ML19326B948
| ML19326B948 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/23/1976 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19326B944 | List: |
| References | |
| NUDOCS 8004180658 | |
| Download: ML19326B948 (20) | |
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l ARKANSAS POWER & LIGIT COWANY DOCKET NO. 50-313 ARKANSAS _ NUCLEAR ONE - UNIT 1 l
AMENDEhT 'IU FACILITY OPERATING LICENSE 1
1 l
Amendment No. 9 License No. DPR-51 1.
ne Nuclear Regulatory Commission (the Commission) has found that:
A.
We application for amendment by Arkansas Power & Light Cospany (the licensee) dated December 10, 1975 (as it relates to reporting requirements), complies with the standards and 4
requirements of the Atomic Energy Act of 1954, as amended 1
(the Act), and the Commission's rules and regulations set '
l forth in 10 CFR Chapter I; B.
H e facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of l
the Conmiission; t
C.
%ere is reasonable assurance (i) that the activities authorized by this amendment can be fonducted without endangering the i
health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations ;
l D.
He issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the i
public; and
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E.
An environmental statement or negative declaration need not I.
be prepared in connection with the issuance of this amendment.
2.
According1ys the license is amended by a change to the Technical l
Specifications as indicated in the attachment to this license l
amend:nent and paragraph 2.c(2) of Facility License No. DPR-51 is hereby amended to read as follows:
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"(2) Technical Specifications i
The Technical Specifications contained in Appendices A l
and B, as revised, are hereby incorporatedliniche j
license. ne licensee shall operate the facility in accordance with the Technical Specifications, as revised."
t 3.
His license amendment becomes effective 60 days from the date of j
its issuance.
FOR THE NUCLEAR REGULATORY COINISSION
~0riginal sic 3*d D7*
I)ennis L ZiO '**"
Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors Attachment; Changes to the Technical Specifications Date of Issuance:
l JAN 2 31976 i
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c ATTACIBfENT TO LICENSE ~ MfENDMENT NO. 9 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Replace existing pages i, ii, 6, 86, 126, 127, 138 and 140 through 146 of the Technical Specifications contained in Appendix A with the attached revised pages bearing the same numbers. The changed areas on the. revised pages are reflected by a marginal -line.
Also, pages S, 12S, 137 and 139 are enclosed as a matter of convenience in updating the Technical Specifi-cations. There are no changes on these pages.
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TABLE OF CONTENTS SECTION TITLE PAGE 1.
DEFINITIO!TS 1
1.1 RATED POWER 1
1.2 REAC"'OR OPERATING CONDITIONS 1
1.3 OPERABLE 2
1.k PROTECTICN INSTRU!2'* ?ATICN LOGIC 2
1.5 INSTRUfG:NTATION SURVEILLANCE 3
1.6 QUADRAffr POWER TILT 4
1.7 REACIOR BUILDING
'4 I
2.
SAFErY LIMITS A :D LIMITING SAFErY SYSTEM SEffINGS 7
2.1 SAFErY LIMITS, REACTOR CCRE 7
2.2 SAFETY LIMITS, REACTOR SYSTEM PRESSURE lo
)
2.3 LIMITING SAFETY SYSTEM SEITINGS, PROTECTIVE INSTRU-MENTATION 11
- 3.
LIMITING CCNDITTONS FOR OPE *ATTON 16 3.1 REACTOR CCOLA::T SYSTE!
16 3.1.1 Operational Cc= enents 16
3.1.2 Prescu-i
- izn. Hez uu and Cooldevn L1=itations 18 3.1.3 Minimum Canditiens for cri-icality 21 4
3.f.k' Reactor Ccolant System Activity 22 3.1.5 Chemistry 25 3.1.6 Leekare 27 3.1.7 Moderator Teneerature Coerricient of Reactivity 30 3.1'. 8 Lov Power Physics Testin Restrictions 31 3.1.9 Control Rod Oceration 32 3.2 MAKEUP AliD CHD1ICAL ADDITION SYSTD'S 34 3.3 IMERGE:!CY C0hE CCOLING, REACTOR SUILDING COOLING, REACTOR BUILDING SPRAY AND PENETRATION 110CM VENTILATION SYSTE S 36 3.k STEAM AND POWER CONVERSICN SYSTEM kO 3.5 INSTRUME:r!ATION SYSTE!S 42 3.5.1 Operational Safety Inr.tru=entation 42 352 Control Rod Graue and Power Distribution Limits k6 3.'5.3 Safety Features Actuation System Setroints 49.
