ML20133G166: Difference between revisions

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| document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE
| document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE
| page count = 5
| page count = 5
| project = TAC:M97466, TAC:M97467
| stage = Other
}}
}}


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==Dear Mr. McCollum:==
==Dear Mr. McCollum:==


4 By letter dated December 12, 1996, you informed the staff of a change to the Catawba Nuclear Station, Units 1 and 2, Technical Specifications (TS) Bases Section 3/4.3.3.1. The change provides clarifying information regarding operation of the radiation monitors for plant operations.            No change to the TS is involved.
4 By {{letter dated|date=December 12, 1996|text=letter dated December 12, 1996}}, you informed the staff of a change to the Catawba Nuclear Station, Units 1 and 2, Technical Specifications (TS) Bases Section 3/4.3.3.1. The change provides clarifying information regarding operation of the radiation monitors for plant operations.            No change to the TS is involved.
As you are aware, the TS Bases are not part of the TS as defined by 10 CFR 50.36. As such, changes to the TS Bases may be made in accordance with the provisions of 10 CFR 50.59. Should the proposed change involve an unreviewed safety question pursuant to 10 CFR 50.59(a)(2), or involve a change to the interpretation of implementation of the TS (i.e., constitute a TS change),
As you are aware, the TS Bases are not part of the TS as defined by 10 CFR 50.36. As such, changes to the TS Bases may be made in accordance with the provisions of 10 CFR 50.59. Should the proposed change involve an unreviewed safety question pursuant to 10 CFR 50.59(a)(2), or involve a change to the interpretation of implementation of the TS (i.e., constitute a TS change),
then the proposed change is to be provided to the staff pursuant to the provisions of 10 CFR 50.59(c) and 10 CFR 50.90 for prior NRC review and approval.
then the proposed change is to be provided to the staff pursuant to the provisions of 10 CFR 50.59(c) and 10 CFR 50.90 for prior NRC review and approval.
Line 58: Line 60:
==Dear Mr. McCollum:==
==Dear Mr. McCollum:==


l By letter dated December 12, 1996, you informed the staff of a change to the Catawba Nuclear Station, Units 1 and 2, Technical Specifications (TS) Bases    l Section 3/4.3.3.1. The change provides clarifying information regarding operation of the radiation monitors for plant operations. No change to the TS is involved.                                                                  l As you are aware, the TS Bases are not part of the TS as defined by 10 CFR 50.36. As such, changes to the TS Bases may be made in accordance with the provisions of 10 CFR 50.59. Should the proposed change involve an unreviewed safety question pursuant to 10 CFR 50.59(a)(2), or involve a change to the interpretation of implementation of the TS (i.e., constitute a TS change),
l By {{letter dated|date=December 12, 1996|text=letter dated December 12, 1996}}, you informed the staff of a change to the Catawba Nuclear Station, Units 1 and 2, Technical Specifications (TS) Bases    l Section 3/4.3.3.1. The change provides clarifying information regarding operation of the radiation monitors for plant operations. No change to the TS is involved.                                                                  l As you are aware, the TS Bases are not part of the TS as defined by 10 CFR 50.36. As such, changes to the TS Bases may be made in accordance with the provisions of 10 CFR 50.59. Should the proposed change involve an unreviewed safety question pursuant to 10 CFR 50.59(a)(2), or involve a change to the interpretation of implementation of the TS (i.e., constitute a TS change),
then the proposed change is to be provided to the staff pursuant to the provisions of 10 CFR 50.59(c) and 10 CFR 50.90 for prior NRC review and approval.
then the proposed change is to be provided to the staff pursuant to the provisions of 10 CFR 50.59(c) and 10 CFR 50.90 for prior NRC review and approval.
For administrative purposes, the revised TS Bases, which you provide to the staff, will ensure that all Catawba TS are updated in a consistent and timely manner. Enclosed is a copy of the revised TS Bases page B 3/4 3-3 for. Catawba Units 1 and 2 that have been dated to correspond to the issue date of this letter.
For administrative purposes, the revised TS Bases, which you provide to the staff, will ensure that all Catawba TS are updated in a consistent and timely manner. Enclosed is a copy of the revised TS Bases page B 3/4 3-3 for. Catawba Units 1 and 2 that have been dated to correspond to the issue date of this letter.

