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| number = ML20010B096
| number = ML20010B096
| issue date = 05/31/1981
| issue date = 05/31/1981
| title = Technical Evaluation of Response to Position 5 of Item II.E.4.2 of NUREG-0737,Containment Isolation Setpoint for Fort Calhoun Nuclear Power Plant.
| title = Technical Evaluation of Response to Position 5 of Item II.E.4.2 of NUREG-0737,Containment Isolation Setpoint for Fort Calhoun Nuclear Power Plant
| author name = Broderick N, Ruvalcaba W, Wade W
| author name = Broderick N, Ruvalcaba W, Wade W
| author affiliation = LAWRENCE LIVERMORE NATIONAL LABORATORY
| author affiliation = LAWRENCE LIVERMORE NATIONAL LABORATORY
Line 18: Line 18:


=Text=
=Text=
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Energy Measurements Group Sari Ramon Operations SRO-250 May 19cl TECHNICAL EVALUATION OF THE RES?ONSE TO POSITION NO.5 OF ITEM 3I. E. 4.2 OF NUREG-0737 CONTAINMENT ISOLATION SETPOINT FOR THE               e     -
Energy Measurements Group Sari Ramon Operations SRO-250 May 19cl TECHNICAL EVALUATION OF THE RES?ONSE TO POSITION NO.5 OF ITEM 3I. E. 4.2 OF NUREG-0737 CONTAINMENT ISOLATION SETPOINT FOR THE e
FORT CALHOUN NUCLEAR POWER PLANT COC CK ET NC. SC-OSS)                   -
FORT CALHOUN NUCLEAR POWER PLANT COC CK ET NC. SC-OSS)
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* This document is UNCLASSI.:IED Dari vati va 05 assifier:         $< d                 M M./
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                                                        ~ 31cnotas i: srecericx Decar: men: Manager 8108130330 810728 PDR ADOCK 05000285 P                   PDR v 'orm Performec {cr Lawrence Livermore Naticesi Lacoratcry uncer U.S. O ecar ment of Energy Centrac Nc. O E. ACO S-7d NVC ~183.
: 4. duvai0aDa Departmen: Manacer
* This document is UNCLASSI.:IED Dari vati va 05 assifier: $< d M M./
~ 31cnotas i: srecericx Decar: men: Manager 8108130330 810728 PDR ADOCK 05000285 P
PDR v 'orm Performec {cr Lawrence Livermore Naticesi Lacoratcry uncer U.S. O ecar ment of Energy Centrac Nc. O E. ACO S-7d NVC ~183.


