ML020580179

Transmittal of Revised Oyster Creek Technical Specification Page 3 (Revision 224), Lep 1 (Revision 224), Lep 4 (Revision 224), Xxiv (Revision 224), TS Appendix a Pages 6-4 & 6-6 (Revision 224)

ML020580179
Person / Time
Site:	Oyster Creek
Issue date:	02/11/2002
From:	Rogers J AmerGen Energy Co
To:	Wolniak D Niagara Mohawk Power Corp, Office of Nuclear Reactor Regulation
References
Download: ML020580179 (7)

Text

Am erGen Telephone No. 609-971-4652 RM Dept.

DOCUMENT TRANSMI'TAL February 11, 2002 To:

D. J. Wolniak

• Copy Serial #164 Niagara Mohawk PLEASE NOTE: IT IS IMPERATIVE THAT YOU NOTIFY RM OF ADDRESS CHANGES!!

FILE INSTRUCTIONS: DESTROY OUTDATED:

OC TECH SPECS AMENDMENT NO: 224 INSERT AND REMOVE PAGES AS PER JOHN ROGERS' COVER LETTER.

FAILURE TO COMPLY WITH REQUIRED ACTION, WITHIN FIVE (5) WORKING DAYS OF THIS REQUEST, COULD RESULT IN A CAP.

REQUIRED ACTION: 1. ADD REVISION TO YOUR CONTROLLED COPIES.

2. DESTROY OUTDATED MATERIAL.

3. RETURN TRANSMITTAL SIGNED AND DATED.

SIGN AND RETURN TO: RECORDS MANAGEMENT, OCAB-1 NAME: DATE:

YOUR SIGNATURE ON THIS FORM INDICATES THAT YOU HAVE FILED THE CURRENT REVISION. THIS SIGNED FORM CAN BE USED FOR AUDITING PURPOSES.

Oyster Creek Nuclear Generating Station Operating License and Technical Specifications Installation Directions Tech Spec Amendment No. 224 Due to the recent NRC approval and docketing of Amendment No. 224, please make the following changes to your copy of the plant Operating License and Technical Specifications:

Operating License Remove Rev Insert Rev Page 3 223 Page 3 224 LEP 1 223 LEP I 224 LEP 4 220 LEP 4 224 XXIV 223 XXIV 224 Technical Specifications Appendix A 0

Remove Rev Insert Rev 6-4 213 6-4 224 6-6 213 6-6 224 Return the acknowledgment sheet documenting the completion of this action to Oyster Creek Records Management within 5 days of receipt of this package.

John Roge Senior Licensing Engineer OYSTER CREEK CONTROLLED DISTRIBUTION d DOCUMENT SERIAL NUMBERR IRMO

(3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source, or special nuclear materials as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear materials without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate such byproduct, source, or special nuclear materials as may be produced by the operation of the facility.

C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter 1 and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level AmerGen Energy Company, LLC is authorized to operate the facility at steady-state power levels not in excess of 1930 megawatts (thermal) (100 percent rated power) in accordance with the conditions specified herein.

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 224, are hereby incorporated in the license. AmerGen Energy Company, LLC shall operate the facility in accordance with the Technical Specifications.

(3) Fire Protection AmerGen Energy Company, LLC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Report dated March 3, 1978, and supplements thereto, subject to the following provision:

Oyster Creek Technical Specifications List of Effective Pages Page Latest Page Latest Number Amendment Number Amendment LEP 1 224 LEP 3 223 LEP 2 222 LEP 4 224 OPERATING LICENSE APPENDIX A - TABLE OF CONTENTS Page Latest Page Latest Number Amendment Number Amendment 1 213 Cover Page 213) 2 213 205 3 222 iii 186 4 217 186 5

6 213 7 213 SECTION 1 - DEFINITIONS Page Latest Page Latest Page Latest Number Amendment Number Amendment Number Amendment 1.0-1 178 1.0-4 211 1.0-7 213 1.0-2 196 1.0-5 186 1.0-8 212 1.0-3 211 1.0-6 213 SECTION 2 - SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS Page Latest Page Latest Page Latest Number Amendment Number Amendment Number Amendment 2.1-1 218 2.3-1 208 2.3-5 211 2.1-2 192 2.3-2 208 2.3-6 211 2.1-3 192 2.3-3 208 2.3-7 211 2.2-1 75 2.3-4 211 2.3-8 211

- LEP 1 -

Latest: 224

Record of Changes (cont'd)

Page XXIV Amendment 210 June 26, 2000 Changes to Surveillance Frequencies Amendment 211 July 17, 2000 Changes to enhance clarity Amendment 212 August 7, 2000 Change to allow Three Loop Operation Amendment 213 August 8, 2000 Transfer of License to AmerGen Amendment 214 August 21, 2000 Deletion of shutdown requirement From the EMRV acoustic monitors Amendment 215 September 15, 2000 Increases the number of spent fuel assemblies in the Spent Fuel Pool Amendment 216 October 25, 2000 Increases the Excess Flow Check Valve Surveillance Interval Amendment 217 November 2, 2000 Revises the Reporting Requirement For the Core Spray Sparger Amendment 218 November 3, 2000 Establishes the MCPR Limit for Cycle 18 &

