ML20245D592: Difference between revisions

From kanterella
Jump to navigation Jump to search
StriderTol Bot insert
 
StriderTol Bot change
 
Line 19: Line 19:


=Text=
=Text=
{{#Wiki_filter:__ _                  _
{{#Wiki_filter:__ _
L C:mm:nwn:lth Edis:n 9 Zion Gin: rating Station 101 Shiloh Blvd.
L 9 Zion Gin: rating Station C:mm:nwn:lth Edis:n 101 Shiloh Blvd.
Zion, Illinois 60099 Telephone 312/746-2084               Apri1 17, 1989 Director of Nuclear Reactor Regulation N
Zion, Illinois 60099 Telephone 312/746-2084 Apri1 17, 1989 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission N
U.S. Nuclear Regulatory Commission                                           -
Hall Station P1-137 Hashington, D.C. 20555
Hall Station P1-137 Hashington, D.C. 20555


==Subject:==
==Subject:==
Zion Nuclear Power Station, Units 1 and 2 License Nos. DPR-39 and DPR-48                                           i NRC Docket Nos. 50-295 and 50-304 Proposed Amendment to Technical Specification Sections 3.1 and 4.1. "Rgartor Protection System"                       ;
Zion Nuclear Power Station, Units 1 and 2 License Nos. DPR-39 and DPR-48 i
i Gentlemen:
NRC Docket Nos. 50-295 and 50-304 Proposed Amendment to Technical Specification Sections 3.1 and 4.1. "Rgartor Protection System" i
Attached is a proposed Technical Specification amendment for Zion Nuclear Power Station, License Nos. DPR-39 and DPR-48. The proposed amendment addresses Sections 3.1 and 4.1 " Reactor Protection System".
Gentlemen:
The purpose of this revision is to demonstrate compliance with NRC Generic Letter 85-09, entitled " Technical Specifications for Generic Letter 83-28, Item 4.3". The proposed Technical Specification change involves additions and clarifications to Tables 3.1-1 and 4.1-1 to address operability and surveillance requirements for Reactor Protection Channels. Specifically, this
Attached is a proposed Technical Specification amendment for Zion Nuclear Power Station, License Nos. DPR-39 and DPR-48.
                      . proposed amendment will change and/or clarify the operability and surveillance requirements for the following functions: 1) Manual Reactor Trip; 2)
The proposed amendment addresses Sections 3.1 and 4.1 " Reactor Protection System".
The purpose of this revision is to demonstrate compliance with NRC Generic Letter 85-09, entitled " Technical Specifications for Generic Letter 83-28, Item 4.3".
The proposed Technical Specification change involves additions and clarifications to Tables 3.1-1 and 4.1-1 to address operability and surveillance requirements for Reactor Protection Channels.
Specifically, this
. proposed amendment will change and/or clarify the operability and surveillance requirements for the following functions:
: 1) Manual Reactor Trip; 2)
Automatic Reactor Trip Logic; and 3) Reactor Trip and Bypass Breakers.
Automatic Reactor Trip Logic; and 3) Reactor Trip and Bypass Breakers.
A summary of the changes is provided below.
A summary of the changes is provided below.
: 1)   Iahle13-L_page_30 Line_3 The line is changed to correct a spelling error.                         l
1)
: 2)   Jable 3.1-1. pAgas_3L3nd_32 dine _2. Land _ explanation of ED _fontaole The description of the Reactor Protection Channel has been changed     ,
Iahle13-L_page_30 Line_3 The line is changed to correct a spelling error.
from " Automatic Reactor Trip Logic" to " Automatic Reactor Trip Logic, Including Reactor Trip Breakers". The change reflects the request of NRR technical reviewers regarding reactor trip logic, and is closely
l 2)
,                                patterned after similar requirements in effect at Ginna. The (#)
Jable 3.1-1. pAgas_3L3nd_32 dine _2. Land _ explanation of ED _fontaole The description of the Reactor Protection Channel has been changed from " Automatic Reactor Trip Logic" to " Automatic Reactor Trip Logic, Including Reactor Trip Breakers".
!                                footnote has been added to clarify the appropriate action if one of l                                 the diverse trip features is inoperable. This footnote is worded in accordance with Generic Letter 85-09.
The change reflects the request of NRR technical reviewers regarding reactor trip logic, and is closely patterned after similar requirements in effect at Ginna.
The (#)
footnote has been added to clarify the appropriate action if one of l
the diverse trip features is inoperable.
This footnote is worded in
(
(
: 3)     lable_4J-1mpage_35mLtne 1 A note has been added to the " Remarks" column of Line 1 to address OPERABILITY of the undervoltage and shunt trip circuits, of the reactor trip breakers in addition to the OPERABILITY requirement of l                                 the reactor bypass breaker circuit. These remarks closely parallel the guidance contained in Generic Letter 85-09.
accordance with Generic Letter 85-09.
8905010066 890417 PDR       ADOCK 05000295 PNU (j
3) lable_4J-1mpage_35mLtne 1 A note has been added to the " Remarks" column of Line 1 to address OPERABILITY of the undervoltage and shunt trip circuits, of the reactor trip breakers in addition to the OPERABILITY requirement of l
P 15 80                                                                     f I
the reactor bypass breaker circuit.
These remarks closely parallel the guidance contained in Generic Letter 85-09.
8905010066 890417 PDR ADOCK 05000295 (j
P PNU 15 80 f
I


