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                                                                                                    'w     -+---m.m.,
'w
-+---m.m.,
I:
I:
aELGED
aELGED
* k UNITED STATES OF AMERICA                             iMU7 NUCLEAR REGULATORY C0tGIISSION Before the Atomic Safety and Licensing Board 02 In the Matter of                                                      //fy y P3;5g
* k UNITED STATES OF AMERICA iMU7 NUCLEAR REGULATORY C0tGIISSION Before the Atomic Safety and Licensing Board 02
                                                            ) .
//fy y P3;5g In the Matter of
rr .      .
)
                                                            )                   iK CLEVELAND ELECTRIC ILLUMINATING         )   Docket Nos. 50-4407 COMPANY, Et t_A1                    )                 50-441
rr.
                                                            )   (Operating Lic n_
)
(Perry Nuclear Power Plant,             )
iK CLEVELAND ELECTRIC ILLUMINATING
03 Units 1 and 2)                                           \                   eg"
)
                                                                            }/
Docket Nos. 50-4407 COMPANY, Et A1
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y:         ,        e       -
50-441 t_
OHIO CITIZENS FOR RESPONSIBLE ENERGL$
)
(Operating Lic n_
(Perry Nuclear Power Plant,
)
03 Units 1 and 2)
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A y
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e OHIO CITIZENS FOR RESPONSIBLE ENERGL$ 'a f
THIRD SET OF INTERROGATORIES TO NRC STAFF
THIRD SET OF INTERROGATORIES TO NRC STAFF
                                                                                'a
~,
                                                                                                        ~,
/
                                                                                                              /
' Ohio Citizens for Responsible Energy ("0CRE e
f
propounds its third set of interrogatories to the NRC Staff, pursuant to the Licensing Board's Memorandum and Order of July 28, 1981 (LBP-81-24, 14 Nhc 175 (1981)).
                        ' Ohio Citizens for Responsible Energy ("0CRE           e propounds its third set of interrogatories to the NRC Staff, pursuant to the Licensing Board's Memorandum and Order of July 28, 1981 (LBP-81-24, 14 Nhc 175 (1981)).
Statement of Purpose The following interrogatories are designed to determine j
Statement of Purpose The following interrogatories are designed to determine j
                  'the Staff's assessment of the potential at PNPP for the type                                           ':
'the Staff's assessment of the potential at PNPP for the type i
i of accident described in NUREG-0785 resulting from a pipe break                                         4, 4
of accident described in NUREG-0785 resulting from a pipe break 4
to the scram discharge volume and to determine the Staff's                                               !
4 to the scram discharge volume and to determine the Staff's regulatory position o'n this problem.
regulatory position o'n this problem.                                                                   h
h
                                                                '                                                        ;i Interrogatories                                                             g.
;i Interrogatories g.
{
3-1.
3-1.
{
Does the so-called " hydraulic" solution or fix to the
Does the so-called " hydraulic" solution or fix to the
                          ~                                                                                               g BWR ATWS problem involve any modification of the SDV system?     If so, describe in detail these modifications                       6           '
~
as they would be required for PNPP.                                                           "
g BWR ATWS problem involve any modification of the SDV system?
If so, describe in detail these modifications 6
as they would be required for PNPP.
3-2.
3-2.
Does the NRC require temperature, humidity, or radiation                                       :
Does the NRC require temperature, humidity, or radiation i
i monitors / detectors at or near the SDV to detect breaks in-the SDV or SDIV?
monitors / detectors at or near the SDV to detect breaks in-the SDV or SDIV?
)
3-3.
3-3.
Has the Staff-submitted any guidelines or rules requiring.                                     )
Has the Staff-submitted any guidelines or rules requiring.
E!
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-b pop