3.5.h In-Core Instru=entation 51 3.6 REACIOR BUILDING 54 3.7 AUXILIARY ELECTRICAL SYSTEM 56 3.8 FUEL IDADING AIID REFUELING 58 3.9 RADI0 ACTIVE DISCHARGE 60 3.10 SECONDARY SYSTnt ACTIVITT 66 3.11 EMERGENCY COOLING POND 66a 3.12 '
.MISCELLWEOUS RADIOACTIVE MATERIALS SOURCES 66b 4.
SURVEILLA?TCE REQUIRE!SNTS 67
-k.1 OPERATIONAL SAFETY ITEMS 67 4.2 REACTOR COOLANT SYSTEM SURVEIIIANCE 76 k.3 REACTOR C00LAlf! SYSTEM INTEGRITY FOLLOWING ENTRY 78 k.k REACTOR BUILDING 79 i
4.k.1 Reactor Building Leakage Test 79 l
l 1
Amendment No. 9
m SECTION nTLE PAGE
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Structural Inter ity 85 k.k.3 Eydreren Purre System 90 k.5 EMERGENCY CCF2 COOLHIG SYSTEd, P2 ACTOR BUILDriG COOLIDG 92 SYSTE4 PERIODIC muaG ARD nm;utATION ROCM VENTILATION SYSTE{
k.5.1 I=errency c:re c:o.ier Ivste=
'92 k.5.2 Resetor Buildine Coelin: Systens 95 k.5.3 Penetrs:1:n ?:e= ten:11n:1en system 98 k.6 AUXILIARI =C'3ICAL SISTEI TESTS 100 h.T REACTOR C05 TROL RCD SYSTEM "ESTS' 102 k.T.1 Control Red Drite Syste 7-
- d
' "asts 102 k.7.2 C:ntro l R:d 2------
veri:its:icn 10k k.8 E!ERGE;CI FEZ 0 WATER PCG TESTEIG 105 k.9 REAC2TETY ANC:4ALIES 106 k.10 r:7IRC :4r:TAL SUR'rEILLA:tCE 107 k.11 CC: COL ROC:4 DERGE:;CY VI:CII.ATIC:{
108 f
k.12 REACCR 3UI~.DE;G PURGE SYS El 110 k.13 D'IR32:CT C00L ::3 PC::D 110a 4.14 RADICACI'IVE !'ATERIALS SCURCES SURVEILLANCE 110b 4.1S AUGI!EiTED INSERVICE INSPECTICN PROGRN4 FOR HIGI ENERGY 110c LINES OUTSIDE OF CONTAINMENT SPECIAL SURVEILLANCE f
4.16 110e j
5.
DESIGir FIATES n1 5.1 SITE in 5.2 REACTOR SUILDE:G H2 5.3 REACTOR nh 5.k Er4 AND SPr;T FUEL STORAGE FAr TtT'm'S E6 6.
ADMINISTRA"IVE CCUTFOLS n7 g.1 RESPCIISIEILI"I n7 o.2 PLANT S"AFF CEGA'!!".ATICH 6.3 quALIFICATI0::S n7 n8 6.k REVIr.1 A:rD AUDIT in 65 ACTIO!! TG 3E TA! GIT IN TEE EVENT OF A REPORTABLE CCCURRENCE DESCRIBED IN TEOCiICAL SPECIFICATION 6.12.3.1127 6.6 ACTION TO BE TM23 IF A SAFETY LDiIT IS EXCEEDED 128 6.7 PLAI;T OPERATING PROCEDURES 3,29 6.8 RADIATION AND FISPIRATORY PROTECTIO'i PROGRAM
- 6. 9.
DERGENCY PLANNEIG 130 136 6.10 UTDUSTRIAL SECURITY PROGRAM 6.n RECORDS RETrITION 137 6.12 PLANT REPORTING req h m 138 ik0 11 Amendment No. 9
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PS. ACTOR BUI1D!3G Reactor buildinE integrity exists when the following conditiions are satisfied:
a.
The equipment hatch is closed and sealed and both doors of the personnel lock and e=ergency lock are closed and sealed, or b.
below.
b.
At least one door on each of the personnel lock and emergency lock is closed and sealed during personnel access or repair.
c.