l
l
      '' d                 =
'' d
    ,4 l                                       .
=
4 )' . 'Jable 4.1-1. Dage 36. Lines 21'. 22 and 23 a)   Line.21 has been revised to add Remark No. 11 which requires testing of automatic reactor trip-logic of each train on alternate. months. The requirements of the Remark'are patterned 1
,4 l
after Generic Letter 85-09 and; include the recommendations of NRC Staff personnel.who ' suggested that a similarity to Ginna requirements would be appropriate.
4 )'. 'Jable 4.1-1. Dage 36. Lines 21'. 22 and 23 a)
b)- Line 22 is an addition to the Table which specifies the Channel Functional Test requirements for the Reactor Trip Breakers. The comments contained in.the Remarks column closely conform _to Generic Letter 85-09.
Line.21 has been revised to add Remark No. 11 which requires testing of automatic reactor trip-logic of each train on alternate. months.
c)   Line 23 is an addition to the Table which specifies the Channel Functional Test requirements for the Reactor Trip Bypass                                                         l Breakers. The comments contained in the Remarks column closely                                               j conform to Generic Letter 85-09.                                                                                 '
The requirements of the Remark'are patterned after Generic Letter 85-09 and; include the recommendations of 1
Attachment 1 cantains.the revised pages of the Technical Specifications.
NRC Staff personnel.who ' suggested that a similarity to Ginna requirements would be appropriate.
Attachment 2 contains- the evaluation of significant hazards review.
b)-
As provided by 10 CFR50.91, the State of Illinois is being notified of-                                                     {
Line 22 is an addition to the Table which specifies the Channel Functional Test requirements for the Reactor Trip Breakers.
this amendment request by transmittal of this letter and attachments.                                                             '
The comments contained in.the Remarks column closely conform _to Generic Letter 85-09.
Please direct any. questions that you may have to this office.                                                             ;
c)
i l'
Line 23 is an addition to the Table which specifies the Channel Functional Test requirements for the Reactor Trip Bypass Breakers.
The comments contained in the Remarks column closely j
conform to Generic Letter 85-09. cantains.the revised pages of the Technical Specifications. contains-the evaluation of significant hazards review.
As provided by 10 CFR50.91, the State of Illinois is being notified of-
{
this amendment request by transmittal of this letter and attachments.
Please direct any. questions that you may have to this office.
i l
Ver truly yours,
Ver truly yours,
                                                                                                                    /                                             i G. E. Trzyn                                 ;
/
Nuclear Licensing                           {
i G. E. Trzyn Nuclear Licensing
Administrator                                 ;
{
Zion Station                                 )
Administrator Zion Station
i cc: Chandu Patel - NRR NRC Resident Inspector - Zion M. C. Parker - IDNS l
)
1 I
i cc: Chandu Patel - NRR NRC Resident Inspector - Zion M. C. Parker - IDNS I
l l
l 15180' u____._____-.__.
15180'                                                                                                                           I u____._____-.__.                               _.                                                                                                                  i
i


1 l
1 l
l 1
l 1
ATTACHMENT 1                                     !
ATTACHMENT 1 1
1
. ZION NUCLEAR POWER STATION EROPOSED AMENDliENT.TO
                                    . ZION NUCLEAR POWER STATION EROPOSED AMENDliENT.TO                             )
)
IECHNICAL SPECIFICATION                               l; SECTIONS 3.1 AND 4.1 I
IECHNICAL SPECIFICATION l
SECTIONS 3.1 AND 4.1 I
l i
l i
1 1
1 1
l 1
l 1
I 15180 t
I 15180 t
i E __. _ _ . _ _ _ _ _ . _ _ _    _
i E __. _ _. _ _ _ _ _. _ _ _


4 ZION NUCLEAR POWER STATION PROPOSED AMENDMENT Pages Modified 30 31 32 35 36 Pages Added None Pages Deleted None l
4 ZION NUCLEAR POWER STATION PROPOSED AMENDMENT Pages Modified 30 31 32 35 36 Pages Added None Pages Deleted None l
l l
l l
t 15180                                       1
t 15180 1
,}}
,}}

Latest revision as of 02:54, 2 December 2024

Application for Amend to Licenses DPR-39 & DPR-48,revising Tech Spec by Adding & Clarifying Tables 3.1-1 & 4.1-1 to Address Operability & Surveillance Requirements for Reactor Protection Channels
ML20245D592
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 04/17/1989
From: Trzyna G
COMMONWEALTH EDISON CO.
To:
Office of Nuclear Reactor Regulation
Shared Package
ML20245D596 List:
References
GL-83-28, NUDOCS 8905010066
Download: ML20245D592 (4)


Text

__ _

L 9 Zion Gin: rating Station C:mm:nwn:lth Edis:n 101 Shiloh Blvd.

