsequent to the May 24, 1985 submittal discussed above. As discussed in the attached revision of the main steam tunnel flooding analysis, this l

l valve has primary and backup protective devices and is t not required for safe shutdown following a feedwater line break in the steam tunnel.

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