All non-automatie reactor. building isolation valves and blind flanges are closed as required.
d.
All autc=atic reactor building isolation valves are operable or deactivated in the closed position.
e.
The reactor building leakage detez=ined at the last testing interval satisfies Specification h.h.1 e
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BLANK PAGE
. Amendment No. 9
Should the inspection of one of the wires reveal any significant physical change (pitting or loss of area), additional wires shall be removed from the applicable surveillance tendons and inspected to determine the extent and cause chang'e.
The.
sheathing filler will be sampled and inspected for changes in physical appearance.
4.4.2.2 Inspection Intervals and Reports The inspection intervals, measured from the date of the initial structural test, shall be one year, three years, five years, and every five years thereafter or as
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modified based on experience.
Tendon surveillance may be conducted during reactor operation provided design conditions regarding loss of adjacent tendons are satisfied at all times.
A quantitative analytical report covering results of each inspection shall be submitted (required by Technical Specification 6.12.4) and shall especially address the following conditions, should they develop:
(1)
Broken wires.
(2) The force-time trend line for any tendon, when extrapolated, that extends beyond either the upper or lower bounds of the predicted design band.
(3)
Unexpected changes in tendon conditions or sheathing filler properties.
4.4.2.3 End Anchorage Concrete Surveillance A.
The end anchorages of the surveillance tendons and adjacent concrete surface will be inspected.
D.
The inspection interval will be one-half year and one year after the structural integrity test.
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C.-
1he selected inspection location shall include:
(1) ' Four (4) locations on one buttress (hoop tendon anchorage)
(2)- Two (2) locations on the top of the ring girder
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(vertical tendon anchorage).
(3) One (1) location 'on the ring girder (dome tendon anchorage).
86 Amendment No. 9 e.,
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2.
Either the Chairman or Acting Chairman shall be present.
3 No more than a minority of the quorum s' hall have line responsibility for nuclear unit operation.
e.
Purpose:
- l. - The Safety Review Committee shall conduct a critical examination of design, construction and those aspects of monitoring nuclear unit operation necessary to formu-late an independent evaluation of contemplated actions, and after-the-fact investigations of anomalies.
2.
The Safety Review Committee shall be constituted by a written charter stating:
a.
Subjects within purview of the board.
b.
Pesponsibility and authority.
Mechanisms for convening meetings.
c.
d.
Provisions for use of subgroups.
e.
Authority for access to unit records.
f.
Reporting requirements.
l f.
Authority and Responsibility:
The Safety Review Comnittee shall be advisoiy to'the Senior Vice President, Production, Transmission and Engineering (N6E) and APGL corporate management.
g.
Review and Audit:
The board will verify that: nuclear unit operation is, con-sistent with Company policy, rules, approved operating pro-cedures and license provisions; unusual events are promptly investigated and corrected in a manner which reduces the probability of recurrence of such. events; trends are detect-ed which may not be apparent to a day-to-day observer.
1 The operation of the nuclear unit (s) shall be formally audited on a periodic bases. These audits shall be per-formed no less frequently than semi-annually. Periodic review of the activity shall be performed by the board to assure that such audits are being accomplished in accor-dance with requirements of Technical Specifications.
Such audits shall include verification of conformance with normal, off normal, maintenance and emergency surveillance, test and radiation control procedures sad the Energency and Security Plans. These audits shall be performed in accordance with appropriate written instructions or procedures and 'shall include verification of compliance ith internal rules, -
procedures and regulations and license provisions, perform-i
.ance of the operating staff, and corrective actions following e
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anomalies. Written reports of such audits shall be incor-porated in the records of the board and disseminated to appropriate ce=bers of management, including those having
. responsibility in the area audited. Follow-up action, including re-audit of deficient areas, shall be taken where indicated and the results reported to responsible manage-ment levels on a formal basis.
Subjects for review shall include:
1.
Proposed tests and-experiments, and results thereof, when these ccustitute an unreviewed safety question defined in 10 CFR 50.59 2.
Proposed changes in procedures, equipment, or systens which cay involve an unreviewed safety cuestion as defined in 10 CFR 50.59(a)(2) or changes which are referred by the Plant Superintendent. Also, new procedures which may affect nuclear safety.
3.
Proposed Technical Specification or license changes.
4.
Violations of statutes, regulations, orders, Technical Specifications, license require =ents, or internal pro-cedures or instructicus having safety significance.
