ML20033C480
| ML20033C480 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/25/1981 |
| From: | METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML20033C475 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8112030301 | |
| Download: ML20033C480 (39) | |
Text
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s TABLE OF CONTENTS
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Section Pace 6
ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6-1 6.2 ORGANIZAT10N 1 6.2.1 CORPORATE 6-1 6.2.2 UNIT STAFF 6-1 6.3 UNIT STAFF OVALIFICATIONS 6-3 6./
TRAINING 6-3 6.5 REVIEW AND AUDIT 6-3
- 6. 5.1 TECHNICAL REVIEW AND CONTROL 6-4 6.5.2 INDEPENDENT SAFETY PIVIEW 6-5 6.5.3 AUDITS 6-7 6.5.4 INDEPENDENT 04 SITE SAFETY REVIEW GROUP 6-8 i
6.6 REPORTr.BLE OCCURRENCE ACTION 6-10 6.7 OCCURRENCES INVOLVING A SAFETY LIMIT VIOLATION 6 ' *-
6.8 PROCEDURES 6-11 6.9 REPORTING REQUIREMENTS 6-12 6.9.1 ROUTINE REPORTS 6-12 6.9.2 REPORTABLE OCCURRENCES 6-13 6.9.3 UNIQUE REPORTING REQUIREAENTS 6-16 6.9.4 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6-17 6.9.5 SEMI-ANNUAL RADICACTIVE EFFLUENT RELEASE REPORT 6-18 6.10 RECORD RETENTION 6-19 6.11 RAD 1AT10N PROTECT 10N PROGRAM 6-21 6.12 HIGH RADIATION AREA 6-21 6.13 PROCESS CONTROL ~73 GRAM 6-21 6.14 0:FSITE DOSE CALCULATION MANUAL (ODCM)-
6-22 6.15 ENV IRONMENTAL QUALF ICAT ION 6-22 l
6.16 IODINE MONITORING PROGRAM 6-22 6.17 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS 6-23 l
0112030301 811125 DR ADOCK 0500029y
- ^ - - -
tIat FIGURES 3.5-2F Deleted LOCA Limited Maximu= Allowable 3.5-2G Linear Heat Rate DfI-1 A"SR Position Limits of Operatie-r
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- '3 5-2H from 0 ETPD to EOC Incore Instrumentation Specificatic-0.5-3 TMI-1 6-1 Organization Chart GPU Nuclear Corporation TMI-l Onsite Organization 6-2 O
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6.1 RESPONSIBILITY 6.1.1 The Vice President - TMI-l shall be responsible for unit operations and may, at any time, delegate his responsibilities in uriting to the Operations and Maintenance Director, TMI-1.
He shall delegate the succession of his responsibilities in writing during his absence.
6.1.2 The Shift Supervisor (or during his absence from the Control Room, a cesignated individual), shall be responsible for the Control Room command function.
A management directive to this effect signed by the Presicent - GDUNO shall be reissued to all unit personnel on en ennual basis.
6.2 OR3ANi2AT10N CODD0DATE I
6.2.1 Ine organication of the GDU Nuclear Corporation (GDUNC) fo manage-nent and technical support shall be functionelly as shown in Figure 6-1.
UNIT STAD:
6.2.2 Ine organization within the unit for management, operations, tecnnical support, and maintenance shall be functionally as snown in Figure 6-2.
I
- a. Each on-duty sh i ft shal l be composed of at least the minimum shi f t crew composition shown in Table 6.2-1.
O.
AT least one license: Reactor Operato shall be present in tne control room.'nen tuel is in tne reactor.
- c. A-least two licensec Reactor Operators shall be present in tne control roor du-ing reactor startup, scheculec reactor snutco,n anc curing recovery from eactor trips.
- c. Tne Shift Supervisor or Shift Foreman # shall be in ine control room at all times other than colc snutcown concitions CT ave age 4 200* F) when he snell ce onsite.
e.
An incivicuei=F cualifiec pur,uanT tc 6.3.2 in raciation pro-TecTion D ocecures snall be on site anen fuel is in the reactor.
f.
A licensec Senior Reactor Operato with no otne concurrerT cpe a'ional cuties snali cirectly supervise:
(a) irradiated fuel nancling and transfer activities onsite, anc (b) all unirraciated fuel handling and transf er activitiec to and from the Reactor Vessel.
cit ncT SR^ licensec, ne snalt have complete: the SR; Training Program.
Fe Tne incivicual of item 6.2.2e and tne Fire E-igace composition may De less inan the minimum recuirements for e pe-ic of time not to exceec 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in orce-To accommocate unexpectec cosence proviced immeciate action is taken to fill the recuirec positions.
6-1
l TABLE 6.2-1 1
MINIMUM SHIFT CREW COMPOSITION ***
I 4
LICENSE CATE(,ORY QUALIFICATIONS Tave > 2000 Tave f 2000
)
SRO 1
1*
i RO 3
1 Non-Licensed Auxiliary Operator 2
1 Shift Technical Advisor 1**
None Required
- Does not include che Licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervising (a) irradiated fuel handling and transfer activities onsite, and (b) all unirradiated fuel handling and transfer activities to and from the Reactor Vessel.
- May be on a different shift rotation than licensed personnel.
- Shift crew composition may be one less than the minimum requirements for i
a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accocenodate unexpected absence of on-duty shif t crew members provided i= mediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.
