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i DocketFile(
i                                                                                                                                     DocketFile(
AUG 01 1975 NRR: Reading File J
J                                                                                        AUG 01 1975                                   NRR: Reading File                                 .'
Docket No. 50-263 RSB Reading File 1
;                              Docket No. 50-263                                                                                       RSB Reading File 1                                                                                                                                     V. Stello                                   'l i                                                                                                                                     RS Administrative Asst.                           ,
V. Stello
                                                                                                                                                                                    .i Karl R. Goller, Assistant Director for Operating Reactors, Group 2. RL                                                                     !'
'l i
I
RS Administrative Asst.
:                                        REVIEW OF NEDO-20846, MONTICELLO ATWS SUBMITTAL a
.i Karl R. Goller, Assistant Director for Operating Reactors, Group 2. RL I
;i       !                                Report
REVIEW OF NEDO-20846, MONTICELLO ATWS SUBMITTAL a
;i Report


==Title:==
==Title:==
NEDO-90846, " Anticipated Transients Without Scram Study for the Monticello Generating Plant"'
NEDO-90846, " Anticipated Transients Without Scram Study for the Monticello Generating Plant"'
* Docket No.:                   50-263 4
Docket No.:
Originating Branch and Project Manager: ORB-2, B. Buckley 1         i                               Technical Review Branch Involved: Reactor Systems Branch 1         -                              Description of Review: First Round Questions Review Status: Awaiting Information j                                         In order that we.may continue our review of.the subject topical, 3
50-263 Originating Branch and Project Manager: ORB-2, B. Buckley 4
j                              additional information is requested. The analysis submitted included j           !                              the effects of, proposed plant modifications. In order to satisfy-l           l                             paragraph II.c of Appendix A to WASH-1270 either revise the analysis                                                                         _
1 i
l            !                            to reflect the plant as it is, or submit plans for any proposed plant 4
Technical Review Branch Involved: Reactor Systems Branch 1
changes and a schedule for implementation of these changes.
Description of Review:
1 l
First Round Questions Review Status: Awaiting Information j
Victor Stello, Jr., Assistant Director l
In order that we.may continue our review of.the subject topical, j
for Reactor Safety i
additional information is requested. The analysis submitted included 3
l                                                                                               Division of Technical Review Office of Nuclear Reactor Regulation
j the effects of, proposed plant modifications.
In order to satisfy-l l
paragraph II.c of Appendix A to WASH-1270 either revise the analysis l
to reflect the plant as it is, or submit plans for any proposed plant changes and a schedule for implementation of these changes.
4 1
l l
Victor Stello, Jr., Assistant Director for Reactor Safety i
l Division of Technical Review Office of Nuclear Reactor Regulation


==Enclosure:==
==Enclosure:==
Concerns-on NEDO-20846 l
cc:
S. Hanauer F. Schroeder A. Giambusso 1
: 0. Ziemann B. Buckley T. Novak j
A. Thadani L.-01shan S. Varga i
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;            ;                            Concerns-on NEDO-20846 l
CONCERNS ON NED0-20846 1.
cc:            S. Hanauer
Provide the peak torus water temperature reached during the MSly closure ATWS.
!                                                          F. Schroeder A. Giambusso 1                                                          0. Ziemann
Provide and justify a torus water temperature limit.
:                                                          B. Buckley T. Novak j                                                          A. Thadani L.-01shan
If the calculated temperature exceeds the limit, discuss the plant modifications needed to keep torus water temperature below the proposed limit.
!                                                          S. Varga i                                                          R, Hsint en
NE00-20626 suggests a pool temperature limit of 170*F.
;                                                        - 8 . R $ ' L <- -
If the peak torus water temperature exceeds 170 F discuss plant modifications needed to keep this temperature below 170'F.
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The analysis takes credit for the operator initiating the standby liquid control system five minutes after the ATWS event.
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Discuss the indications available to the operator to assure this manual initiation of the SLC.
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In figure 4-3 the relief valve flow oscillates between about 3,000 and 7,000 lb/sec from about 30 seconds to 95 seconds after t
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the ATWS. At about 108 seconds the relief valve flow begins to oscillate between 3,000 and 14,000 lb/sec.
!                      PDR      ADOCK 05000263.
Explain this difference in the peak relief valve flow.
p                                      PDR      ,    _
4.
        . , --                                            - ,_                                          ....;-.-.-.a.                              . , . - . . ..          - . - -
The Technical Specifications present sodium pentaborate solution concentration versus net tank volume in Figure 3.4.1.
 