s break detection instruments as described in 3-2 above?
s break detection instruments as described in 3-2 above?
3-4. Has there ever been an SDV pipe break recorded by the
3-4.
                                                                          ~
Has there ever been an SDV pipe break recorded by the
NRC?   If so, give salient details.
~
3-5. What emergency operating procedures will the NRC require the Applicants to have available in the control room to use in the event of an SDV pipe break?
NRC?
k 3-6. Does the NRC require training of reactor operators on responding to SDV pipe breaks? If so, describe such training requirements.                                               ,
If so, give salient details.
3-7. Does the Staff currently believe that the isolation of               ;
3-5.
i the SDV system can be assured in the PNPP design as is?               !
What emergency operating procedures will the NRC require the Applicants to have available in the control room to use in the event of an SDV pipe break?
What modifications, if any, would be needed to assure                 ;
k 3-6.
such isolation?                                                       !
Does the NRC require training of reactor operators on responding to SDV pipe breaks? If so, describe such training requirements.
3-8. What arethe Staff's esticates of the maximum flow rate through an SDV pipe break in the Perry design?
3-7.
3-9. Would water lost through the SDV in 'a break become avail-             ,
Does the Staff currently believe that the isolation of i
able for subsequent cooling purposes?   If so, indicate the flow path; i.e., from what point to what point would the coolant ultimately pass?                                           !
the SDV system can be assured in the PNPP design as is?
3-10. If the response to 3-9 above is in'the affirmative, does the rationale include the possibility of that
What modifications, if any, would be needed to assure such isolation?
3-8.
What arethe Staff's esticates of the maximum flow rate through an SDV pipe break in the Perry design?
3-9.
Would water lost through the SDV in 'a break become avail-able for subsequent cooling purposes?
If so, indicate the flow path; i.e.,
from what point to what point would the coolant ultimately pass?
3-10.
If the response to 3-9 above is in'the affirmative, does the rationale include the possibility of that
{
{
{
water steaming (flashing) at the break point?                         {
water steaming (flashing) at the break point?
[
[
3-11. Has the Staff required any modification of the SDV design i
3-11.
for Applicants' plant?   If so, enumerate and explain any such modifications.
Has the Staff required any modification of the SDV design i
3-12. Has the Staff required any changes in the metallurgy of the SDV system for PNPP?   If so, describe in detail.
for Applicants' plant?
3-13. Will the Applicants be required to perform a fatigue                 -
If so, enumerate and explain any such modifications.
analysis on-the Perry SDV system? If so, explain the G
3-12.
Has the Staff required any changes in the metallurgy of the SDV system for PNPP?
If so, describe in detail.
3-13.
Will the Applicants be required to perform a fatigue analysis on-the Perry SDV system?
If so, explain the G


      .~
.~
extent of such requirements.
extent of such requirements.
3-14.
3-14.
Does the Staff intend to hold the Applicants to GDC 54 i
Does the Staff intend to hold the Applicants to GDC 54 and 55 of Appendix h to 10 CPR Part 50 with regard to i
and 55 of Appendix h to 10 CPR Part 50 with regard to isolation valves within the SDV system? If not, why not?
isolation valves within the SDV system?
If not, why not?
3-15.
3-15.
Has the Staff established any surveillance requirements on the SDV system at PNPP?   If so, produce those require-ments.
Has the Staff established any surveillance requirements on the SDV system at PNPP?
3-16.                                                                         I Relevant to 3-15 above, will any surveillance include             ,
If so, produce those require-ments.
radiography? If so, please elaborate.                             e r
I 3-16.
3-17.                                                                       r Has the Staff accepted the recommendations of C. Michelson       _
Relevant to 3-15 above, will any surveillance include radiography?
L of the NRC AEOD that operability of the hi-level scram           E i
If so, please elaborate.
be independent of the SDV venting or draining requirements?     5
e r
[
3-17.
(See 8/1/80 letter from Michelson to H. Denton, Office           t i
r Has the Staff accepted the recommendations of C. Michelson L
of NMR, NRC.)                                                   ~E E
of the NRC AEOD that operability of the hi-level scram E
3-18.                                                                       s Is pipe whip a design consideration for SDV piping               =
i be independent of the SDV venting or draining requirements?
E design?     If so, to what extent?                               E 3-19.                                                                       E In the Staff's opinion, did the suspected act of vandalism       m E
5[
described in PNO-81-109 cause any irreparable harm to           E I_f z
(See 8/1/80 letter from Michelson to H. Denton, Office t
the SDV system that could lead to scram failure or to           b=.
i of NMR, NRC.)
a pipe break in the SDV piping?                                   5 3-20.
~E E
In the Staff's opinion, could the deficiency in the             hk t                           ta stress ana,1ysis for the CRD hydraulic system described         ==
3-18.
in the March 11, 1982 letter from D. Davidson of CEI             b_
Is pipe whip a design consideration for SDV piping s=
to J.                                                           E5 Kepplcr of NRC Region III (water hammer loads from scram valve operation) lead to a . break in the SDV piping?     $b EE Are the modifications proposed by the Applicants in said letter sufficient to preclude this't                             um
E E
                                                                                  ==-
design?
If so, to what extent?
E 3-19.
In the Staff's opinion, did the suspected act of vandalism m
E described in PNO-81-109 cause any irreparable harm to E
I_f z
the SDV system that could lead to scram failure or to b=.
a pipe break in the SDV piping?
5 3-20.
In the Staff's opinion, could the deficiency in the hk t
ta stress ana,1ysis for the CRD hydraulic system described
 