This provision does not permit any shift crew position to be unmanned upon shift change due to an incoming shift crewman being late or absent.
i 6-2 i
i l
- g. A Sito Fire Brigadc## of at least 5 members shall bn main-tained onsite at all times. The Site Fire Brigada shall not include members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency,
- h. The Shift T.
.ical Advisor shall serve in an advisory capa-city to the.1ift Supervisor on matters pertaining to the engineering aspsats assuring safe operation of the unit.
6.3 UNIT STAFF 0"',
ilCATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI-N 18.1 of 1978 for comparable positions unless otherwise noted in the Technical Specificatons. Licensed operators shall meet the supplemental requirements specified in Sections A ar;d C of enclosure 1 of the March 28, 1980 NRC letter to al l licensees.
individuals who do not meet ANSI 18.1-1978 Section 4.5 are not considered technicians or maintenance personnel for purposes of determining qualifications bJt are permitted to perform work f or which qualification has been demonstrated.
6.3.2 The Manager-Radiological Controls or the Deputy shall meet or exceed the qualifications of Regulatory Guide 1.8 of 1977.
Each Radiological Controls Technician / Foreman shall meet or exceed the qualifications of ANSI 18.1-1971, paragraph 4.5.2/
4.3.2 or be formally qualified through an NRC approved TMI-1 Radiation Controls training program. All Radiological Controls Technicians will be qualified through training and examination in each area or specific task related to their rad *ological controls functions prior to their performance of those tasks.
6.3.3 The Shift Technical Advisors shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in unit design, response and analysis of transients and accidents.
I 6.4.
TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager Plant Training - TMl-1 and shall meet or exceed the requirements and recommendations of Regulatory Guide 1.8 of 1977 and Appendix "A" of 10CFR Part 55 except that Radiological Controls training may be under the direction of the Vice President - Radiological and Environmenatl~ Controls.
Licensed operators shall meet the supplemental requirement specified in Section A and C of Enclosure 1 of the March 25, 1980 NRC: letter to all licensees.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Manager Plant Training - TMI-1 and shall meet or exceed the requirements of Section 27 of the NFPA Code - 1976.
6.5 REVIEW AND AUDIT, 6.5.1 TECHNICAL REVIEW AND CONTROL 6-3
' ~ ~
The Vice President of cach division within GPU Nuclear Corporation as. indicated in Figure 6-1, shall be responsible for ensuring the preparation, review, and approval of documents required by the activities described in 6.5.1.1 through 6.5.1.5 within his f unc-tional area of responsibility as assigned in the GPUN Review and Approval Matrix.
Implementing approvals shall be per*ormed at the cognizant manager level or above.
ACTIVITIES 6.5.1.1 Each procedure required by Technical Specification 6.8 and other procedures including those for tests and experiments which are important to safety, and changes thereto which are important to safety, shall be prepared by a designated individual (s)/ group knowledgeable in the area affected by the procedure. Each such procedure, and change thereto, shall be reviewed for adequacy by an individual (s)/ group other than the preparer, but who may be from the same organization as the individual who pr epared the procedure,and change thereto, shall be reviewed by an individual (s)/
group other than the preparer, but who may be from the same division as the individual who prepared the proccdure or change.
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.l.3 Proposed modifications to unit structures, systems and compor<ents important to safety shall be designed by an individual / organization knowledgeable in the areas affected by the proposed mod'fication.
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 are important to 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 eval-ation and recommendations to p. event 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 sha.ll be reviewed by an individual / group other than the indivi-dual group which prepared the report.
6.5.1.7 Special reviews, investigations or analyses and reports thereon as requested by the Vice President TMI-1 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)/
6-4
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group which prepared them.'_
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1-6.9.1.9 The Emergency Plan.and:Implenienting procedures shall be reviewed
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- ~by a knowledgeable Individual (s)/ group other than tne it.dividual(s)/
Mg group whIch preparedQhem.gf
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- __ _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, recommendations and disposition of the corrective action to prevent recur-rence to the Vice President TMi-1. shall be reviewed by a knowledgeable individual (s)/ group.
6.5.1.11 Major changes to redweste systems shall be reviewed by a knowledgeable individuals (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 er not additional cross-discip linary review is necessary.
It deemed necessary, such revie. shall be performed by the appropriate personnel.
Individuals responsible for reviews considered under 6.5.1.1 througn 6.5.1.5 shall render determinzTions in writine w iTh regarc to whether or not 6.5.1.1 through 6.5.1.5 constitul a an unreviewed safety question.
RECORDS 6.5.1.13 Written recorcs of activities performec under specif ications 6.5.1.1 through 6.5.1.11 shall be maintainec.
QUALIFICATIONS
. 6.5.1.14 Responsible Technical Reviewers shall meet or exceed the qualifications of_ ANSI _N 18.1-1978.Section 4.6, or 4.4 for applicable disciplines.
Responsible Technical Reviewers shall be designated in writing.
6.5.2 INDEPENDENT SAFETY REVIEW FUNCTIOR 6.5.2.1 The Vice President of each. division within GPU Nuclear Corporation as indicated in Figure 6-1 shall be responsible for ensuring the periodic incepenaent safety review of the subjects cescribed in 6.5.2.5 within his assigned area of safety revie. responsibility, as assignec in the GPUN Revie and Approval Matrix.
6.5.2.2 Independent saf ety review shall be completed by an individual / group not having direct responsibility for the performance of the activi-ties under review, but who may be from the same functionally cogni-zant organization as the indivicual/ group performing the original work.
