ML20059K822: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:,
{{#Wiki_filter:,
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  ' ~~ ENTERGY                                               eo Box 75e Por1Gibson,MS 39150 Tel 601437 2800 November 8, 1993                                       @O'""
o,.o
,c. i.
' ~~ ENTERGY eo Box 75e Por1Gibson,MS 39150 Tel 601437 2800 November 8, 1993
@O'""
Operators -
Operators -
Grand Gut! Nocear Staton U.S. Nuclear Regulatory Commission Mail Station Pl-37 Washington, D.C. 20555 Attention:     Document Control Desk
Grand Gut! Nocear Staton U.S. Nuclear Regulatory Commission Mail Station Pl-37 Washington, D.C.
20555 Attention:
Document Control Desk


==Subject:==
==Subject:==
Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29 Verification of Standby Service Water and Fuel Pool Cooling Flow Rates GNRO-93/00131 Gentlemen:
Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29 Verification of Standby Service Water and Fuel Pool Cooling Flow Rates GNRO-93/00131 Gentlemen:
In a {{letter dated|date=November 01, 1991|text=letter dated November 01, 1991}} (GNRO-91/00145), Entergy Operations, on behalf of the Grand Gulf Nuclear Station (GGNS) proposed an engineering solution that would. provide sufficient spent fuel pool cooling capacity for the worst case normal design decay heat loads for the spent fuel pool. The worst case being a full pool containing 4348 spent fuel assemblies.
In a {{letter dated|date=November 01, 1991|text=letter dated November 01, 1991}} (GNRO-91/00145), Entergy Operations, on behalf of the Grand Gulf Nuclear Station (GGNS) proposed an engineering solution that would. provide sufficient spent fuel pool cooling capacity for the worst case normal design decay heat loads for the spent fuel pool.
The worst case being a full pool containing 4348 spent fuel assemblies.
The solution proposed consisted of operation of the fuel pool cooling and cleanup system (FPCC) with one FPCC pump through two FPCC heat exchangers with cooling provided by standby service water (SSW).
The solution proposed consisted of operation of the fuel pool cooling and cleanup system (FPCC) with one FPCC pump through two FPCC heat exchangers with cooling provided by standby service water (SSW).
In a {{letter dated|date=July 30, 1992|text=letter dated July 30, 1992}} (GNRI-92/00163), the NRC provided its Safety Evaluation Report (SER) approving this mode of operation of the FPCC as a means of insuring sufficient spent fuel pool decay heat removal without reliance on the residual heat removal system for back up cooling.
In a {{letter dated|date=July 30, 1992|text=letter dated July 30, 1992}} (GNRI-92/00163), the NRC provided its Safety Evaluation Report (SER) approving this mode of operation of the FPCC as a means of insuring sufficient spent fuel pool decay heat removal without reliance on the residual heat removal system for back up cooling.
Final approval was contingent on verification that the increased SSW and FPCC flows necessary for the one pump two heat exchanger mode of operation are within the capability of the systems.
Final approval was contingent on verification that the increased SSW and FPCC flows necessary for the one pump two heat exchanger mode of operation are within the capability of the systems.
The SER requested these flow results be submitted prior to restart from refueling outage six. This letter fulfills that commitment by providing results from system tests which verify these increased flows are obtainable, while maintaining the required flows to other components.
The SER requested these flow results be submitted prior to restart from refueling outage six.
110095                           f90\
This letter fulfills that commitment by providing results from system tests which verify these increased flows are obtainable, while maintaining the required flows to other components.
G9310051                                     1
110095 f90\\
* 9311160208 931108 PDR ADOCK 05000416 hj R                          \
G9310051 1
P              PDR   Q
9311160208 931108 R
\\
PDR ADOCK 05000416 hj P
PDR Q


                                  -~         ----                  - - - --- - -----
-~
November 8, 1993 GNRO-93/00131 Page 2 of 3 equest submittal A forthcoming GGNS operating license change   it ofr 2324 h(TS4348 to   remove the Technical Specifications limspent fuel assemb 5.6.3)                                        l cooling issue to a spaces in the GGNS spent fuel pool,results will bring the GGNS close.
November 8, 1993 GNRO-93/00131 Page 2 of 3 equest submittal A forthcoming GGNS operating license change r it of 2324 (TS to remove the Technical Specifications limspent fuel assem h
4348 spaces in the GGNS spent fuel pool,results will bring the GGNS 5.6.3) l cooling issue to a close.
Yours truly,
Yours truly,
                        ,. /* W CRH/JEO/   c attachment:  FPCC and SSW Flow Results (w/a) cc:
/* W CRH/JEO/
Mr. R. H. Bernhard Mr. H. W. Keiser (w/a)
c FPCC and SSW Flow Results (w/a) attachment:
Mr. R. H. Bernhard Mr. H. W. Keiser (w/a) cc:
Mr. R. B. McGehee (w/a)
Mr. R. B. McGehee (w/a)
Mr. N. S. Reynolds (w/a)
Mr. N. S. Reynolds (w/a)
Mr. H. L. Thomas (w/o)
Mr. H. L. Thomas (w/o)
Mr. Stewart D. Ebneter (w/a)
Ebneter (w/a)
Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta St., N.W., Suite 2900 30323 Atlanta, Georgia Mr. P. W. O'Connor, Project Manager (w/2)
Mr. Stewart D.
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 13H3         20555 Washington, D.C.
Regional Administrator U.S. Nuclear Regulatory Commission Region II Suite 2900 101 Marietta St.,
G9310051
N.W.,
30323 Atlanta, Georgia O'Connor, Project Manager (w/2)
Mr. P. W.
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 13H3 Washington, D.C.
20555 G9310051