==
in the {{letter dated|date=March 11, 1982|text=March 11, 1982 letter}} from D. Davidson of CEI b_
E5 to J. Kepplcr of NRC Region III (water hammer loads from scram valve operation) lead to a. break in the SDV piping?
$b EE Are the modifications proposed by the Applicants in said letter sufficient to preclude this't um
= = -
M
M
                                                                                  =-
=-
7:
7:


                                                  .k.
.k.
3-21. In the Staff's opinion, could the concerns described in the 3-29-82 letter from A. Schwencer, Division of Licensing, NRC, to D. Davidson, l
3-21.
A                 CEI, re " Fast Scram" Hydrodynamic Loads on Control Rod Drive. Systems, lead to a pipe break in the SDV system?                 -
In the Staff's opinion, could the concerns described in the 3-29-82 letter from A. Schwencer, Division of Licensing, NRC, to D. Davidson, l
3 Respectfully submitted, WW           s$
A CEI, re " Fast Scram" Hydrodynamic Loads on Control Rod Drive. Systems, lead to a pipe break in the SDV system?
3 Respectfully submitted, WW s$
Susan L. Hiatt OCHE Interim Representative 8275 Munson Rd.
Susan L. Hiatt OCHE Interim Representative 8275 Munson Rd.
      '                                                          Mentor, OH     44060 (216) 255-3158 e
Mentor, OH 44060 (216) 255-3158 e
i e
i e


_T
_T
              *~
*~
g eoW CERTIFICATE OF SERVICE                                       ~3 P3:52 6r ;.        -
g eoW CERTIFICATE OF SERVICE
This is to certify that copies of OCRE's SECOND SET; 0F:
~3 P3:52 This is to certify that copies of OCRE's SECOND SET; 0F:
INTERh0GATORIES TO     NRC STAFF were served                 TObyAPPLICANTS deposit in the U.S.and  Mail,THIRDfirst~         SET OF class, on    the postage Service List  prepaid, below.this 29th day of April,1982 to those I                                             !
6r ;.
Susan L. Riatt                                                 i SERVICE LIST g
INTERh0GATORIES TO APPLICANTS and THIRD SET OF TO NRC STAFF were served by deposit in the U.S. Mail, first~
Peter B. Bloch, Chairman                                                                                               5 Atomic Safety and Licensing Board                             Daniel D. Wilt, Esq.                                     $
class, postage prepaid, this 29th day of April,1982 to those on the Service List below.
U.S. Nuclear Regulatory Comm'n                               7301 Cliippewa Rd.
I Susan L. Riatt i
Washington, D.C.               20555                         Brecksville, OH 44141                                     &j h
SERVICE LIST g
Dr. Jerry R. Kline                                                                                                   4 11 Atomic Safety and Licensing Board                                                                                     y U.S. Nuclear Regulatory Comm'n Washington, D. C. 20555                                                                                                 e s,i Frederick J. Shon                                                                                                       b Atomic Safety and Licensing Board                                                                                       55 U.S. Nuclear. Regulatory Comm n                 e Washington, D.C. 20555                                                                                                 .L g
Peter B. Bloch, Chairman 5
Docketing and Service Section                                                                                         g 55 Office of the Secretary U.S. Nuclear Regulatory Comm'n .                                                                                       M
Atomic Safety and Licensing Board Daniel D. Wilt, Esq.
                                                                                                                                      ;g Wkshington, D.C.. 20555 W
U.S. Nuclear Regulatory Comm'n 7301 Cliippewa Rd.
James Thessin, Esq.                                                                                                     $
&j Washington, D.C.
                                                                                                                                      =..
20555 Brecksville, OH 44141 h
Office      of the Executive Legal Director                                                                                                     ;
Dr. Jerry R. Kline 4
U.S. Nuclear Regulatory Comm'n                                                                                           g Washington, D.C. 20555                                                                                                 n
11 Atomic Safety and Licensing Board y
U.S. Nuclear Regulatory Comm'n Washington, D. C.
20555 s,i e
Frederick J. Shon b
Atomic Safety and Licensing Board U.S. Nuclear. Regulatory Comm n 55 e
.L Washington, D.C.
20555 g
Docketing and Service Section g
55 Office of the Secretary U.S. Nuclear Regulatory Comm'n.
M
;g Wkshington, D.C..
20555 W
James Thessin, Esq.
Office of the Executive
=..
Legal Director U.S. Nuclear Regulatory Comm'n g
Washington, D.C.
20555 n
:==
:==
m Jay Silberg, Esq.                                                                                                     555 Ein 1800 M Street, N.W.
m Jay Silberg, Esq.
washington, D.C. 20036                                                                                               $
555 Ein 1800 M Street, N.W.
x 5s
washington, D.C.
;            Atomic Safety and Licensing Appeal Board Panel                                                                         b 1            U.S. NuclearD.C.
20036 x
Washington,          Regulatory Commission                                '
5s Atomic Safety and Licensing Appeal Board Panel b
EE 20555 x           r . . -
U.S. Nuclear Regulatory Commission 1
Washington, D.C.
EE 20555 x
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Latest revision as of 07:32, 18 December 2024

