ML20135H792
| ML20135H792 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 09/18/1985 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20135H785 | List: |
| References | |
| NUDOCS 8509240235 | |
| Download: ML20135H792 (13) | |
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l ATTACHMENT I TO JPN-85-69 PROPOSED TECHNICAL SPECIFICATION CHANGES RELATED TO REPORTING REQUIREMENTS PTS-84-04 i
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 DPR-59 8509240235 850919 PDR ADOCK 05000333 P
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'A JAFNPP TABLE OF CONTENTS (cont'd)
- f. age, D.
Emergency Service Water System D.
240 E.
Intake Deicing Heaters E.
242 3.12 Fire Protection Systems 244a 5.0 Design Features 245 5.1 Site 245 5.2 Reactor 245 5.3 Reactor Pressure Vessel 745 5.4 Containment 245 5.5 Fuel Storage 245 5.6 Seismic Design 246 6.0 Administrative Controls 247 6.1 Responsibility 247 6.2 Plant Staff Organization 247 6.3 Plant St'aff Qualifications 248 6.4 Retraining and Replacement Training 248 6.5 Review and Audit 249 6.5.1 Plant Operating Review Committee (PORC) 249 6.5.2 Safety Review Committee (SRC) 250 6.6 Reportable Event Action 253 l
m 6.7 Safety Limit Action 253 6.8 Procedures 253
.6.9 Reporting Requirements 254a 6.10 Record Retention 254h 6.11 Radiation Protection Program 255 6.12 Industrial Security Program 258 6.13 Emergency Plan 258 6.14 Fire Protection Program 258 7.0 References 285 Amendment No. 7, M, M, M, M j
JAFNPP TECHNICAL SPECIFICATIONS 1.0 DEFINTTIONS The succeedins frequently used terms are explicitely defined so that a uniform interpretation of the specifications may be achieved.
A.
Reportable Event - A reportable event shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.
B.
Core Alteration - The act of moving any component in the region above the core support plate, below the upper grid and within the shroud.
Normal control rod movement with the control rod drive hydraulic system is not defined as a core alteration.
Normal movement of in-core instrumentation is not defined as a
core alteration.
Amendment No. #, M 1
Y A
-3 8.
R;visw th9 Emergtncy Plcn cnd irplcmenting proccdurcs cnnually.
9.
Perform special review and/or investigations at the request of the Resident Manager.
- 10. Review of all Reportable Events.
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- 11. Review the Offsite Dose Calculation Manual (ODCM) and implementing procedures at least once per 24 months.
- 12. Review the Process Control Program (PCP) at least once per 24 months.
(F) Authority The PORC shall function to advise the Resident Manager on all matters related to nuclear safety and environmental operations. The PORC shall recommend approval or disapproval to the Resident Manager of those items considered in 6.5 IE (1) through (4) at.d determine if items considered in 6.5 lE (1) through (5) constitute unreviewed safety questions, as defined in 10 CFR 50.59.
In the event of a disagreement between the PORC and the Resident Manager, the Chairman of the SRC and the Executive Vice President-Nuclear Generation, or their designated alternates, shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and written notification provided on the next business day; however, the Resident Manager shall have responsibility for resolution of such disagreement pursuant to Section 6.1.
(G) Records Minutes of all meetings of the PORC shall be recorded and numbered.
Copies will be retained in file. Copies will be forwarded to the Chairman of the SRC and the Executive Vice President-Nuclear Generation.
(H) Procedures Conduct of the PORC and the mechanism for implementation of its responsibilities and authority are defined in the pertinent Administrative Procedures.
6.5.2 SAFETY REVIEW COMMITTEE (SRC)
FUNCTION 6,5.2.1 The SRC shall function to provide independent review and audit of designated activities in the areas of:
a.
Nuclear power plant operations b.
Nuclear engineering c.
Chemistry and radiochemistry d.
Metallurgy e.
Instrumentation and control Amendment No.,MT, X,.95, R 250
s dUORUM 6.5.2.6 A quorum of SRC shall consist of the Chairman or Vice-Chairman and four members, including alternates.
No more than a minority of the quorum shall have a direct line responsibility for the operation of the plant.
REVIEW 6.5.2.7 The SRC shall review:
a.
The safety evaluation for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.
b.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety guestion as defined in Section 50.59, 10 CFR.
c.
Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
d.
Proposed changes to Technical Specifications of this Operating License.
e.
Violations of code, regulations, orders Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
f.
Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.
g.
All Reportable Events.
l h.
All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems or components.
- i. Reports and meetings minutes of the Plant Operating Review Committee.
AUDIT 6.5.2.8 Audits of facility activities shall be performed under the cognizance of the SRC.
These audits shall encompass:
a.
The confermance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once par 12 months.
b.
The performance, training and qualifications of the entire facility staff at least once per 12 months.
Amendment No. JAT, M, M 252
. To CHARTER f
46.5.2.11 Conduct of the committee will be in accordance with a charter approved by the Executive Vice President-Nuclear Generation setting forth the mechanism for implementation of the committee's responsibilities and authority.
6.6 REPORTABLE EVENT ACTION The following actions shall be taken for Reportable Events:
(A) The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and l'
(B) Each Reportable Event shall be reviewed by the PORC, and the results of this review shall be submitted to the SRC and the 42' Executive Vice President - Nuclear Generation.
4 6.7 SAFETY LIMIT VIOLATION 1
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(A) If a safety limit is exceeded, the reactor shall be shut down and reactor operation shall only be resumed in accordance with the 4
provisions of 10 CFR 50.36, (c)-(i).
(B) An immediate report of each safety limit. violation shall be made to the NRC by the Resident. Manager. The Executive Vice President-Nuclear Generation and Chairman of the SRC will be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(C) The PORC shall prepare a complete investigative report of each safety limit violation and include appropriate analysis and evaluation of:
(1) applicable circumstances preceding the occurrence, (2) effects of the occurrence upon facility component systems or structures and (3) corrective action required to prevent j
recurrence. The Resident Manager shall_ forward this report to the Executive Vice President-Nuclear Generation, Chairman of the SRC and the NRC.
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6.8 PROCEDURES (A) Written procedures and administrative policies shall be established, implemented'and maintained that meet or exceed the
. requirements and recoaseendations -of Section 5 " Facility Administrative Fo11cies.and Procedures" of ANSI 18.7-1972 and Appendix A of Regulatory Guide 1.33, November 1972..In addition, j
procedures shall be established, implemented and maintained for the 1-Fire Protection Program sud other programs, as specified in i
Appendix B of the Radiological Effluent Technical Specifications, Section 7.2.
(B). Those procedures affecting. nuclear safety-shall be reviewed by PORC-and approved by the Resident'Nanager prior to implementation.
L(C) : Temporary changes to nuclear related procedures may'be made provided:
'1.
The intent of the original procedure is not altered.
{.
' Amendment-No. M,,40', M, X, M L
.253
.s
- 2. thm changs is approv:d by two membars of ths plcnt ccnessment staff, l
at locst cns of whom holds a Ssnior Racetor Opsretor's licsnse on tha unit affected.
- 3. The charge is documented, reviewed by the PORC and approved by the Resident Manager within 14 days of implementation.
6.9 REPORTING REQUIREM.?NTS (A) ROUTINE REPORTS l
In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.
- 1. STARTUP REPORT a.
A summary report of plant startup and power escalation testing shall be submitted following (1) amendment to the license involving a planned increase in power level, (2) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (3) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.
The report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in-this report.
Amendment No. #, M. M 254-a 1CY T
p f-+'f
'*e#
P-"+
- F
.+:
(A) ROUTINE' REPORTS (C ntinusd)
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- 1. STARTUP REPORT (Continued) b.
Startup Reports shall be submitted within (1) 90 days following completion of the startup test program, or (2) 90 days following resumption or commencement of commercial power operation, or whichever is earliest. If the Start-up Report does not cover both events, i.e.,
completion of startup test program and resumption or commencement of commercial power operation, supplementary reports shall be submitted at least every three months until b(*h events are completed.
- 2. ANNUAL OCCUPATIONAL EXPOSURE TABULATION A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 meem/yr and their associated man rem exposure according to work and' job functions,1/ e.g.,
reactor operations and surveillance, in-service inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty
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functions may be estimates based on pocket dosimeter, TLD, or film badge measuraments. Small exposures totaling less than 20%
of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
- 3. MONTHLY OPERATING REPORT A report providing a narrative summary of facility operating experience, major safety-related maintenance, and other pertinent information, should be submitted no later than the 15th of each month following the calendar month covered to the USNRC Director, Office of Management Information and Program Control.
i 1/ This tabulation supplements the requirements of o 20.407 of 10 CFR Part 20.