6.5.2.3 GPU Nuclear Corporation shal l col lectively have or have access to the experience and competence required to independently review subjects in the following areas:
6-5
a.
Nuclear power plant operations b.
Nuclear engineering c.
Chemistry and radiochemistry d.
Metallurgy e.
Nondestructive testing j
f.
Instrumentation and contrc!
g.
Radiological safety h.
Mechanical engineering
- i. Electrical engineering J.
Adninistrative controls and quality assarance practices k.
Emergency plans and related organization, procedures and j
equipment 1.
Other appropriate fields' associated with the unique characteristics of TMI-i.
'j 6.5.2.4 Consultants may be utilized as determined by the cognizant Vice-I President to provide expert advice.
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 f acility as described h the Safety Analysis Report, of changes in pro-cedures as described in the Safety Analysis Report, and of tests or experiments not described in the Safety Analysis Report, which are canpleted without prior NRC approval uncer tne provisions of 10CFR 50.59(a)(1 ). This review is to verify that such changes, tests or experiments did not i nvolve a change in tne Technical Specifications or an unreviewed safety question as defined in 10CFR 50.59(a)(2). Such reviews neea r.;t to performed prior to implementation.
f
- 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 an unre-viewed safety question as defined in 10CFR 50.59(c). Matters l
o+ this kind shall be reviewed prior to submittal to the NRC.
I i
- c. Proposed changes to Technical Specifications o-license amend-ments related to nuclear saf ety shall be reviewed prior to submittal to the NRC for approval.
- d. Violations, deviations, and reportable events wnich require reporting to the NRC in writing.
Such reviews are performed af ter the f act. Review of events covered under this subsection snali include results of any investigations mace and the recom-l mendations 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 i n
(
section 6.5.3 and involving safety related functions.
6-6
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i f.'Any otner matters involving safe operation of the nuclear power plant which a reviewer deems appropriate for consideration, or i
which is referred to the independent reviewers.
1 6.5.2.6 QUALIFICATIONS-The independent reviewer (s) shall either have a Bachelor's Degree in Engineering or the Physical Sciences and five (5) years of profes-sional level experience in the area being reviewed or have 9 years of appropriate experience in the field of his speciality. 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 j
6.5.2.7 Reports of reviews encompassed in Section 6.5.2.5 shall be prepared, maintained and transmitted to the cognizant division Vice President.
6.5.3.
AUDITS 6.5.3.1 Audits of unit acitivities shall be performed by the Quality Assurance Department in accordance with the TMI-1 Operational Quality Assurance
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Plan. These audits shall encompass:
a.
Tne conformance of unit operations to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.
b.
The performance, training and qualifications of the entire unit staff at least once per 12 months.
c.
The verif ication of the non conf ormances and corrective actions program to be properly implemented and documented as related to actions taker. to correct deficiencies occurring in unit equipment, structures, systems or methods of opera-tion that af f ect nuclear saf ety at least once per 6 months.
c.
The performance of activities required by the Operational l
Quality Assurance Plan to meet the criteria of Appendix "B",
10 CFR 50, at least once per 24 months.
e.
The Emergency Plan and implementing procedures at least once per 24 months.
j f.
The Security Plan and implementing procedu es at least once per 24 months.
I g.
The Fire Protection Program and implementing procedures at j
least once per 24 months.
b.
The Offsite Dose Calculation Manual and implementing proce-6-7
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dures at-least once per 24 months.
1.
The Process Contro Program and implementing procedures for solidification of radioactive wastes at least once per-24 months.
J.
The performance of activities required by the Quality Assurance Program to meet criteria of Regulatory Guide 4.15, December, 1977 at least once per 12 months.
k.
Any other area of unit operation considered appropriate by the '0SRG or the Of fice of the President-GPUNC.
6.5.3.2 Audits of the following shall be performed under the cognizance of the Vice President - Technical Functions:
a.
An independent fire protection and loss prevention program inspection and audit shall be performed annually utilizing either qualified of fsite licensee personnel or an outside fire protection firm.
b.
An inspection and audit of the fire protection and loss prevention program, by an outside qualified fire consultant at intervals no greater than 3 years.
RECORDS 6.5.3.3 Audit reports encompassed by sections 6.5.3.1 and 6.5.3.2 shall be forwarced for action to the mangement posi' ions responsibie for the areas audited within 60 days after completion of the audit. Upper management shall be informed per the Operation Quality Assurance Plan.
6.5.4 INDEPENDENT ONSITE SAFETY REVIEW GROUP (IOSRG)
FUNCTION 6.5.4.1 The 10SRG shall be a full-time group of engineers, independe t of the unit staff, and located onsite.
ORGANIZATION 6.5.4.2 The 10SRG shall consist of the Safety Review Manager and a minimum staff of 3 members, each 'f whom shall have an academic degree in o
engineering or a physical science field.
6.5.4.3 The 10SRG shall report to the Nuclear Safety Assessment Department Director.
6.5.4.4 The periodic review functions of tne 10SRG shall incluce the fol-lowing on a selective and overview basis:
- 1) Evaluation for technical adequacy and clarity of procedures important to the safe operation of the unit.
l 6-8
- 2) Evaluation of unit operations from a safety perspective.
- 3) Assessment of unit safety programs.
- 4) Assessment of the unit performance regarcing conformance to requirements related to safety.