_.    ,-                _-        -          . . _ - .              -                            . l
9 INTRODUCTION AND BACKGROUND As a consequence of tne incident at TMI-2, implementation of a numcer of new recuirements nas been reconnended for operating reac:ces.
                                                                          .                        9 INTRODUCTION AND BACKGROUND As a consequence of tne incident at TMI-2, implementation of a numcer of new recuirements nas been reconnended for operating reac:ces.
Tnese new requirements are described in NUREG-0560, "NRC Action Plan Uevel-oped as a Result of :ne TMI-2 Accident," May 1950, and NUREG-0737, "Clari-fication of TMI Action Plan Requirements," Nove=cer 1980.
Tnese new requirements are described in NUREG-0560, "NRC Action Plan Uevel-oped as a Result of :ne TMI-2 Accident," May 1950, and NUREG-0737, "Clari-fication of TMI Action Plan Requirements," Nove=cer 1980. Tne NRC staff nas also requested licensees to suomit information sufficient to permit an indepencent evaluation of tneir response to :nese new requirements. Inis recort provides an evaluation of tne response to Actica Plan Item II.E.4.2, position 5, by :ne designated licensee.
Tne NRC staff nas also requested licensees to suomit information sufficient to permit an indepencent evaluation of tneir response to :nese new requirements.
DESICi BASIS OR REVIEW CRITERIA Position 5 requires :na :ne cantainment Oressure se::oin: na:
Inis recort provides an evaluation of tne response to Actica Plan Item II.E.4.2, position 5, by :ne designated licensee.
initiates c:ntainment isolation for non-essential systam containmen vessel penetrations be at, Or recuced to, ". . .the minimum compa-iole i:n normal
DESICi BASIS OR REVIEW CRITERIA Position 5 requires :na :ne cantainment Oressure se::oin:
;                operating c:ncitions."                                         e         -
na:
TECHNICAL EVALUATION             _        .
initiates c:ntainment isolation for non-essential systam containmen vessel penetrations be at, Or recuced to, "...the minimum compa-iole i:n normal operating c:ncitions."
Res?cnse evaluation is cased uce.n :ne values pr0vicec f:r               ne 4
e TECHNICAL EVALUATION Res?cnse evaluation is cased uce.n :ne values pr0vicec f:r ne foll: wing parameters:
foll: wing parameters:
4 1
1~
~
( '. ) ine maximum 0:servec or ex:ec:ec containmen           pressure -
( '. )
ine maximum 0:servec or ex:ec:ec containmen pressure -
curing ncroal operation.
curing ncroal operation.
(2)   Tne 1::: errer anc ::servec crif: n               ne :ressure
(2)
,                                    sensing ins rumen a- :n :r:.::ing :ne iscia::en s;;na; (see n, e).                            .
Tne 1::: errer anc ::servec crif: n ne :ressure sensing ins rumen a- :n :r:.::ing :ne iscia::en s;;na; (see n, e).
(3)   Tne containment isciatica pressure sa :oin:.
(3)
Tne containment isciatica pressure sa :oin:.
l
l
(                               NOTE: T'n e clarification Occument (NUREG-0737)       roviced 0-ly
(
NOTE: T' e clarification Occument (NUREG-0737) roviced 0-ly n
:ne ex:ec ac margin f r instrumen: error anc cic nc:
:ne ex:ec ac margin f r instrumen: error anc cic nc:
s:ecify acceptacle values for inst.umen: crif; cr a mospneric cnanges contricuting_ :o :ne stal sensing loco eraer. Acc1:icnal staff guidance estaolisnec a
s:ecify acceptacle values for inst.umen: crif; cr a mospneric cnanges contricuting_ :o :ne stal sensing loco eraer.
;.                                    l i t ' *. of 3.0 psi for an isola-ion se: point margin over l
Acc1:icnal staff guidance estaolisnec a l i t ' *. of 3.0 psi for an isola-ion se: point margin over l
:ne normal containment pressure to accour.: for total
:ne normal containment pressure to accour.: for total loop ef or.
;                                      loop ef or.         In aceition, for sumatmosoneric contain-J                                     ments, a 3.0 psi se point margin over atmospneric i
In aceition, for sumatmosoneric contain-J ments, a 3.0 psi se point margin over atmospneric i
pressure is also c:nsicerec acceptable.
pressure is also c:nsicerec acceptable.
In consideration of these values, :ne isolation pressure se: point
In consideration of these values, :ne isolation pressure se: point is to be as low as practical wi nout increasing :ne procacility of inaaver-l tent activation of tne isolation signal.
;                is to be as low as practical wi nout increasing :ne procacility of inaaver-tent activation of tne isolation signal.
CONCLUSIONS-The letter of Decemoer 31, 1980, suomi;;ec sy C=ana Puolic Power Di stri ct. provided sufficient information to concluce nat :ne.c:ntainment l
l CONCLUSIONS-
isolatien pressure se: point for For. Calnoun Nuclear ? wer Plan: meets :ne l
* The letter of Decemoer 31, 1980, suomi;;ec sy C=ana Puolic Power Di stri ct . provided sufficient information to concluce nat :ne.c:ntainment l                 isolatien pressure se: point for For. Calnoun Nuclear ? wer Plan: meets :ne l
NUREG-0660/0737 requirements and is witnin :ne accitional limiting guice-lines proviced by :ne NRC staff, it
NUREG-0660/0737 requirements and is witnin :ne accitional limiting guice-lines proviced by :ne NRC staff, it