1 i       .
1 i
l
Attachmnnt to GNRO-93/00131 j
;                                                Attachmnnt to GNRO-93/00131     j rage 1 of 1   ]
rage 1 of 1
i l                   VERIFICATION OF INCREASED FUEL POOL AND STANDBY           f j                               SERVICE NATER SYSTEK FLONS
]
:i                                                                             i REQUIRED           TEST       t FLON             DATA a
i l
l         FPCC Pump A                             1600           1620 GPM
VERIFICATION OF INCREASED FUEL POOL AND STANDBY f
;        FPCC Pump B                             1600           1600 GPM
j SERVICE NATER SYSTEK FLONS
,        SSW A*
:i i
A and B Fuel Pool HTEXs                 2508           2556 GPM h
REQUIRED TEST t
FLON DATA a
l FPCC Pump A 1600 1620 GPM FPCC Pump B 1600 1600 GPM SSW A*
A and B Fuel Pool HTEXs 2508 2556 GPM h
l i
l i
          *The "A" Train, which has higher flow requirements was tested.
*The "A" Train, which has higher flow requirements was tested.
Apart from the flow differences, both A and B trains are identical.                                                       ,
Apart from the flow differences, both A and B trains are identical.
i f
i f
i G9310051
i G9310051
                                                                                  ,}}
,}}

Latest revision as of 01:22, 17 December 2024

Provides Results from Sys Tests Which Verified That Increased SSW & Fuel Pool Cooling Flow Rates Obtainable While Maintaining Required Flows to Other Components
ML20059K822
Person / Time
Site: Grand Gulf 
Issue date: 11/08/1993
From: Hutchinson C
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GNRO-93-00131, GNRO-93-131, NUDOCS 9311160208
Download: ML20059K822 (3)


Text

,

s,..

o,.o

,c. i.

' ~~ ENTERGY eo Box 75e Por1Gibson,MS 39150 Tel 601437 2800 November 8, 1993

@O'""

Operators -

Grand Gut! Nocear Staton U.S. Nuclear Regulatory Commission Mail Station Pl-37 Washington, D.C.

20555 Attention:

Document Control Desk

Subject:

Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29 Verification of Standby Service Water and Fuel Pool Cooling Flow Rates GNRO-93/00131 Gentlemen:

In a letter dated November 01, 1991 (GNRO-91/00145), Entergy Operations, on behalf of the Grand Gulf Nuclear Station (GGNS) proposed an engineering solution that would. provide sufficient spent fuel pool cooling capacity for the worst case normal design decay heat loads for the spent fuel pool.

The worst case being a full pool containing 4348 spent fuel assemblies.

The solution proposed consisted of operation of the fuel pool cooling and cleanup system (FPCC) with one FPCC pump through two FPCC heat exchangers with cooling provided by standby service water (SSW).

In a letter dated July 30, 1992 (GNRI-92/00163), the NRC provided its Safety Evaluation Report (SER) approving this mode of operation of the FPCC as a means of insuring sufficient spent fuel pool decay heat removal without reliance on the residual heat removal system for back up cooling.

Final approval was contingent on verification that the increased SSW and FPCC flows necessary for the one pump two heat exchanger mode of operation are within the capability of the systems.

The SER requested these flow results be submitted prior to restart from refueling outage six.

This letter fulfills that commitment by providing results from system tests which verify these increased flows are obtainable, while maintaining the required flows to other components.

110095 f90\\

G9310051 1

9311160208 931108 R

\\

PDR ADOCK 05000416 hj P

PDR Q

-~

November 8, 1993 GNRO-93/00131 Page 2 of 3 equest submittal A forthcoming GGNS operating license change r it of 2324 (TS to remove the Technical Specifications limspent fuel assem h

4348 spaces in the GGNS spent fuel pool,results will bring the GGNS 5.6.3) l cooling issue to a close.

Yours truly,

/* W CRH/JEO/

c FPCC and SSW Flow Results (w/a) attachment:

Mr. R. H. Bernhard Mr. H. W. Keiser (w/a) cc:

Mr. R. B. McGehee (w/a)

Mr. N. S. Reynolds (w/a)

Mr. H. L. Thomas (w/o)

Ebneter (w/a)

Mr. Stewart D.

Regional Administrator U.S. Nuclear Regulatory Commission Region II Suite 2900 101 Marietta St.,

N.W.,

30323 Atlanta, Georgia O'Connor, Project Manager (w/2)

Mr. P. W.

Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 13H3 Washington, D.C.

20555 G9310051

1 i

Attachmnnt to GNRO-93/00131 j

rage 1 of 1

]

i l

VERIFICATION OF INCREASED FUEL POOL AND STANDBY f

j SERVICE NATER SYSTEK FLONS

i i

REQUIRED TEST t

FLON DATA a

l FPCC Pump A 1600 1620 GPM FPCC Pump B 1600 1600 GPM SSW A*

A and B Fuel Pool HTEXs 2508 2556 GPM h

l i

  • The "A" Train, which has higher flow requirements was tested.

Apart from the flow differences, both A and B trains are identical.

i f

i G9310051

,