Latest revision as of 00:45, 10 August 2022

Forwards Rev TS Bases Page B 3/4 3-3 for Plant
ML20133G166
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 01/13/1997
From: Tam P
NRC (Affiliation Not Assigned)
To: Mccollum W
DUKE POWER CO.
References
TAC-M97466, TAC-M97467, NUDOCS 9701150195
Download: ML20133G166 (5)


Text

..

January 13, 199'7 # '

Mr. Willian R. McCollum Site Vice President '

t Catawba Nuclear Station Duke Power Company '

4800 Concord Road York, South Carolina 29745-9635

SUBJECT:

CATAWBA NUCLEAR STATION, UNITS 1 AND 2 - DISTRIBUTION OF REVISED TECHNICAL SPECIFICATIONS BASES PAGES (TAC NOS. M97466 AND M97467)

Dear Mr. McCollum:

4 By letter dated December 12, 1996, you informed the staff of a change to the Catawba Nuclear Station, Units 1 and 2, Technical Specifications (TS) Bases Section 3/4.3.3.1. The change provides clarifying information regarding operation of the radiation monitors for plant operations. No change to the TS is involved.

As you are aware, the TS Bases are not part of the TS as defined by 10 CFR 50.36. As such, changes to the TS Bases may be made in accordance with the provisions of 10 CFR 50.59. Should the proposed change involve an unreviewed safety question pursuant to 10 CFR 50.59(a)(2), or involve a change to the interpretation of implementation of the TS (i.e., constitute a TS change),

then the proposed change is to be provided to the staff pursuant to the provisions of 10 CFR 50.59(c) and 10 CFR 50.90 for prior NRC review and approval.

For administrative purposes, the revised TS Bases, which you provide to the staff, will ensure that all Catawba TS are updated in a consistent and timely manner. Enclosed is a copy of the revised TS Bases page B 3/4 3-3 for Catawba Units 1 and 2 that have been dated to correspond to the issue date of this letter.

Sincerely, l Original signed by:

Peter S. Tam, Senior Project Manager Project Directorate 11-2 Division of Reactor Projects - I/II i Office of Nuclear Reactor Regulation Docket Nos. 50-413 and 50-414 DISTRIBUTION Docket File' SVarga'

Enclosure:

Bases Change Pages PUBLIC . '

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PDII-2 RF . HBerkow .. \

cc w/ encl: See next page PTam . LBerry , t \

OGC ACRS RCrlenjak, RII EMerschoff,'RII DOCUMENT NAME: G:\ CATAWBA \ CAT 97466.LTR '

To receive a copy of this document, indicate in the box: "C" - Copy without 4 attachment / enclosure "E" - Copy with attachment / enclosure "N" dad &opy 0FFICE PDII-2/PM PDII-2/LA\l)g N- PDII-ME//

/W

~ '

NAME PTam:cn LBerry, HBerhtiw DATE / /97 / % /97 (C / /97 / / /1)/97-0FFICIAL RECORD COPY 9701150 95 970113 PDR ADOCK 05000413 khh P PDR

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UNITED STATES  !

NUCLEAR REGULATORY COMMISSION f WASHINGTON. D.C. 20666-0001

%,.....,e# January 13, 1997 I Mr. William R. McCollum '

Site Vice President

' Catawba Nuclear Station l l

Duke Power Company 4800 Concord Road York, South Carolina 29745-9635

SUBJECT:

CATAWBA NUCLEAR STATION, UNITS 1 AND 2 - DISTRIBUTION OF REVISED TECHNICAL SPECIFICATIONS BASES PAGES (TAC NOS. M97466 AND M97467) i