5 Significant operating abnor-Nties or deviations from nor # perfer-" ce of unit equi;=ent whose failur'e would affect safe shutdown of the plant.
6.
Reportable occurrences described in Technical Specification 6.12.3.1.
T.
The Energency Plans and procedures.
8.
The Industrial Security Plan and procedures.
9 Environ = ental =enitoring.
- 10. Nuclear safety matters deemed essential to the safe operation of the facility by the Superintendent, the Plant Safety Co==ittee, the I-fanager, Nuclear Services, the Director Power Production, or the Senior Vice President (PTSE).
11.- Reports and meeting minutes of the Plant Safety Committee.
12.
Reports submitted to the NRC and associated responses.
h.
Minutes:
Meeting minutes shall be prepared,' formally approved, retain-ed and promptly distributed to board members and other appropriate =e=bers of =anagement having responsibility in the areas reviewed.
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- 126 -
._ p endment No. 9
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6.5 ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE OCCURRENCE DESCRIBED IN TECHNICAL SPECIFICATION 6.12.3.1 6.5.1 Any reportable occurrence described in Technical Specification 6.12.3.1 shall be reported immediately to the Manager, Nuclear Services, the Director Power Production, and the Senior Vice i
President (PT&E) and promptly reviewed by the Plant Safety Committee.
6.5.2 The Plant Safety Committee shall prepare a separate report for each reportable occurrence described in Technical Spec-ification 6.12.3.1.
This report shall include an evaluation i
of the cause of the occurrence, a record of the corrective action taken, and recommendations for appropriate action to prevent or reduce the probability of a recurrence.
6.5.3 Copies of all such reports shall be submitted to the Super--
intendent for distribution to the Mansger, Nuclear Services, the Director Power Production, the Senior Vice President (PT&E), and to the Chairman of the Safety Review Committee for review and approval of any recommendations.
6.5.4 The Senior Vice President (PT&E) shall report the circum-stances of any reportable occurrence described in Technical Specification 6.12.3.1 to the NRC as specified in Section 6.12, " Plant Reporting Requirements".
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Amendment No. 9
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6.10 INDUSTRIAL SECURITY PROGRAM 6.10.1 An industrial security program shall be maintained throughout the life of the plant in accordance with the provisions of the ANO Industrial Security Plan. Annual review of the Plant Security Plan will be performed.
6.10.2 Investigations of all attempted or actual security infractions shall be conducted by the Superintendent, in cooperation with any Federal, State, or local agencies involved, and a report filed with the Manager, Nuclear Services, the Director Power Production, Senior Vice President (PTSE), and Chairman of the Safety Review Committee.
6.10.3 Industrial Security violations shall be report-d as indicated in Specification 6.12.
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6.11 RECORDS ar.ac.J nCN l
6.11.1 All records and logs relative to the following areas shall be retained for 5' years:
Records of nor=al nuclear unit operation, including power a.
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levels and periods of operation at each power level.
j 3
i b.
Records of principal maintenance activities, incitiding
,j inspection, repair, substitution or replacement of principal. i' items of equip =ent pertaining to nuclear safety.
Records of reportable occurrences described in Technical l
c.
Specification 6.12.3.1.
d.
Records of periodic checks, inspections and calibratio.c3 performed to verify that surveillance requirements are being met.
Records of any special reacter test or experi=ents.
e.
1.
Records of changes c:ade in the Operating Procedures.
g.
Records of rad'ioactive ship =ents.
h.
Test results, in units of microcuries, f6r leak tests perfomed pursuant to Specification 4.14.
i.
Record of annual physical inventory verifying accountability of sources on record.
6.11.2 All records relative to the following areas shall be retained for the life of the plant:
Records and drawing changes reflecting plant design modifi--
a.
cations made to systems and equipment described in the' Final
. Safety Analysis Report.
h.
Records of new and spent fuel inventory, transfers of fuel, and assembly histories.
Records of plant radiation and contamination surveys.
c.
d.
Records of off-site environmental monitoring surveys.
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Records of radiation erpsure of all plant personnel, and e.
others who enter radiation control areas, f.
Records of radioactivity in liquid and gaseous vastes related to the environment.
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t Amendment No. 9
Records of transient or operational cycling for those plant g.
components that have been designed to operate safely for a limited number of transients or operational cycles.
h.
Records of current individual plant staff members indicating qualifications, experience, training a.ed retraining.