The concentration varies from 10.8% to 21.4%.
Enclosure 1                    ,
Perform the analysis using each of these concentrations.
CONCERNS ON NED0-20846
Justify the use of 13% as an initial condition listed in Table 3-1 of NED0-20846. Also justify the poison reactivity worth and provide vessel volume.
: 1. Provide the peak torus water temperature reached during the MSly closure ATWS.     Provide and justify a torus water temperature limit. If the calculated temperature exceeds the limit, discuss the plant modifications needed to keep torus water temperature below the proposed limit. NE00-20626 suggests a pool temperature limit of 170*F. If the peak torus water temperature exceeds 170 F discuss plant modifications needed to keep this temperature below 170'F.
5.
  .                  2. The analysis takes credit for the operator initiating the standby liquid control system five minutes after the ATWS event. Discuss the indications available to the operator to assure this manual initiation of the SLC.
In Section 4.4 of the Technical Specifications a minimum flow rate of 24 gpm for each of the standby liquid control system pumps is listed as a surveillance requirement.
: 3. In figure 4-3 the relief valve flow oscillates between about t
Perform the analysis using this value.
3,000 and 7,000 lb/sec from about 30 seconds to 95 seconds after
In Table 3-2 of NED0-20846 a 28 gpm flow rate per pump is listed.
:                      the ATWS. At about 108 seconds the relief valve flow begins to oscillate between 3,000 and 14,000 lb/sec. Explain this difference in the peak relief valve flow.
Provide your basis for using this L
: 4. The Technical Specifications present sodium pentaborate solution concentration versus net tank volume in Figure 3.4.1. The concentration varies from 10.8% to 21.4%. Perform the analysis using each of these concentrations. Justify the use of 13% as an initial condition listed in Table 3-1 of NED0-20846. Also justify the poison reactivity worth and provide vessel volume.
value in your analysis.
: 5. In Section 4.4 of the Technical Specifications a minimum flow rate of 24 gpm for each of the standby liquid control system pumps is listed as a surveillance requirement. Perform the analysis using this value. In Table 3-2 of NED0-20846 a 28 gpm flow rate per pump is listed. Provide your basis for using this L
Provide the total volume of poison in-jected following the ATWS for both hot shutdown and cold shutdown.
value in your analysis. Provide the total volume of poison in-jected following the ATWS for both hot shutdown and cold shutdown.
i 6.
i                   6. It is stated that no accounting for possible non-homogeneous mixing was made since this would take a detailed evaluation.
It is stated that no accounting for possible non-homogeneous mixing was made since this would take a detailed evaluation.
However, GE stated at a meeting with the staff on August 7, 1974, that tests were being conducted on borated water mixing ohenomena.
However, GE stated at a meeting with the staff on August 7, 1974, that tests were being conducted on borated water mixing ohenomena.
Demonstrate that your assumption of uniform mixina is consistent-with the experimental data. Otherwise, perform a sensitivity study to show the effects.of nonhomogeneous mixing of the liquid -
Demonstrate that your assumption of uniform mixina is consistent-with the experimental data. Otherwise, perform a sensitivity study to show the effects.of nonhomogeneous mixing of the liquid -
poison, varying the mixing efficiency from 50% to 100%.
poison, varying the mixing efficiency from 50% to 100%.
                ~~
~~
: 7. The staff has submitted to General Electric questions on NED0-20626 (letter from V. Stello to I. Stuart, January 28, 1974, and letter from W. Butler to I. Stuart, April 9, 1975). Respond to the following questions as they apply to Monticello:   1, 4, 5, 6, 9, 12, 13, 16, 17, 310.1, 310.3, and 310.5.
 
: 8. Provide the bases for assuming thirty seconds for transport time 3
7.
of the sodium pertaborate solution from the storage tank to the
The staff has submitted to General Electric questions on NED0-20626 (letter from V. Stello to I. Stuart, January 28, 1974, and letter from W. Butler to I. Stuart, April 9, 1975).
;                      vessel and for the liquid to become effective in the core.
Respond to the following questions as they apply to Monticello:
1, 4, 5, 6, 9, 12, 13, 16, 17, 310.1, 310.3, and 310.5.
8.
Provide the bases for assuming thirty seconds for transport time 3
of the sodium pertaborate solution from the storage tank to the vessel and for the liquid to become effective in the core.
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Latest revision as of 21:06, 12 December 2024

Requests Response to Encl Concerns on NEDO-20846,plant ATWS Submittal
ML20125A483
Person / Time
Site: Monticello 
Issue date: 08/01/1975
From: Stello V
Office of Nuclear Reactor Regulation
To: Goller K
Office of Nuclear Reactor Regulation
Shared Package
ML20125A480 List:
References
NUDOCS 9212080363
Download: ML20125A483 (3)


Text

__

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

7

\\

/

3 4

i DocketFile(

AUG 01 1975 NRR: Reading File J

Docket No. 50-263 RSB Reading File 1

V. Stello

'l i

RS Administrative Asst.

