ML20053B604

Amend 77 to License DPR-50,revising Administrative Controls Section of Tech Specs to Reflect Major Changes in Organization & Internal Safety Review Process

ML20053B604
Person / Time
Site:	Crane
Issue date:	04/28/1982
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Metropolitan Edison Co, Jersey Central Power & Light Co, Pennsylvania Electric Co, GPU Nuclear Corp
Shared Package
ML20053B600	List: ML20053B599 ML20053B604 ML20053B606 ML20053B609
References
DPR-50-A-077 NUDOCS 8206010038
Download: ML20053B604 (31)

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NUCLEAR REGULATORY COMMISSION j

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JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION DOCKET N0. 50-289 s

THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendnent No. 77 License No. DPR-50 1.

The Nuclear Regulatory Conrnission (the Consnis:: ion) has found that:

A.

The application for amendment by Metropolitan Edison Company, et al.

(the licensees), dated April 10, 1981, as supplenented August 13, 1981, and November 25, 1981, complies with the standards and require-ments of the Atomic Energy Act of 1954, as amendpd (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;

B.

The facility will operate in confomity with the application.

the provisions of the Act, and the rules and regulations of the Consnission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Consnission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Coninission's regulations and all applicable mquirements have been satisfied.

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8206010038 820428 PDR ADOCK 05000289 P

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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.c.(2) of Facility Operating License No. DPR-50 is hereby amended to read as follows:

),

(2) Technical Specifications The Technical Specifications contained in Appendices j

A and B, as revised through Amendment No. 77, are hereby incorporated in the license.

The GPU Huclear Corpora-tion shall operate the facility in accordance with t' e h

Technical Specifications.

3.

This license amendment becones effective 4 months after its date of

'tsuance or upon reactor initial criticality following authorization to

. tart, whichever occurs first.

FOR THE NUCLEAR REGULATORY COMMISSI0tl l'

/

i John F. Stolz, Chief Oderating Reactors Branch #4 1 vision of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: April 28,1982 I

ATTACHMENT TP LICENSE AMENDMENT NO. 77 FACII'f( aPERATING LICENSE NO. DPR-50 DOCKET NO. 50-289 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

• Remove Insert v

v viii viii 6 6-27 6 6-24 Fig, 6-1 Fig. 6-2

• Changes on the revised TS pages do not become effective for 4 months after the date of issuance or upon reactor initial criticality following authori-zation to restart, whichever occurs first.

In the interim, the existing TS pages are in effect and should be retained, i

l

TABLE OF C0h7ENTS Section M

5 DESIGN FEATURES 5-1 5.1 SITE 5-1 5.2 CONTAINMENT 5-2 5.2.1 REACTOR BUILDING 5-2 5.2.2 REACIOR BUILDING ISOLATION SYSTEM 5-3 5.3 REACTOR 5-4 5.3.1 REACTOR CORE 5-4 5.3.2 REACTOR C001 ANT SYSTEM 5-4 5.4 NEW AND SPENT FUEL STORAGE FACILITIES 5-6 5.4.1 NEW FUEL STORAGE 5-6 5.4.2 SPENI FUEL STORAGE 5-6 5.)

AIR INTAKE TUNNEL FIRE PROTECTION SYSTEMS 5-8 6-1 6

ADMINISTRATIW CONTROLS 6.1 RESPONSIBILITY 6-1 6.2 ORGANIZATION 6-1 6.2.1 CORPORATE 6-1 6.2.2 UNIT STAFF 6-1 6.3 UNIT STAFF OUALIFICATIONS 6-3 6.4 TRAINING 6-3 6.5 REVIEW AND AUDIT 6-3 6.5.1 TECHNICAL REVIEW AND CONTROL 6-4 6.5.2 INDE?ENDENT SACETY PZVIEW 6-5 6.5.3 AUDITS 6-7 6.5.4 lNCEPENDENT ONSITE SAFETY REVIEW GROUP 6-6 6.6 REPORTABLE OCCURRENCE ACTION 6-10 6.7 OCCURRENCES INVOLVING A SAFETY LIMIT VIOLATION 6-10 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 REQUIREMENTS 6-16 6.9.4 ANNU AL RADIOLOGICAL ENVIRONMENTAL (PERATING, REPORT 6-17 6.9.5 SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6-18 6.10 CICORD RETENTION 6-?9 6.1*

RADIAT10N PROTECT 10N PROGRAM 6-21 6.12 HIGH RADIATION AREA 6-21 6.13 PROCESS CONTROL PROGRAM 6-21 6.14 0:Fi:TE DOSE CALCULATION MANUAL (ODCM) 6-22 6.15 ENVtRONVENTAL QUALIFICATION 6-22 6.16 10 DINE MON!!CRiNG PROGRAM 6-22 6.li MAJOR CHANGES TC R AD IC ACT I VE WASTE TREATNENT SYSTEMS 6-23 Anendnent flo. E, AT, J2', 77 y