ENCLOSURE 8
ENCLOSURE 8
                          ~                     '.      .
~
CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION
CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION
                                                                                    ~
~
3.6.1.7 The containment purge supply and exhaust isolation valves may be open for safety-related reasons [or chall be locked closed]. The cc .tainment vent line isolation valves may- be open for safety-related reasons [or shall be locked closed).
3.6.1.7 The containment purge supply and exhaust isolation valves may be open for safety-related reasons [or chall be locked closed]. The cc.tainment vent line isolation valves may-be open for safety-related reasons [or shall be locked closed).
APPLICABILITY:       MODES 1, 2, 3, and 4.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
ACTION:
(For plants with valves closed by tecnnical spe,cification)
(For plants with valves closed by tecnnical spe,cification)
With one containment purge supply and/or one exhaust isolation valve open, close the open valve (s) within one hour or be in' at least HOT STA"D3Y within the next 6 hours and in COLD SHUTOOWN within the following 30 h:urs.                .
With one containment purge supply and/or one exhaust isolation valve open, close the open valve (s) within one hour or be in' at least HOT STA"D3Y within the next 6 hours and in COLD SHUTOOWN within the following 30 h:urs.
(For plants with valves that may be opened by techn1{ cal specifications)
(For plants with valves that may be opened by techn1{ cal specifications) 1.
: 1. With one containment purge supply and/or o.ne exhaust isolation or vent val,e inoperable, close the associated OPERABLE valve and either restore the inoperable val /e to CPERABLE status within 72 hours or lock -the C?ERABLE valve closed.
With one containment purge supply and/or o.ne exhaust isolation or vent val,e inoperable, close the associated OPERABLE valve and either restore the inoperable val /e to CPERABLE status within 72 hours or lock -the C?ERABLE valve closed.
: 2. Operation   ty then continue until cerformance of the next required valve :est provided tha: the OPERA 5LE valve is verified to be locked closed at least cnce per 31 days.
Operation ty then continue until cerformance of the next required 2.
: 3. Otherwise, be in at least HOT STAND 3Y within the next six hours and in COLD SHUTOCWN wi-hin the following 30 hours.                            -. --.
valve :est provided tha: the OPERA 5LE valve is verified to be locked closed at least cnce per 31 days.
: i. The provisions of Specification 3.0.4 are not applicable.
3.
SURVEILLANCE REOUIREMENTS a.5.1.7.1 ine         -inch containment purge supply and exhaust isolation valves
Otherwise, be in at least HOT STAND 3Y within the next six hours and in COLD SHUTOCWN wi-hin the following 30 hours.
                                      ~
The provisions of Specification 3.0.4 are not applicable.
and the - -inen vent line isolation valves shall be determined locked closed at least ence per 31 days.
i.
SURVEILLANCE REOUIREMENTS
-inch containment purge supply and exhaust isolation valves a.5.1.7.1 ine
-inen vent line isolation valves shall be determined locked closed
~
and the -
at least ence per 31 days.
4.5.1.7.2 The valve seals of the purge supply and exhaust isolation valves and the vent line isolation valves shall be replaced at least one per ___ years.
4.5.1.7.2 The valve seals of the purge supply and exhaust isolation valves and the vent line isolation valves shall be replaced at least one per ___ years.
3/4 6'-10}}
3/4 6'-10}}

Latest revision as of 07:25, 21 December 2024

Technical Evaluation of Response to Position 5 of Item II.E.4.2 of NUREG-0737,Containment Isolation Setpoint for Fort Calhoun Nuclear Power Plant
ML20010B096
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 05/31/1981
From: Broderick N, Ruvalcaba W, Wade W
LAWRENCE LIVERMORE NATIONAL LABORATORY
To:
Shared Package
ML20010B090 List:
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.2, TASK-TM NUDOCS 8108130330
Download: ML20010B096 (3)


Text

.s' i.

~

Energy Measurements Group Sari Ramon Operations SRO-250 May 19cl TECHNICAL EVALUATION OF THE RES?ONSE TO POSITION NO.5 OF ITEM 3I. E. 4.2 OF NUREG-0737 CONTAINMENT ISOLATION SETPOINT FOR THE e

FORT CALHOUN NUCLEAR POWER PLANT COC CK ET NC. SC-OSS)

E?

W. O.-WaCe A:Or0vec f r ?u:'.

2.ic.

!'l Y f l--

4

4. duvai0aDa Departmen: Manacer
  • This document is UNCLASSI.:IED Dari vati va 05 assifier: $< d M M./

~ 31cnotas i: srecericx Decar: men: Manager 8108130330 810728 PDR ADOCK 05000285 P

PDR v 'orm Performec {cr Lawrence Livermore Naticesi Lacoratcry uncer U.S. O ecar ment of Energy Centrac Nc. O E. ACO S-7d NVC ~183.