Oh Citizens for Responsible Energy Third Set of Interrogatories Directed to Nrc.Certificate of Svc Encl. Related Correspondence
ML20052D237
Person / Time
Site: Perry  FirstEnergy icon.png
Issue date: 04/29/1982
From: Hiatt S
OHIO CITIZENS FOR RESPONSIBLE ENERGY
To:
NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD)
References
NUDOCS 8205060390
Download: ML20052D237 (5)
v • d • e


Text

--

'w

-+---m.m.,

I:

aELGED

  • k UNITED STATES OF AMERICA iMU7 NUCLEAR REGULATORY C0tGIISSION Before the Atomic Safety and Licensing Board 02

//fy y P3;5g In the Matter of

)

rr.

)

iK CLEVELAND ELECTRIC ILLUMINATING

)

Docket Nos. 50-4407 COMPANY, Et A1

)

50-441 t_

)

(Operating Lic n_

(Perry Nuclear Power Plant,

)

03 Units 1 and 2)

\\

eg

}

/

A y

y:

e OHIO CITIZENS FOR RESPONSIBLE ENERGL$ 'a f

THIRD SET OF INTERROGATORIES TO NRC STAFF

~,

/

' Ohio Citizens for Responsible Energy ("0CRE e

propounds its third set of interrogatories to the NRC Staff, pursuant to the Licensing Board's Memorandum and Order of July 28, 1981 (LBP-81-24, 14 Nhc 175 (1981)).

Statement of Purpose The following interrogatories are designed to determine j

'the Staff's assessment of the potential at PNPP for the type i

of accident described in NUREG-0785 resulting from a pipe break 4

4 to the scram discharge volume and to determine the Staff's regulatory position o'n this problem.

h

i Interrogatories g.

{

3-1.

Does the so-called " hydraulic" solution or fix to the

~

g BWR ATWS problem involve any modification of the SDV system?

If so, describe in detail these modifications 6

as they would be required for PNPP.

3-2.

Does the NRC require temperature, humidity, or radiation i

monitors / detectors at or near the SDV to detect breaks in-the SDV or SDIV?

)

3-3.

Has the Staff-submitted any guidelines or rules requiring.

8205060390 820429 E!

m PDR ADOCM 05000440 O

n

-b pop

s break detection instruments as described in 3-2 above?

3-4.

Has there ever been an SDV pipe break recorded by the

~

NRC?

If so, give salient details.

3-5.

What emergency operating procedures will the NRC require the Applicants to have available in the control room to use in the event of an SDV pipe break?

k 3-6.

Does the NRC require training of reactor operators on responding to SDV pipe breaks? If so, describe such training requirements.

3-7.

Does the Staff currently believe that the isolation of i

the SDV system can be assured in the PNPP design as is?

What modifications, if any, would be needed to assure such isolation?

3-8.

What arethe Staff's esticates of the maximum flow rate through an SDV pipe break in the Perry design?