Dear Mr. McCollum:

l By letter dated December 12, 1996, you informed the staff of a change to the Catawba Nuclear Station, Units 1 and 2, Technical Specifications (TS) Bases l Section 3/4.3.3.1. The change provides clarifying information regarding operation of the radiation monitors for plant operations. No change to the TS is involved. l As you are aware, the TS Bases are not part of the TS as defined by 10 CFR 50.36. As such, changes to the TS Bases may be made in accordance with the provisions of 10 CFR 50.59. Should the proposed change involve an unreviewed safety question pursuant to 10 CFR 50.59(a)(2), or involve a change to the interpretation of implementation of the TS (i.e., constitute a TS change),

then the proposed change is to be provided to the staff pursuant to the provisions of 10 CFR 50.59(c) and 10 CFR 50.90 for prior NRC review and approval.

For administrative purposes, the revised TS Bases, which you provide to the staff, will ensure that all Catawba TS are updated in a consistent and timely manner. Enclosed is a copy of the revised TS Bases page B 3/4 3-3 for. Catawba Units 1 and 2 that have been dated to correspond to the issue date of this letter.

Sincerely, e f -

w Pete 6. Tam, Senior Project Manager Project Directorate II-2 Divi.sion of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-413 and 50-414

Enclosure:

Bases Change Pages cc w/ encl: See next page

Mr. W. R. McCollum Duke Power Company Catawba Nuclear Station cc:

Mr. M. S. Kitlan North Carolina Electric Membership Regulatory Compliance Manager Corporation Duke Power Company P. O. Box 27306 4800 Concord Road Raleigh, North Carolina 27611 York, South Carolina 29745 Senior Resident Inspector Mr. Paul R. Newton 4830 Concord Road Legal Department (PB05E) York, South Carolina 29745 Duke Power Company 422 South Church Street Regional Administrator, Region II Charlotte, North Carolina 28242-0001 U. S. Nuclear Regulatory Commission 101 Marietta Street, NW. Suite 2900 J. Michael McGarry, III, Esquire Atlanta, Georgia 30323 Winston and Strawn 1400 L Street, NW Max Batavia, Chief Washington, DC 20005 Bureau of Radiological Health South Carolina Department of North Carolina Municipal Power

~~

Health and Environmental Control Agency Number 1 2600 Bull Street 1427 Meadowwood Boulevard Columbia, South Carolina 29201 P. O. Box 29513 Raleigh, North Carolina 27626-0513 Mr. G. A. Copp Licensing - EC050 Mr. Peter R. Harden, IV Duke Power Company Account Sales Manager 526 South Church Street Westinghouse Electric Corporation Charlotte, North Carolina 28242-0001 Power Systems Field Sales P. O. Box 7288 Saluda River Electric Charlotte, North Carolina 28241 P. O. Box 929 Laurens, South Carolina 29360 County Manager of York County York County Courthouse Ms. Karen E. Long York, South Carolina 29745 Assistant Attorney General North Carolina Department of Justice Richard P. Wilson, Esquire P. O. Box 629 Assistant Attorney General Raleigh, North Carolina 27602 South Carolina Attorney General's Office Elaine Wathen, Lead REP Planner P. O. Box 11549 Division of Emergency Management Columbia, South Carolina 29211 116 West Jones Street Raleigh, North Carolina 27603-1335 Piedmont Municipal Power Agency 121 Village Drive Dayne H. Brown, Director Greer, South Carolina 29651 Division of Radiation Protection N.C. Department of Environment, Mr. T. Richard Puryear Health and Natural Resources Owners Group (NCEMC) P. O. Box 27687 Duke Power Company Raleigh, North Carolina 27611-7687 4800 Concord Road  :

York, South Carolina 29745

_ . . _ . _ _ ~ _ _ . _ _ _ _._ __

INSTRUMENTATION BASES REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued)

The Engineered Safety Features Actuation System interlocks perform the following functions:

P-4 Reactor tripped - Actuates Turbine trip, closes main feedwater valves on T , below Setpoint, prevents the opening of the main feedwater ,

valves which were closed by a Safety Injection or High Steam i Generator Water Level signal, allows safety injection block so that components can be reset or tripped. l l

Reactor not tripped - prevents manual block of Safety Injection.

l P-11 Defeats the manual block of Safety Injection actuation on low pres-surizer pressure and low steam line pressure and defeats steam line isolation on r gative steam line pressure rate. Defeats the manual block of the motor-driven auxiliary feedwater pumps on trip of main feedwater pumps and low-low steam generator water level.