- 5) Any other matter involving safe operation of the nuclear power plant that the Safety Review Manage-deems appropriate for consideration.
l I
i AUTHORITY 6.5.4.3 The 10SRG snatt have access to the unit anc unit recorcs es necessary to pe-form its evaluetions anc assessments. Sesec on its reviews, tne 10SRG shall provice recommendations to tne management positions responsible for tne a eas reviewec.
6.5.4.6 OUALIFICATIONS The 10SRG engineers shall have a Bachelor's Degree in Engineering or ine Dnyscial Sciences and tnree (3) years of professional level ex-perience in the nuclea power fielc including tecnnical supporting functions or 6 years of appropriate expe-lence.
Crecit towarc experience will be y:ven to advance degrees on a one-To-one basi s up to a maximum of two years.
RECORDS 6.5.4.7 Reports of evaluations anc assessments encompassec in Section 6.5.4.4 shall be prepa ed, approvec, anc transmittec to the Nuclear Safety Assessment Department Directo, division Vice President, and the managemen+ positions responsi0le fo* the areas reviewed.
I 6-9
56.6 REPORTABLE OCCURRENCE ACTION I
6.6.1 The following actions shall be taken in the event of a reportable j
occurrence requiring prompt notification with written follow-up:
a.
Each occurrence shall be reported innediately to the g
cognizant manager and the cognizant division Vice l
President and the Vice President TMi-1.
The func-tionally cognizant division staf f shall prepare a description of the occurrence, the cause of the occurrence and recommendations for appropriate cor-rective action to prevent or minimize the probability of a repetition of the occurrence. Copies of all such reports shall be submitted to the functionally cogni-zant division Vice President and the Vice President TMl-1.
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D.
The Nuclear Regulatory Commission shall be notified in accordance with the requirements of Technical Specification l
6.9.2.A.
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6.6.2 The following actions shall be taken in tne event of a reportable occurrence requiring a thirty-day written report.
a.
Each such occurrence shall be reported promptly to the cogni-zent manager and the cognizant Vice President and the Vice f
President TMI-1.
A written report for 'each occurrence Sall be prepared by the functionally cognizant division staf7 and j
shall include a description of the occurrence, the cause of the occurrence, and appropriate corrective action to prevent or minimize the probability of repetition of the occurrence.
Copies of all such reports shall be submitted to the func-Tionally cognizant division Vice President anc the Vice-President TMI-1.
4 b.
The Nuclear Regulatory Commission shall be notified in ac-cordance with the requirements of Technical Specification
+
4 6.9.2.B.
6.7 OCCURRENCES INVOLVING A SAFETY LIMIT VICLATION 6.7.1 The following actions shall be taken in the event a safety limit is violated:
l a.
The reactor shall be shut down and operation shall not be resumed until authorized by the Nuclear Regulatory Commission.
b.
An immediate report shall be made to the Operations and Maintenance Director, and Vice President TMI-1, and the j
occurrence shall be promptly reported to the Nuclear Regulatory Commission in accordance with Technical Specification 6.9.2.A.
c.
A complete analysis of the circumstances leading up to and resulting from the occurrence shall be prepared by the i
4 6-10
=
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l unit staff. This report shall include analysis of the effects of the occurrence and recommendations concerning operation of the unit and prevention of recurrence. This report shall be submitted to the Operations and Maintenance l
2 Director. and the Vice President TMi-1.
Appropriate analysis of reports will be submitted to the Nuclear Regulatory Commission in accordance with Technical Specification 6.9.2.A.
i 6.8 PROCEDURES
- 6. 6.1 Written procedures important to safety shall be established, imple-nented and maintained covering the items referenced below:
i a.
The applicable procedures recommenced in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.
b.
Surveillance and test activities of equipment important to safety and radioactive waste management of equipment.
c.
Refueling Operations.
d.
Security Plan Implementation, e.
Fire Protection Program lep tementation.
f.
Emergency Plan implementation.
g.
Process Control Program implementation.
h.
Offsite Dose Calculation Manual implementation.
j i.
Quality Assurance Program for ef fluert and environmental monitoring using the guicance in Regulatory Guide 4.15.
6.8.2 Further, each procedure requirec by 6.8.1 above, and changes thereto i
l which a e important to safety, shall be reviewed and approved as described in 6.5.1 prior to implementation and shall be reviewed periodically as set forth in administrative prececures.
6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
a.
Tne intent of the original procecure is not altered; i
b.
The change is approved by two members of GPUNC Management Staff authorized under Section 6.5.1.12 and knowledgeable I
in the area affected by the procedure. For changes which may af f ect the operational status of unit systems or eauip-ment, at least one of these individuals shall be a member of unit management or super /ision holding a Senior Reactor Opera ^or's License on the unit.
I The change is documented, reviewed and approved as described c.
in 6.5.1.1 within 14 days of i=plementation.
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6-11 i
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+.7 6.9 REPORTING REQUIREMENTS in addition to the appliceble reporting requirements of Title 10, Code of F t f er r. : Regulations, the following identified reports shall be submitted to the Director of the Rcgion 1 Of fice of Inspection and Enforcernent unless otherwise noted.
6.9.1 Routine Reports A.
Startuo Recort. A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned.acrease in power level, (3) installation of fuel that has a dif ferent design or has been manuf actured by a dif ferent fuel supplier, and (4) modifications that may have significantly altered the nucle.ar, thermal, or hydraulic performance of the plant.
The report shall address each of the tests identified in tne FSAR and shall in general inc!ude 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 correc-tive actions that were required to obtain satisfactory operation shall also be described.
Any additional specific details required in license conditions cased on other connitments shall be included in this report.