3-9.

Would water lost through the SDV in 'a break become avail-able for subsequent cooling purposes?

If so, indicate the flow path; i.e.,

from what point to what point would the coolant ultimately pass?

3-10.

If the response to 3-9 above is in'the affirmative, does the rationale include the possibility of that

{

{

water steaming (flashing) at the break point?

[

3-11.

Has the Staff required any modification of the SDV design i

for Applicants' plant?

If so, enumerate and explain any such modifications.

3-12.

Has the Staff required any changes in the metallurgy of the SDV system for PNPP?

If so, describe in detail.

3-13.

Will the Applicants be required to perform a fatigue analysis on-the Perry SDV system?

If so, explain the G

.~

extent of such requirements.

3-14.

Does the Staff intend to hold the Applicants to GDC 54 and 55 of Appendix h to 10 CPR Part 50 with regard to i

isolation valves within the SDV system?

If not, why not?

3-15.

Has the Staff established any surveillance requirements on the SDV system at PNPP?

If so, produce those require-ments.

I 3-16.

Relevant to 3-15 above, will any surveillance include radiography?

If so, please elaborate.

e r

3-17.

r Has the Staff accepted the recommendations of C. Michelson L

of the NRC AEOD that operability of the hi-level scram E

i be independent of the SDV venting or draining requirements?

5[

(See 8/1/80 letter from Michelson to H. Denton, Office t

i of NMR, NRC.)

~E E

3-18.

Is pipe whip a design consideration for SDV piping s=

E E

design?

If so, to what extent?

E 3-19.

In the Staff's opinion, did the suspected act of vandalism m

E described in PNO-81-109 cause any irreparable harm to E

I_f z

the SDV system that could lead to scram failure or to b=.

a pipe break in the SDV piping?

5 3-20.

In the Staff's opinion, could the deficiency in the hk t

ta stress ana,1ysis for the CRD hydraulic system described

==

in the March 11, 1982 letter from D. Davidson of CEI b_

E5 to J. Kepplcr of NRC Region III (water hammer loads from scram valve operation) lead to a. break in the SDV piping?

$b EE Are the modifications proposed by the Applicants in said letter sufficient to preclude this't um

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7:

.k.

3-21.

In the Staff's opinion, could the concerns described in the 3-29-82 letter from A. Schwencer, Division of Licensing, NRC, to D. Davidson, l

A CEI, re " Fast Scram" Hydrodynamic Loads on Control Rod Drive. Systems, lead to a pipe break in the SDV system?

3 Respectfully submitted, WW s$

Susan L. Hiatt OCHE Interim Representative 8275 Munson Rd.

Mentor, OH 44060 (216) 255-3158 e

i e

_T

  • ~

g eoW CERTIFICATE OF SERVICE

~3 P3:52 This is to certify that copies of OCRE's SECOND SET; 0F:

6r ;.

INTERh0GATORIES TO APPLICANTS and THIRD SET OF TO NRC STAFF were served by deposit in the U.S. Mail, first~

class, postage prepaid, this 29th day of April,1982 to those on the Service List below.

I Susan L. Riatt i

SERVICE LIST g

Peter B. Bloch, Chairman 5

Atomic Safety and Licensing Board Daniel D. Wilt, Esq.

U.S. Nuclear Regulatory Comm'n 7301 Cliippewa Rd.

&j Washington, D.C.

20555 Brecksville, OH 44141 h

Dr. Jerry R. Kline 4

11 Atomic Safety and Licensing Board y

U.S. Nuclear Regulatory Comm'n Washington, D. C.

20555 s,i e

Frederick J. Shon b

Atomic Safety and Licensing Board U.S. Nuclear. Regulatory Comm n 55 e

.L Washington, D.C.

20555 g

Docketing and Service Section g

55 Office of the Secretary U.S. Nuclear Regulatory Comm'n.

M

g Wkshington, D.C..

20555 W

James Thessin, Esq.

Office of the Executive

=..

Legal Director U.S. Nuclear Regulatory Comm'n g

Washington, D.C.

20555 n

==

m Jay Silberg, Esq.

555 Ein 1800 M Street, N.W.

washington, D.C.

20036 x

5s Atomic Safety and Licensing Appeal Board Panel b

U.S. Nuclear Regulatory Commission 1

Washington, D.C.

EE 20555 x

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