Amendment 219 January 24, 2001 Change to SGTS charcoal testing Standard Amendment 220 April 27, 2001 Shift Staffing and STA Role Amendment 221 July 17, 2001 Change to MSIV full stroke test Requirements Amendment 222 December 27, 2001 Change to Off Site Power Supplies Amendment 223 January 23, 2002 Removal of Restrictions on Heavy Loads over Spent Fuel Amendment 224 January 28, 2002 Revision to Section 6 Required by a Revision to 50.59

6.5.1.2 Proposed changes to the Appendix "A" Technical Specifications shall be reviewed by a knowledgeable individual(s)/group other than the individual(s)/group who prepared the change.

6.5.1.3 Proposed modifications, that affect nuclear safety, to facility structures, systems and components shall be designed by an individual/organization knowledgeable in the areas affected by the proposed modification. Each such modification shall be reviewed by an individual/group other than the individual/group which designed the modification but may be from the same division as the individual who designed the modification.

6.5.1.4 Proposed tests and experiments that affect nuclear safety shall be reviewed by a knowledgeable individual(s)/group other than the preparer but who-may-be from the same division as the individual who prepared the tests and experiments.

6.5.1.5 Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence, shall be reviewed by a knowledgeable individual(s)/group other than the individual/group which performed the investigation.

6.5.1.6 Events requiring 24-hour written notification to the Commission shall be reviewed by an individual/group other than the individual/group which prepared the report.

6.5.1.7 Special reviews, investigations or analyses and reports thereon as requested by the Vice President - Oyster Creek shall be performed by a knowledgeable individual(s)/group.

6.5.1.8 The Security Plan and implementing procedures shall be reviewed by a knowledgeable individual(s)/group other than the individual(s)/group which prepared them.

6.5.1.9 The Emergency Plan and implementing procedures shall be reviewed by a knowledgeable individual(s)/group other than the individual(s)/group which prepared them.

6.5.1.10 Review of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation shall be performed by a knowledgeable individual(s)/group. Recommendations and disposition of the corrective action to prevent recurrence shall be sent to the Vice President - Oyster Creek.

6.5.1.11 Major changes to radwaste systems shall be reviewed by a knowledgeable individual(s)/group other than the individual(s)/group which prepared them.

6.5.1.12 Individuals responsible for reviews performed in accordance with 6.5.1.1 through 6.5.1.4 shall include a determination of whether or not additional cross-disciplinary review is necessary. If deemed necessary, such review shall be performed by the appropriate personnel. Individuals responsible for reviews considered under 6.5.1.1, 6.5.1.3, and 6.5.1.4 shall render determinations in writing with regard to whether or not NRC approval is required pursuant to IOCFR50.59.

OYSTER CREEK 6-4 Amendment No.: 69, 125, 134, 180, 210,213,224

RESPONSIBILITIES 6.5.2.5 The following subjects shall be independently reviewed by the functionally assigned divisions:

a. Written safety evaluations of changes in the facility as described in the Updated Final Safety Analysis Report (USFAR), of changes in procedures as described in the UFSAR, and of tests or experiments not described in the USFAR, which are completed without prior NRC approval under the provisions of IOCFR50.59(c)(1). This review is to verify that such changes, tests or experiments did not involve a change in the Technical Specifications or require NRC approval pursuant to 10CFR50.59. Such reviews need not be performed prior to implementation.

b. Proposed changes in procedures, proposed changes in the facility, or proposed tests or experiments, any of which involves a change in the Technical Specifications or requires NRC approval pursuant to I OCFR50.59.

Matters of this kind shall be reviewed prior to submittal to the NRC.

c. Proposed changes to Technical Specifications or license amendments related to nuclear safety shall be reviewed prior to submittal to the NRC for approval.

d. Violations, deviations, and reportable events which require reporting to the NRC in writing. Such reviews are performed after the fact. Review of events covered under this subsection shall include results of any investigations made and the recommendations resulting from such investigations to prevent or reduce the probability of recurrence of the event.

e. Written summaries of audit reports in the areas specified in section 6.5.3 and involving safety related functions.

f. Any other matters involving safe operations of the nuclear power plant which a reviewer deems appropriate for consideration, or which is referred to the independent reviewers.

QUALIFICATIONS 6.5.2.6 The independent reviewer(s) shall either have a Bachelor's Degree in Engineering or the Physical Sciences and five (5) years of professional level experience in the area being reviewed or have 9 years of appropriate experience in the field of his specialty. An individual performing reviews may possess competence in more than one specialty area. Credit toward experience will be given for advanced degrees on a one-for-one basis up to a maximum of two years.

RECORDS 6.5.2.7 Reports of reviews encompassed in Section 6.5.2.5 shall be prepared, maintained and transmitted to the cognizant Vice President - Oyster Creek.

OYSTER CREEK 6-6 Amendment No.: 69, 134, 203, 210, 213, 224