Startup reports shall be submitted within (1) 90 days folio.ing cocpletion af the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
If the Startup Report does not cover all three events (i.e.,
initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplem9ntary reports shall be submitted at least every three months until all three events have been completed.
E.
Annual Recorts. Annual reports covering the activities of the unit as described below during the crevious calendar year shall be submitted on en annual casis shall incluce:
(A single sub-mittal may be made for the station, The submit'al should combine tnose sections that are common to both units at the station.)
1.
A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures and their associated man rem exposure according to work and job functions, (e.g.,
reactor operations and surveil-lance, inservice inspection, routine maintenance, special maintenance (cescribed maintenance), waste processing, and refueling). The dose assignment to various duty functions may be estimates based pocket dos imeter, TLD, or film bedge measurements. Small exposures totalling less than 20% of the individual tctal dose need not be accounted for.
In the aggregate, at least 60% of the total whole body dose received 6-12
from cxternal sources shall be assigned to specific major work functions.
(This tabulation supplements the requirements of Section 20.407 of 10 CFR Part 20.)
2.
The following information on aircraft movements at the Harrisburg International Airport:
- a. The total number of aircraft movements (takeoffs and.
landings) at the Harrisburg international Airport for the previous twelve-month period,
- b. The total number of movements of aircraft larger than 200,000 pounds, based on a current percentage estimate provided by the airport manager or his designee.
3.
The following information from the periodic Leak Reduction Program tests shall be reported:
- a. Results of leakage measurments,
- b. Results of visual inspections, and
- c. Maintenance undertaken as a result of Leskage Reduction Program tests or inspections.
4.
The following information regarding pressurizer power operated relief valve and pressurizer safety valve challenges shall be reported:
- a. Date er.d time of incident,
- b. Description of occurrence, and
- c. Corrective measures taken if incident resulted from an equipment failure.
f C.
Monthly Operatino Reports. Routine reports of operating
[
statistics and shutcown experience shall be submitted on a monthly basis to tne Office of Inpsection and Enforcement, U. S. Nuclear Regulatory Commission, Washington, D. C. with a copy to the Region 1 Office no later than the fifteenth of each month following the calendar month covered by the report.
6.9.2 Reoortable Occurrences Reportetie Occurrences, including corrective actions and measures to prevent recurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of an occurrence, in case of corrected or supplemental reports, reference shall be made to the original report date.
(These reporting require-ments apply only to Appendix A Technical Specifications.)
A.
Promot Notification With Written Follow-Up. Tne types of events listed Delow shall be reported as expeuitiously 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 confirmed by telegraph, mail-gram, telecopy or f acsimile transmission to Director of the appropriate Regional Office, or his cesignate no later than the first working day following the event, with a written 6-13
________A
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follow-up report witnin two weeks. The written follow-up report shall include material to-provide complete explanation, cause of.tle event, the circumstances. surrounding the event, any corrective action, and component _ failure data.
1.
Failure of the reactor protection system or other systems subject to limiting safety system settings to initiate the required protective function by the time a monitored pera-meter reaches the setpoint specified.as the limiting safety system setting in the Technical Specifications or failure to conplete the required protective function.
Note:
Instrument drift discovered as a result of testing need not be reported under this item but may be reportable under items 6.9.2.A.5, 6.9.2.A.6, or 6.9.2.B.1 below.
2.
Operation of the unit or af fected systems when any parameter or operation subject to a limiting condition is less conser-vative than the least conservative aspect of the limiting condition for operation established in the Technical Speci-fications.
Note:
If specified action is taken when a system.is found to be operating between the most conservative and the least conservative aspects of a limiting condition for opera-tion 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 reportabis under item 6.9.2.B.2 below.
3.
Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment.
Note: Leakage of valve packing or gaskets within the limits for identified leakage set forth in the Technical Specifications need not be reported under this item.
4.
Reactivity anomalies involving disagreement with the predicted value of reactivity balance under steady state conditions during power opertaion grete-than or equal to 1% JL k/k; a calculatec reactivity balance indicating a shutdown margin less conservative than specified in the Technical Specifica-tions short term reactivity increases that correspond to a reactor perloc of less than 5 seconcs or, if sub-critical an unplanned reactivity insertion of more than 0.5% & k/k; or occurrence of any unplanned criticality.
5.
Failure or malfunction of one or more components which prevents or could prevent, by itself, the fulfillment of the functional requirements of systems (s) used to cope with i
i accidents analyzed in the FSAR.
6.
Personnel error or procedural inadequacy which prevents or i
f i
6-14
. ~. -
could prevent, by itself, the fulfillment.of the functional-requirements of systems required to cope with accidents analyzed in the FSAR.
i l
Note: For items 6.9.2.A.5 and 6.9.2.A.6 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 6.9.2.B.2 and 6.9.2.B.3.
i 7.
Conditions arising from_ natural or man-made events that,.
as a direct result of the event required plant shutdown.
operation of safety systems, or other protective measures requ: red by Technical Specifications.
8.
Errors discovered in the transient or accident analyses or in the methods used for such analyses as describsd in the FSAR or in the bases for the Technical Specifications that j
have or could have permitted reactor operation in a manner i
less conservative than assumed in the safety analyses.
9.
Performance of structures, systems, or components that requires remedial action or corrective measures to prevent t
operation in a manner less conservative than assumed in the accident analyses in tne'FSAR or Technical Specifications bases; or discovery during plant life of conditions not
?
specifically considered in the FSAR or Technical Specifice-tions that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.