Zion, Illinois 60099 Telephone 312/746-2084 Apri1 17, 1989 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission N

Hall Station P1-137 Hashington, D.C. 20555

Subject:

Zion Nuclear Power Station, Units 1 and 2 License Nos. DPR-39 and DPR-48 i

NRC Docket Nos. 50-295 and 50-304 Proposed Amendment to Technical Specification Sections 3.1 and 4.1. "Rgartor Protection System" i

Gentlemen:

Attached is a proposed Technical Specification amendment for Zion Nuclear Power Station, License Nos. DPR-39 and DPR-48.

The proposed amendment addresses Sections 3.1 and 4.1 " Reactor Protection System".

The purpose of this revision is to demonstrate compliance with NRC Generic Letter 85-09, entitled " Technical Specifications for Generic Letter 83-28, Item 4.3".

The proposed Technical Specification change involves additions and clarifications to Tables 3.1-1 and 4.1-1 to address operability and surveillance requirements for Reactor Protection Channels.

Specifically, this

. proposed amendment will change and/or clarify the operability and surveillance requirements for the following functions:

1) Manual Reactor Trip; 2)

Automatic Reactor Trip Logic; and 3) Reactor Trip and Bypass Breakers.

A summary of the changes is provided below.

1)

Iahle13-L_page_30 Line_3 The line is changed to correct a spelling error.

l 2)

Jable 3.1-1. pAgas_3L3nd_32 dine _2. Land _ explanation of ED _fontaole The description of the Reactor Protection Channel has been changed from " Automatic Reactor Trip Logic" to " Automatic Reactor Trip Logic, Including Reactor Trip Breakers".

The change reflects the request of NRR technical reviewers regarding reactor trip logic, and is closely patterned after similar requirements in effect at Ginna.

The (#)

footnote has been added to clarify the appropriate action if one of l

the diverse trip features is inoperable.

This footnote is worded in

(

accordance with Generic Letter 85-09.

3) lable_4J-1mpage_35mLtne 1 A note has been added to the " Remarks" column of Line 1 to address OPERABILITY of the undervoltage and shunt trip circuits, of the reactor trip breakers in addition to the OPERABILITY requirement of l

the reactor bypass breaker circuit.

These remarks closely parallel the guidance contained in Generic Letter 85-09.

8905010066 890417 PDR ADOCK 05000295 (j

P PNU 15 80 f

I

l

d

=

,4 l

4 )'. 'Jable 4.1-1. Dage 36. Lines 21'. 22 and 23 a)

Line.21 has been revised to add Remark No. 11 which requires testing of automatic reactor trip-logic of each train on alternate. months.

The requirements of the Remark'are patterned after Generic Letter 85-09 and; include the recommendations of 1

NRC Staff personnel.who ' suggested that a similarity to Ginna requirements would be appropriate.

b)-

Line 22 is an addition to the Table which specifies the Channel Functional Test requirements for the Reactor Trip Breakers.

The comments contained in.the Remarks column closely conform _to Generic Letter 85-09.

c)

Line 23 is an addition to the Table which specifies the Channel Functional Test requirements for the Reactor Trip Bypass Breakers.

The comments contained in the Remarks column closely j

conform to Generic Letter 85-09. cantains.the revised pages of the Technical Specifications. contains-the evaluation of significant hazards review.

As provided by 10 CFR50.91, the State of Illinois is being notified of-

{

this amendment request by transmittal of this letter and attachments.

Please direct any. questions that you may have to this office.

i l

Ver truly yours,

/

i G. E. Trzyn Nuclear Licensing

{

Administrator Zion Station

)

i cc: Chandu Patel - NRR NRC Resident Inspector - Zion M. C. Parker - IDNS I

l 15180' u____._____-.__.

i

1 l

l 1

ATTACHMENT 1 1

. ZION NUCLEAR POWER STATION EROPOSED AMENDliENT.TO

)

IECHNICAL SPECIFICATION l

SECTIONS 3.1 AND 4.1 I

l i

1 1

l 1

I 15180 t

i E __. _ _. _ _ _ _ _. _ _ _

4 ZION NUCLEAR POWER STATION PROPOSED AMENDMENT Pages Modified 30 31 32 35 36 Pages Added None Pages Deleted None l

l l

t 15180 1

,