P-12 On decreasing reactor coolant loop temperature, P-12 automatically blocks steam dump and allows manual bypass of steam dump block for the cooldown valves only. On increasing reactor coolant loop temper-ature, P-12 automatically defeats the manual bypass of the steam dump block.

P-14 On increasing steam generator level, P-14 automatically trips all feedwater isolation valves, pumps and turbine and inhibits feedwater  ;

control valve modulation.

Surveillances for the Reactor Trip Bypass Breakers are included in respense to the NRC's Generic Letter 85-09, dated May 23, 1985.

3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING FOR PLAhi OPERATIONS The OPERABILITY of the radiation monitoring instrumentation for plant operations ensures that: (1)theassociatedactionwillbeinitiatedwhenthe radiation level monitored by each channel or combination thereof reaches its Setpoint, (2) the specified coincidence logic is maintained, and (3) suffi-cient redundancy is maintained to permit a channel to be out-of-service for testing or maintenance. The radiation monitors for plant operations sense radiation levels in selected plant systems and locations and determine whether or not predetermined limits are being exceeded. The radiation monitors send actuation signals to initiate alarms or automatic isolation action and actuation of Emergency Exhaust or Ventilation Systems. Some of the final actuations are dependent on plant condition in addition to the actuation signals from the radiation monitors.

CATAWBA - UNIT 1 B 3/4 3-3 Revised by NRC Letter dated J@nu@rL 13, 1997

o INSTRUMENTATION l

BASES REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTVATION SYSTEM INSTRUMENTATION (Continued)

The Engineered Safety Features Actuation System interlocks perform the following functions:

P-4 Reactor tripped - Actuates Turbine trip, closes main feedwater valves below Setpoint, prevents the opening of the main feedwater on T 'which were closed by a Safety Injection or High Steam va1Es Generator Water Level signal, allows safety injection block so that components can be reset or tripped.

Reactor not tripped - prevents manual block of Safety Injection.

P-11 Defeats the manual block of Safety Injection actuation on low pres- l surizer pressure and low steam line pressure and defeats steam line isolation on negative steam line pressure rate. Defeats the manual ,

block of the motor-driven auxiliary feedwater pumps on trip of main l feedwater pumps and low-low steam generator water level.

P-12 On decreasing reactor coolant loop temperature, P-12 automatically blocks steam dump and allows manual bypass of steam dump block for the cooldown valves only. On increasing reactor coolant loop temper-ature, P-12 automatically defeats the manual bypass of the steam dump l block. )

l P-14 On increasing steam generator level, P-14 automatically trips all feedwater isolation valves, pumps and turbine and inhibits feedwater control valve modulation.

Surveillances for the Reactor Trip Bypass Breakers are included in response to the NRC's Generic Letter 85-09, dated May 23, 1985.

3/4.3.3 MONITORING INSTRUMENTATION 1

3/4.3.3.1 RADIATION MONITORING FOR PLANT OPERATIONS The OPERABILITY of the radiation monitoring instrumentation for plant operations ensures that: (1) the associated action will be initiated when the radiation level monitored by each channel or combination thereof reaches its Setpoint, (2) the specified coincidence logic is maintained, and (3) suffi-cient redundancy is maintained to pemit a channel to be out-of-service for testing or maintenance. The radiation monitors for plant operations sense radiation levels in selected plant systems and locations and detemine whether or not predetemined limits are being exceeded. The radiation monitors send actuation signals to initiate alams or automatic isolation action and l actuation of Emergency Exhaust or Ventilation Systems. Scme of the final l actuations are dependent on plant condition in addition to the actuation

signals from the radiation monitors.

CATAWBA - UNIT 2 B 3/4 3-3 Revised by NRC Letter i

dated January / 13, 1997 -