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[-
Aneadmeat No. E f
254-b-
(These pages intentionally blank)
Amenda.ent No. M 254-c thru 254-f
(B) SPECIAL REPORTS
- 1. Fifteen copies of the Evaluation Report of the results of the first five years of performance of the non-destructive inspection listed in Table 4.6-1 of Technical Specifications 4.6.F. Structural Integrity, relating to the FitzPatrick in-service inspection program shall be submitted to the NRC, Director of Operating Reactors, within three months of the completion of the fifth year of the program.
- 2. Special reports relating to fire protection equipment and systems shall be submitted to the NRC in accordance with Specifications 3.12.A.l.c 3.12.A.l.d.2, 3.12.B.2, 3.12.C.2 and 3.12.E.2.
6.10 RECORD RETENTION (A) The following records shall be retained for at least five years:
- 1. Records and logs of facility operation covering time intervals at each power level.
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- 2. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.
- 3. All Reportable Events.
- 4. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
- 5. Records of reactor tests and experiments.
- 6. Records of changes made to Operating Procedures.
- 7. Records of radioactive shipments.
- 8. Records of sealed source leak tests and results.
- 9. Records of annual physical inventory of all source material of record.
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1 Amendment No. D(
254-g
ATTACHMENT II TO JPN-85-69 PROPOSED TECHNICAL SPECIFICATION CHANGES RELATED TO REPORTING REOUIREMENTS PTS-84-04
~t 1
h NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT
^
DOCKET NO. 50-333 DPR-59
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Section I - Description of the Chances The proposed changes to the Technical Specifications are shown in Attachment I to the Application for Amendment.
These
, changes occur in the Table of Contents, page 111: Section 1
(" Definitions") page.1; and Section 6 (" Administrative Controls") pages 250, 252, 253, 254-a, 254-b, 254-c, 254-d, 254-e, 254-f and 254-g.
The proposed changes reflect the
(
-requirements of Generic Letter No. 83-43
(" Reporting i
Requirements of 10.CFR 50, Sections 50.72 and 50.73, and Standard Technical Specifications") dated December.19, 1983.
l In the proposed amendment, the following changes are incorporated:
a)
The definition, " Reportable Occurrence", has been i
r.eplaced by the new term, " Reportable Event".
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b)
The~ reporting requirements incorporated into-Section 6 i
(" Administrative Controls") have been modified to agree t
with paragraph (g) of Section 50.'73 which specifically i
states that:
"the requirements contained in this section replace all existing requirements for licensees
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to report ' Reportable Occurrences' as defined in Individual plant Technical Specifications".
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c)
The Table of Contents has been revised to reflect'the above changes.
Section II - Purpose of the Chances i
The purpose of the changes'is t'o make the FitzPatrick Technical Specifications conform with the reporting requirements of'10 l
CFR Part 50, Sections 50.72 and 50.73 as described in Generic F
Letter No. 83-43.
Section III - Impact of the Chances e
l The proposed changes do not change any system or subsystem and I
will'not alter-the conclusions of either the FSAR or SER accident analyses.
The Authority considers that the proposed changes can be classified as not likely to involve significant hazards l
considerations since the proposed changes constitute "a change-
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-to make a license conform to changes in the regulations, where the license change results in very minor changes to facility operations. clearly in keeping with the. regulations" (Example (vii), Federal Register, Vol. _ 48, No. 67. dated April 6,
- 1983, page 14870).
Section IV - Implementation of the Chances Implementation of.the changes, as proposed, will not impact the ALARA or fire protection programs at FitzPatrick,'nor will the changes impact the environment.
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a Section V ' Conclusion The incorporation of these changes:
a)
Will not change the probability nor the consequences of an accident or malfunction of equipment important to safety as previously evaluated in the Safety Analysis Report; b)
Will not increase the possibility of an' accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report; c)
Will not reduce the margin of safety as defined in the basis for any Technical Specificationr.;
i d)
Does not constitute an unreviewed safety question as defined in 10 CFR 50.59: and s
e)
Involves no significant hazards considerations, as defined in 10 CPR 50.92.
4 Section VI - References 1)
James A. FitzPatrick Nuclear Power Plant Final Safety Analysis Report (FSAR), Rev 2, July 1984.
2)
James A. FitzPatrick Nuclear Power Plant Safety Evaluation Report (SER).
3)
NRC Generic Letter No. 83-43'" Reporting Requirements of 10 CFR Part 50, Sections 50.72 and 50.73, and Standard Technical Specifications".
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