1 i
Note:
This item is intended to provice for reporting of potentially generic problems.
i 10.
Failure or malfunction of the pressurizer power operated relief valve or pressurizer safety valves which prevents or could prevent, by itself, the fulfiiIment of tne functional requirements of system (s) used to cope with accidents analyzed i
in tne FSAR or as specified in the basis of Technical l
Specifications.
I 11.
Offsite releases of radioactive materials in liquid and gaseous effluents which exceed the limits of Technical Specification 3.22.1.1 or 3.22.2.1.
4 i
12.
Exceeding the limits in Technical Specification 3.22.2.6 for the storage of radioactive materials in tne listed tanks.
B.
Thirty Day Written Reports. The reportable occurrences dis-cussed below shall be the subject of written reports to the Director of th appropriate Regional Office within thirty days of occurrence of the event. The written report shall include l
narrative material to provide a complete explanation of tne cause of the event, circumstances surrounding the event, any corrective action, and component failure data.
i 1
6-15 i
I
1.
Reactor protection system or engineered safety feature instruntent settings which are found to be less conservative than those established by the Technical Specifications but which do not prevent the ful fillment of the f unctional requirements of affected systems.
2.
Conditions leading to operation in a degraded mode permi'ted by a limiting condition for operation or plant shutdown required by a limiting condition for operation.
Note:
Routine surveillance testing, instrument calibration, or preventive m6lr.tenance which require system configurations as described in items 6.9.2.B.1 and 6.9.2.B.2 need not be be reported except where tett results themselves reveal a degraded mode as described above.
3.
Observed inadequacies in the implementation of administrative or procedural controis which tr.reaten to cause reduction of degree or redundancy provided in reactor protection systems or engineerec safety feature systems.
4.
Abnormal degradation of systems other than those specified in items 6.9.2.A.3. designed to contain radioactive material resulting from the fission process.
Note:
Sealed sources or calibration sources are not included under this item. Leakage of valve packing or gaskets witnin Tne limits for identified leakage set forth in Tecnnical Specifications neec not be reported uncer this item.
5.
An unplanned offsite release of 1) more than 1 curie of radioactive material in liquid effluents, 2) more than 150 curies of noble gas in gaseous effluents, or 3) more than 0.05 curies of radiciodine in gaseous effluents.
6.
Measured levels of radioactivity in en environmental sampling medium cetermined to exceed the reporting level values of Table 3.23.2 when averaged over any calender quarter sampling period.
6.9.3 Unicue Reportinc Recuirements A.
Special reports shall be submittec to tae D; rector cf tr.a Office of Inspection and enforcement Regioni i Office w;ithin the timc l
period specified for each report. These reports shall be sub-l mitted covering tne activities icentified below:
l Tests Subr.itta l Dates (1) Containment Structural Within 3.:onths after
(
integrity Test - Tendon performance of surveil-Surveillance Program lance program.
6-16 l
l l
(2) Steam Generator Tube Within 3 months after Inspection Program completion of inspection.
(See Section 4.19.5)
(3) Continament integrated Within 6 months after Leak Rate Test completion of test.
(4) Inservice inspection Within 6 months after five Program years of operation.
(5) Radioactive Sealed Source Within 90 days after Leekage Test revealing the completion of Test.
presence of JL 0.005 micro-curies of Removable Contami-nation.
g 6.9.4 ANNUAL RADICLOGICAL ENVIRONMENTAL DPERATING REPORT Note:
- single submittal may be made for the station. The submittal shou;d combine those sections that are common to both units at the station however, f or units with separate radwaste systems, the submittal shall specify the release of radioactive materia l f ran each un it.
6.9.4.1 Routine radiological environmental operating reports covering the operation of the unit during the previous calendar yea shall be submittec prior to May 1 of each year.
6.9.4.2 Tne annua! reciclogical envircr~ ental operating reports shall incluce summ ar i es, interpretations, and an anaiysis of trencs of the results of the radiological environemnial surveillance activities for the report period, including a comparison.ith preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plent operation on the environment. The reports shall also include tne results of the lanc use censuses required by Technical Specifica-tion 3.23.2.
If harmful effects of evidence of irreversible damage are cetected by tne monitoring, the report shall provide an analysis of the proDlem and a planned course of action to elleviate the problem.
The annuai radiological environmental operating re orts shall include summa-ized and tabulatec results in the format of Tne Radiological Assessmen* STP on The REM? Maren 1978 of all radio logicet environ-mental samples taken during the repo-t period.
In the event tnet some results are not available for inclusicn.ith the repo-t, the repor+
shall De submittec noting and explaining tne reasons Tor the missing resu!?s. The missing data shall be submi??ec as soon as possicle in a supplement, y report.
The repo-ts shall also include the fol!o.ing:
a summary description of tne radiological environmental nonito-ing p ogram; a map of all sempting locations keyed to a table giving distences anc directions from one reactor; and the results of licensee parti:ipation in the 6-17
' Intericboratory Comparison Program, required by Technical Specifica-tion 3.23.3.
6.9.5 Semiannual Effluent Release Report Note: A single submittal may be made for the station. The submi+tal should combine those sections that are cor. mon to both units at the station however; f or units with separate radwaste systems, the submittal shall specify the release of radioactive material from each unit.
6.9.5.1 Routine radioactive effluent release reports covering the operations of the unit during the previous 6 months of operation shall be sub-mitted witnin 60 days af ter January 1 and July 1 of each year.