.i Karl R. Goller, Assistant Director for Operating Reactors, Group 2. RL I

REVIEW OF NEDO-20846, MONTICELLO ATWS SUBMITTAL a

i Report

Title:

NEDO-90846, " Anticipated Transients Without Scram Study for the Monticello Generating Plant"'

Docket No.:

50-263 Originating Branch and Project Manager: ORB-2, B. Buckley 4

1 i

Technical Review Branch Involved: Reactor Systems Branch 1

Description of Review:

First Round Questions Review Status: Awaiting Information j

In order that we.may continue our review of.the subject topical, j

additional information is requested. The analysis submitted included 3

j the effects of, proposed plant modifications.

In order to satisfy-l l

paragraph II.c of Appendix A to WASH-1270 either revise the analysis l

to reflect the plant as it is, or submit plans for any proposed plant changes and a schedule for implementation of these changes.

4 1

l l

Victor Stello, Jr., Assistant Director for Reactor Safety i

l Division of Technical Review Office of Nuclear Reactor Regulation

Enclosure:

Concerns-on NEDO-20846 l

cc:

S. Hanauer F. Schroeder A. Giambusso 1

0. Ziemann B. Buckley T. Novak j

A. Thadani L.-01shan S. Varga i

R, Hsint en

- 8. R $ ' L <- -

?

c, Can i=

fm A

typr OFPIC

)=

{

. L_ olfshan:db._,_WMinners;....

T_oyaki _ _ySte..

.. a c.-

15/6/75.. _ _547R5 5/J.7%

_5L 3 i

omy Forms AEC.514 (Rev. 9 53) MCM 0240

- # u. s.eovanmusut enintine orrics se74.sas. tee 9212000363 750001' PDR ADOCK 05000263.

PDR p

....;-.-.-.a.

CONCERNS ON NED0-20846 1.

Provide the peak torus water temperature reached during the MSly closure ATWS.

Provide and justify a torus water temperature limit.

If the calculated temperature exceeds the limit, discuss the plant modifications needed to keep torus water temperature below the proposed limit.

NE00-20626 suggests a pool temperature limit of 170*F.

If the peak torus water temperature exceeds 170 F discuss plant modifications needed to keep this temperature below 170'F.

2.

The analysis takes credit for the operator initiating the standby liquid control system five minutes after the ATWS event.

Discuss the indications available to the operator to assure this manual initiation of the SLC.

3.

In figure 4-3 the relief valve flow oscillates between about 3,000 and 7,000 lb/sec from about 30 seconds to 95 seconds after t

the ATWS. At about 108 seconds the relief valve flow begins to oscillate between 3,000 and 14,000 lb/sec.

Explain this difference in the peak relief valve flow.

4.

The Technical Specifications present sodium pentaborate solution concentration versus net tank volume in Figure 3.4.1.

The concentration varies from 10.8% to 21.4%.

Perform the analysis using each of these concentrations.

Justify the use of 13% as an initial condition listed in Table 3-1 of NED0-20846. Also justify the poison reactivity worth and provide vessel volume.

5.

In Section 4.4 of the Technical Specifications a minimum flow rate of 24 gpm for each of the standby liquid control system pumps is listed as a surveillance requirement.

Perform the analysis using this value.

In Table 3-2 of NED0-20846 a 28 gpm flow rate per pump is listed.

Provide your basis for using this L

value in your analysis.

Provide the total volume of poison in-jected following the ATWS for both hot shutdown and cold shutdown.

i 6.

It is stated that no accounting for possible non-homogeneous mixing was made since this would take a detailed evaluation.

However, GE stated at a meeting with the staff on August 7, 1974, that tests were being conducted on borated water mixing ohenomena.

Demonstrate that your assumption of uniform mixina is consistent-with the experimental data. Otherwise, perform a sensitivity study to show the effects.of nonhomogeneous mixing of the liquid -

poison, varying the mixing efficiency from 50% to 100%.

~~

7.

The staff has submitted to General Electric questions on NED0-20626 (letter from V. Stello to I. Stuart, January 28, 1974, and letter from W. Butler to I. Stuart, April 9, 1975).

Respond to the following questions as they apply to Monticello:

1, 4, 5, 6, 9, 12, 13, 16, 17, 310.1, 310.3, and 310.5.

8.

Provide the bases for assuming thirty seconds for transport time 3

of the sodium pertaborate solution from the storage tank to the vessel and for the liquid to become effective in the core.

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