9 INTRODUCTION AND BACKGROUND As a consequence of tne incident at TMI-2, implementation of a numcer of new recuirements nas been reconnended for operating reac:ces.

Tnese new requirements are described in NUREG-0560, "NRC Action Plan Uevel-oped as a Result of :ne TMI-2 Accident," May 1950, and NUREG-0737, "Clari-fication of TMI Action Plan Requirements," Nove=cer 1980.

Tne NRC staff nas also requested licensees to suomit information sufficient to permit an indepencent evaluation of tneir response to :nese new requirements.

Inis recort provides an evaluation of tne response to Actica Plan Item II.E.4.2, position 5, by :ne designated licensee.

DESICi BASIS OR REVIEW CRITERIA Position 5 requires :na :ne cantainment Oressure se::oin:

na:

initiates c:ntainment isolation for non-essential systam containmen vessel penetrations be at, Or recuced to, "...the minimum compa-iole i:n normal operating c:ncitions."

e TECHNICAL EVALUATION Res?cnse evaluation is cased uce.n :ne values pr0vicec f:r ne foll: wing parameters:

4 1

~

( '. )

ine maximum 0:servec or ex:ec:ec containmen pressure -

curing ncroal operation.

(2)

Tne 1::: errer anc ::servec crif: n ne :ressure sensing ins rumen a- :n :r:.::ing :ne iscia::en s;;na; (see n, e).

(3)

Tne containment isciatica pressure sa :oin:.

l

(

NOTE: T' e clarification Occument (NUREG-0737) roviced 0-ly n

ne ex:ec ac margin f r instrumen: error anc cic nc:

s:ecify acceptacle values for inst.umen: crif; cr a mospneric cnanges contricuting_ :o :ne stal sensing loco eraer.

Acc1:icnal staff guidance estaolisnec a l i t ' *. of 3.0 psi for an isola-ion se: point margin over l

ne normal containment pressure to accour.: for total loop ef or.

In aceition, for sumatmosoneric contain-J ments, a 3.0 psi se point margin over atmospneric i

pressure is also c:nsicerec acceptable.

In consideration of these values, :ne isolation pressure se: point is to be as low as practical wi nout increasing :ne procacility of inaaver-l tent activation of tne isolation signal.

CONCLUSIONS-The letter of Decemoer 31, 1980, suomi;;ec sy C=ana Puolic Power Di stri ct. provided sufficient information to concluce nat :ne.c:ntainment l

isolatien pressure se: point for For. Calnoun Nuclear ? wer Plan: meets :ne l

NUREG-0660/0737 requirements and is witnin :ne accitional limiting guice-lines proviced by :ne NRC staff, it

ENCLOSURE 8

~

CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION

~

3.6.1.7 The containment purge supply and exhaust isolation valves may be open for safety-related reasons [or chall be locked closed]. The cc.tainment vent line isolation valves may-be open for safety-related reasons [or shall be locked closed).

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

(For plants with valves closed by tecnnical spe,cification)

With one containment purge supply and/or one exhaust isolation valve open, close the open valve (s) within one hour or be in' at least HOT STA"D3Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTOOWN within the following 30 h:urs.

(For plants with valves that may be opened by techn1{ cal specifications) 1.

With one containment purge supply and/or o.ne exhaust isolation or vent val,e inoperable, close the associated OPERABLE valve and either restore the inoperable val /e to CPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or lock -the C?ERABLE valve closed.

Operation ty then continue until cerformance of the next required 2.

valve :est provided tha: the OPERA 5LE valve is verified to be locked closed at least cnce per 31 days.

3.

Otherwise, be in at least HOT STAND 3Y within the next six hours and in COLD SHUTOCWN wi-hin the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

The provisions of Specification 3.0.4 are not applicable.

i.

SURVEILLANCE REOUIREMENTS

-inch containment purge supply and exhaust isolation valves a.5.1.7.1 ine

-inen vent line isolation valves shall be determined locked closed

~

and the -

at least ence per 31 days.

4.5.1.7.2 The valve seals of the purge supply and exhaust isolation valves and the vent line isolation valves shall be replaced at least one per ___ years.

3/4 6'-10