6.9.5.2 The radioactive effluent relesse reports shall inc!ude a summary of the quantities of radioactivce liquid and gases effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21,
" Measuring, Evaluating ano Reporting Radioactivity in Solid wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents f rom Light-Water-Cooled Nuclear Power P lants", Revision 1, June 1974, with data summarized on a quarterly basis follo.ing the format of Appendix 3.tnereof.
Tne radioactive effluent release report to be sutmitted 60 days after January 1 of each year shail include an annual summaly of hourly meteorolog ical cata collected over tne previous year.
This annual summary may De either in the to-m of en hourly-by-nourly listing of wind speed, aind cirection, atmospaeric stability, and precipitetion (if neasurec) on magnetic tape, or in tne form of joint frequency distribution of wind speec, aind direction, and atmospheric stability. Inis same report shall incluce an assessment of the radia-tico coses cue to the radioactive liquid and gaseous ef fluents released from the unit or station during the previous calencer yea.
This same report shall also incluce an assessment of the radiation coses from radioactive liquid and gseous effluents to individuals cue to their activities inside the site bouncery (Figures 5.1-3 anc 5.1-4) during tne report period.
All assumptions used in making these assessments (i.e.,
specific activity exposure time and location) shall De included in these reports. The meteorological conditions con-current w ith the time of release of radioactive materials in caseous effluents (as determined by sampling t equency anc measurement) shall be used for determining the gaseous pathway doses. The assessmen* of radiation coses shall be performed in accordance with tne Offsite Dose Calculation Manual (00CM).
The racioactive effluent release repo-t to be submittec 60 cays after Janua y 1 of each year shall aiso inctuce an assessment of radiation Coses to the likely and most exposec real individua! from reactor releases and othe nearby uranium fuel cycle sources ; including coses from primary effluent pathways and ci ect radiation) for the previous 12 consecutive montns to snow cento mance.itn 40 CFR 190 " Environ-mental Raciation Protec7 ion Standarcs for Nuclear Co er Operation".
Acceptab le methods to calcu lating the cose contr icutions f rom liquic 6-15
and geseous effluents are given in Regulatory Guide 1.109, Rev. 1.
Tne radioactive effluent release reports shall include the following information for each type of solid waste shippec offsite the during report period:
- a. container volume,
- b. total curie quantity (specify whether cetermined by measurement or e +ir. ate),
- c. principal racionuclices (specify whether determined by measurement or estimate),
- d. type of waste (e.g. spent resin compacted dry w asle, evaporator bottoms),
- e. type of container (e.g., LSA, Type A, Type B, Large Quantity) and
- f. solidification agent (e.g., cement, urea formaldehyde).
The racioactive ef f l uent release reports snail include a summary of unplanned releases from tne site to unrestrictec areas of radicactive mate-ials in gaseous anc licuic efflu-enTs on a cue-terly basis.
The radioactive effluent release repcrts snali incluce any changes to the Process Contrcl Program (PCP) made during the reporting perioc.
Any changes To The Offsite Dose Calculation Manual shel1 ce submitted.itn the next Semiannual Radioac-ive Effluent Recort.
6.10 RECORD RETENTION 6.10.1 The following recorcs shall be retained f or at least five years:
- a. Records of normal station operation including po.e-levels and periocs of operation at each powe" level.
- b. Recorcs of principal maintenance activities, inclucing inspec-tion, repairs, substitution, or re;!acemen7 of principal items of eculpment important to safety.
- c. Reco-ds of reportable occurrences.
- d. Recorcs of periodic checks, +ests arc calibrations.
- e. Recorcs of reactor physics tests anc othe special Tests important to safety.
- f. Changes to operating procedures imporTent to safety.
- g. Records of solic radioactive shipmen +s.
6-19
- h. Test results, i'n units of microcuries, for leak tests performed on licensed sealed sources.
- i. Results of annual physical inventory verifying accountability of licensed sources on record.
- j. Control Room Log Book.
- k. Shif t Foreman Log Book.
6.10.2 The following records shall be retainec for *he curation of Operating License DPR-50.
- a. Record and crawing changes re+ aeciing f acility cesign modifications made to systems and equipment descriDed in the Final Safety Analysis Report.
- b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
- c. Routine unit radiation surveys and monitoring reco-ds.
l
- d. Records of radiation exposure history and radiation expcsure status of personnel, including all contracters anc unit visite s who enter radioactive material areas.
- e. Recorcs of racioactive licuid and gaseous wstes release: to the environment, anc records of environmental monitoring surveys,
- f. Records of transient or operational cycles f or those f aci l ity components important to safety for a limitec nunce of transients or cycles as cetined in tne Final Safety Analysis Report.
- g. Records of trair.inc and qual if ication for current memoe s of tne unit staff.
- n. Recorcs of in-service inspections performed pursuant to these Technical Specifications.
- i. Recorcs of Ouality Assurance activities required by tne Operatione!
Quality Assurance Plan.
- j. Recorcs of reviews performed for cnanges made to D ocecures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
- k. Recorcs of reviews by the Indepencen* Onsite Sa'eTy Review Group (previously Plant Operations Revie Committee and General Office Revie. Board minutes).
- i. Records of analyses required by the raciologica! environmental nonito-ing program.
v
/
hr 6-20
m'. Records of +he service lives of cil hycrculic snubDers listed on Table 3.16.1 Irtcluding the cate at which the service life com-mences and associated installation and maintenance records.