1.
Reactor coolant system inservice inspections.
J.
Minutes of meeting of the Safety Review Committee.
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r~s 6.12 REPORTING REQUIREMENTS 6.12.1 In addition to the applicable reporting requirements et Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the Director of the appropriate Regional Office of Inspection and Enforcement unless otherwise noted.
6.12.2 Routine Reports 6.12.2.1 Startup Report A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) mnendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) 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 in general 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.
Startup reports shall be submitted within (1) 90 days following c' mpletion o
of the startup test program, (2) 90 days following resumption or commence-ment of commercial power operation, or (3) 9 months following initial criti-cality, whichever is earliest.
If the Startup Report does not cover all three events (i.e., f.nitial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.
6.12.2.2 Annual Operating Report 3/
Routine operating reports covering the operation of the unit during the previc s calendar year should be submitted prior to March'1 of each year.
The initial report shall be submitted prior to March 1 of the year follow-ing initial criticality.
The annual operating reports made by licensees shall provide a compre-hensive,summ-y of the operating experience gained during the year, even though some repetition of previously reported information may be involved.
References in the an.aal operating report to previously submitted reports shall be clear.
1/ A single submittal may be made for a multiple unit station.
The sub-mittal should combine those sections that are common to all units at the station.
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Amendment No. 9
m Erch annuti operating report shall include:
(a)
A narrative summary of operating experience during the report period relating to safe operation of the facility, including safety-related maintenance not covered in item (b) (5).
(b)
For each outage or forced reduction in power / of over twenty percent 2
of design power level where the reduction extends for. greater than four hours:
(1) the proximate cause gud the system and major component involved (if the outage or forced reduction in power involved equipment malfunction);
(2) a bMef discussion of (or reference to reports of) any report-able occurreaces pertaining to the outage or power reduction; (3) corrective action taken to reduce the probability of recurrence, if appropriate; (4) operatingtimelostasaresultoffthe outage or power reduction (for scheduled or forced outages,- use the generator off-line hours; for forced reduction, in power, use the approximate dura-tion of operation at reduced power);
(5) a description of major safety-related correctivo maintenance performed during the outage or power reduction, including the system and component involved and identification of the criti-cal path activity dictating the length of, the outage or power reduction; and (6) a report of any single release of radioactivity or single radi-
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ation exposure specifically associated with the outage which accounts for more than 10% of the allowable annual values.
(c) A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job functions,4./
e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling.
I/ The tem " forced reduction in power" is normally defined in the electric power industry as the occurrence of a component failure or ocher condition which requires that the load on the unit be reduced for ccrrective action imediately or up to and including the very next weekend.
Note that routine preventive maintenance, surveillance and calibration activities requiring power reductions are not covered by this section.
1/ The term " forced outage" is normally defined in the electric power industry as the occurrence of a component failure or other condition which requires that the unit be removed from service for corrective action immediately or up to and including the very next weekend.
il This tabulation supplements the requirements of 20.407 of 10 CFR part 20.
- 141 -
Amendment No. 9
e P: dose assigument to various duty functions may be estimates based on pccket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be acc1unted 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.
(d)
Indications of failed fuel resulting from irradiated fuel examinations, including eddy current tests, ultrasonic tests, or visual examinations completed during the report period.
6.12.2.3 Monthly Operating Report Routine reports of operating statistics and shutdown experience shall be submitted on a monthly asis to the Director, Office of Management Inform-ation and Program Cor
,1, U.S. Nuclear Regulatory Commission, Washi1gton, D.C.
20555, with a copy to the appropriate Regional Office, by the tenth of each month following the calendar month covered by the report.
6.12.3 Reportable Occurrences Reportable occurrences, including corrective actions and measures to prevent reoccurrence, shall be reported to the NRC as required below.
Supplemental reports may be required to fully describe final resolution of occurrence.
In case of corrected or supplemental reports, a licensee event repcrt shall be completed and reference shall be made to the orig-inal report date.
6.12.3.1 Prompt Notification With Written Followup
'Ihe types of events listed below shall be reported as expeditiously as possible, but within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, by telephone and cenfirmed by telegraph, mailgram, or facsimile transmission to the Director of the appropriate Regional Office, or his designate no later than the first working day following the event, with a written followup report within two weeks. A copy of the confirmation and the written followup report shall also be sent to the Director, Office of Management Information and Program Control, USNRC. The written report shall include, as a minimum, a completed copy of a licensee event report form.
Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.
(a)
Failure of the reactor protection system or other systems subject to limiting safety system settings to initiate the required protective func-tion by the time a monitored parameter reaches the setpoint specified as the limiting safety system setting in the Technical Specifications or j
failure to complete the required protective function.
NOTE:
l Instrument drift discovered as a result of testing need not be reported j
under this item but may be reportable under items (e), (f), or 6.12.3.2(a).
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- 142 -
Amendment No. 9
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(b) Operation of the unit or affected systems when any parameter or operation' subject to a limiting condition is less conservative than the least conservative aspect of the limiting condition for operation established in the Technical Specifications.
NOTE:
If specified action is taken when a system is found to be operating between the most cohservative and the least conservative aspects of a limiting condition for operation listed in the Technical Specifications, the limiting condition for operation is not considered to have been violated and need not be reported under this item, but it may be reportable under item 6.12.3.2(b) below.
(c) Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment.
NOTE:
Leakage of valve packing or gaskets within the li=its for identified leakage set forth in the Technical Specifications need not be reported under this item.
-(d) Reactivity anomalies involving disagreement with the predicted value of reactivity balance under steady state conditions dunng power oper-crion greater than or equal to l'a SK/K; a calculated' reactivity balance indicating a shutdown margin less conservative than specified in the Technical Specifications; short-term reactivity increases that correspond to a reactor period of. less than S seconds or, if suberitical, an un-planned reactivity insertion of more than 0.5% AK/K or occurrence of any unplanned criticality.
(e)
Failure or malfunction of one or more congonents which prevents or could prevent, by itself, the fulfillment of the functional require-ments of system (s) used to cope with accidents analyzed in the FSAR.
(f)
Personnel error or procedural inadequacy which prevents or could pre-vent, by itself, the fulfillment of-the functional require =ents of systems required to cope with accidents analyzed in the FSAR.
NOTE:
For items 6.12.3.1(e) and (f) reduced redundancy that does not result in a loss of system function need not be reported under this section but may be reportable under items 6.12.3.2(b) and (c) below.
(g)
Conditions arising from natural or man-made events that, as a direct result of the event require plant shutdown, operation of safety systems, or other protective measures required by Technical Specifications.
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Amendment No. 9
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(h) Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety. analysis report or in the bases for the Technical Specifications that have or could have permitted reactor operation in a manner less conservative than assured in the analyses.
(i) Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or Technical Specifications bases; or discovery during plant life of conditions not specifically considered in the safety analysis report or Technical Specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.
NOTE:
This item is intended to provide for reporting of potentially generic problems.
6.12.3.2 "Ihirty Day Written Reports The reportable occurrences discussed below shall be the subject of written reports to the Director of the appropriate Regional Office within thirty days of occurrence of the event.
A copy of the written report shall also be sent to the Director, Office of Management of
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Information and Program Control. The written report shall include, as a, minimum, a completed copy of a licensee event report form.
Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.
i (a) which are found to be less conservative than those est Technical Specifications but which do not prevent the fulf'111 ment of the functional requirements of affected systems.
(b)
Conditiens leading to operation in a degraded. mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation.
Note:
i Routine. surveillance testing, instrument calibration, or preventative maintenance which require system configurations as described in items -
(a) and (b) above need not be reported except where test results them-selves reveal a degraded mode as described above.
(c)
.cedural controls which threaten to cause reduction of de redundancy provided in reactor protection systems or engineered safety
. feature systems.
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- 144 -
Amendment No. 9
(d)
Abnormal degradation of systems other than those specified in item 6.12.3.1(c) above designed to contain radioactive material resulting from the fission process.
NarE:
Sealed sources or calibration sources are not included under this item.
Leakage of valve packing or gaskets within the limits for identified leakage set forth in Technical Specifications need not be reported under this item.
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a 6.12.4 Unique Reporting Requirements I
Unique reports cover inspections, tests, and maintenance that are appropriate to assure safe operation of the plant. The frequency and content of these reports are determined on an individual case basis and designated in these Technical Specifications. Unique reports shall be submitted in writing to the Director of-the appro-priate Inspection and Enforcement Regional Office within 90 days of the completion of the tests, inspections, and maintenance.
The subjects of unique reports shall include:
(a) Tendon surveillance.
(Specification 4.4.2)
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Amendment ilo. 9
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