- n. Records for Environmentat Qualification which are covered under the provision of paragraph 6.15.
6._11 RADIATION PROTECTION PROGRAM Procedures f or personnei radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and edhered to f or all operations involving personnel raciation exposure.
6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control cevice" or " alarm signal" required by paragraph 20.20:3 (c)(2) of 10 CFR 20:
- a. Eacn High Radiation Area shall be be-ricaded anc conspicuously postec as a High Radiation Area, anc personnel desiring entrance shall obtain a Radiation Acrk Dermi- (R60).
Any individual enter-ing a High Radiation Area shall (a' use a continuously indicating dose rate monitoring device or (b) use a radiation dose rate integ-rating cevice which alarms at a present cose level, or (c) assure that a raciological control tecnnician provices periodic radiation surveillance with a cose rate monitoring instrument.
- b. Any area accessible to pe sonne; where a major po-tion of the body could receive in any one hour a cose in excess of one thousanc mrem snel! De l ockec or guarcec to prevent unauthorized entry.
The keys to these locked berricaces shall be maintained unce-the actinis-trative control of the Radiological Controls Foreman on da*v.
I The Raciation Work Permit is not requirec by Radiological Controls pe sonnel during the perto mance of tneir assigned raciation protection cuties providea tney are following raciological control procedures for entry into High Raciation Areas.
6.13 PROCESS CONTROL PROGRAV (PCP) 6.13.1 The P P shall be approvec by the Com-ission prio-o implementation.
6.13.2 GPU Nuclear Corporation initiatec cnange to the FCP:
1
(
- i. Shall De submitted to tne NRC in ne Semiannua! Racioactive Effluent Release Repo-? for ine cerioc in which the enanges were made. This submit?al shall contain:
a.
sufficiently detailed information to justify tne changes without benefit of adcitione!
c' supplemental informstion; b.
a cetermination tnet the cnanges dic not recuce the overa!!
conformance of the solidifiec.aste product to existing criteria for so:ic wastes; anc 6-21
c.
documeritation that the changes have been reviewed and I
approved pursuant to 5.6.2.
I
- 2. Shall become effective upon review and approval by GPUNC Management.
6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementat'sn.
6.14.2 GPU Nuclear Corporation initiated changes to tne ODCM:
1.
Shall be submitted to the NRC in the Semiannual Radioactive Effluent Release Report for the period in which the Cnanges were made. This submittal shall contain:
a.
sufficiently detailed information to justify the changes without benefit of additional o* Supplemental information; b.
a cetermination that the changes cid not reduce Tne ac-curacy cr reliaDility of dose calculations or setpoint ceterminations; and c.
cocumentation that the changes have been reviewec and approved pursuant to 6.8.2.
2.
Snell become effective upon revie. anc approval cy GOUNC l
Management.
6.15 ENVIRONVENTAL DUALiFICAT10N 1.
By no late-than June 30, 1952 all safety-related electrical equipment in the facility shall be cualified in accordance with the provisions of division c+ Operating Reactors
" Guidelines for Evtluating Environmental Qualification of C! ass IE Electrical Equipment in Operating Reactors" (DDR Guidelines) or, NUREG-0588 " Interim Staf f Position on Environmental Qualification of Safety-Relatec Electrical Eculpment", Decem0er 1979.
Copies of these documents are attached to Order to-Modification of License DOR-50 cated October 24, 1980.
2.
By no late-than December 1, 1950, cocplete and auciticle records must be available anc maintained at a central loce-tion which cescr:be the environmente! oualification methoc used for all safety-relatec electrical equipment in suf-ficient cetail to document the cegree of compliance with the D00 Guidelines or NUREG-058E. Thereafter, such recorcs shoulc be upcated and maintained current as eculpment is replaced, furtner tested, or otherwise furtner cualified.
6.16 IODINE MDNITORING PROGRAV A program whicn will ensure the capacility to accurately determine 6-22
the airborne lodine concentrction in vital creas under cccident c m-citions shall be implemented. This program shall include the fol-lowing:
1.
Training of personnel.
2.
Procedures for monitoring, and 3.
Provisions f or maintenance of sampling and analysis equipment.
6.17 MAJOR CHANGES TO RADIDACTIVE WASTE TREATMENT SYSTEMS 6.17.1 GPU Nuclear Corporation initiated safety related changes to the radioactive waste system (liquid, gaseous and solid):
1.
Shall be reported to the Commission in the Annual Report (Specitication 6.9.1B) for the period in which the evalu-ation was reviewed.
The discussion of each change shall I
contain:
a.
A summary of the evaluation that led to the determina-tion that the char.ge c?uld be made in accordance with 10 CFR 50.59; b.
Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; c.
A detailed description cf the equipment, componen+s and processes involved and the interfaces with other plant systems; c.
An evaluation of the change which shows the predicted releases of radioactive materials in liauid enc gaseous effluents anc/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereia; e.
An 7 valuation of the change which shows the expected maximum exposures to incivicuals in the unrestricted area and to the general popul ation that di f f er from those previously estimated in the license application and amencments thereto; t.
A comparison of the precicted releases of radioactive materials, in liquid and gaseous effluents and in solid weste, to the actual releases for the period prior to when the enanges are to be made; g.
An estimate of the exposure to plant operating personnel es a result of the enange; and h.
Documentation of the fact that the change was reviewed and 6-23
approved.
2.
Shall become effec +.ive upon review and approval in accordance with l
Section 6.5.1.
4 d
6-24
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