LIST OF FIGURES

'rieur, Title i

5-2 Site Topography 5 Mile Radius 5-3 Site Boundary for Caseous Effluents 5-4 Site Boundary for Liquid Ef fluents 6-1 GPU Nuclear Corporation Organization Chart 6-2 21-1 Onsite Organization 1

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Amendment flo. E, 77 viii i

6 ADMINISTRATIVE CONTROLS 6.1 RESPOSSIBILITY 6.1.1 Th2 Vico Pr cid:nt - TMI-1 chc11 be racptnciblo for unit operations and may, at any time, delegate his responsibilities in writing 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 Snitt 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 ef fect signed by tne President - GPUNO shall be reissued to all unit personnel on an annual basis.

6.2 GR3 AN i 2AT I ON Coco 00. ATE 6.2.1 The organization of the GDU Nuclear Corporation (GPUNO) for manage-ment anc technical support shall be functionally as shown in Figure 6-1.

UNIT STAFF 6.2.2 The organization within the unit f or management, operations, technical support, and maintenance shall be functionally as snown in Figure 6-2.

a. ~acn on-duty shi ft shall be composed of at least the minimum shif t crew cocposition shown in Table 6.2-1.

c. AT least one licensec Reactor Operator shall be present in tne control rcom when fuel is in tne reactor.

c. AT least two licensed Reactor Operators shall be presert in Tne control r:cm during reactor startup, seneculee reactor snutcown and c uring recovery from reactor trips.

c. The Shitt Suoervisor or Shif t Foreman # shall be in the control room at all times other than cold shutcown conditions (T everage 4 200* F) wnen he shall ce onsite.

e. An indivicuel## cualifiec pursuant to 6.3.2 in ractation pro-Tection procecures shall be on site wnen fuel is in the reactor.

f. A licensed Senier Reactor Operator.ith no other concurrent cperational c) ties snali direc-ly supervise:

(a), irradiated fuel handling and transfer activities onsite, and (b) al; unieradiated fuel handling and transfer activities to and from the Reactor Vessel.

=l? ncT SR; licensec, ne snell have car.pletec ine SRC Training Drogram.

F# Ihe inCivicual of item 6.2.29 a9c tne Fire E-igace composition may oe less nan the minimum recui ements for a pe-ioc et time nor to exceet 2 nours in orcer TO accommocate unexpacted acsence proviced immeciere action is *aKen To fill the requirec positions.

Amendment No. JY, X,77 6-1.,

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TABLE 6.2-1 MINIMUM SHIFT CREb' COMPOSITION ***

LICENSE CATEGORY Tave) 2000 Tave j; 2000 QUALIFICATIONS SRO 1

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• 1 Non-Licensed Auxiliary Operator 2

1 Shift Technical Advisor 1**

None Required

• Does not include the 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.

• • • Except for.the Shif t Supervisor, shif t crew composition may be one less than the minimum requirements for 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 accommodate unexpected absence of on-duty shif t crew members provided immediate 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 shif t crew position to be unmanned upon shif t change due to an incoming shif t crewman being late or absent.

• • • • Includes the Shift Foreman, who is either SRO licensed or R0 licensed and has completed the SRO training program.

6-2 Amendment No.,R, X, 77

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g. A S'ite Fire Briged:## of at least 5 memosrs shall ba main-tainsd onsito ct all timts. Ths Sito Fire Brigsda shall not include members of the minimum shift crew necessary for saf e shutdown of the unit and any personnel required for other essential functions during a fire emergency.

h. The Shift Technical Advisor shall serve in an advisory caca-city to the Shif t Supervisor on matters pertaining to the engineering aspects assuring safe operation of the unit.

6.3 UNIT STAFF CUALIFICATICNS 6.3.1 Each member of the unit staff shall meet er exceed the minimum qualifications of ANSI /ANS 3.1 of 1978 for comparable positions unless othernise noted in the Technical Specifications. Licensed operators shal l meet the supp lemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees.

Indivicuals who do not meet ANSI /ANS 3.1 of 1978 Section 4.5 are not considered technicians or maintenance personnel for Durpcses of determining cualifications Du? are permitted to perform acrk t er s n ich qual i f ication 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 Tecnnician/ Foreman snail meet or exceed the qual i f ications of ANSI-N 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 radiological 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 ana accicents.

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 reccmmencations of Regulatory Guide 1.8 of 1977 and Apoendix "A" of 10CFR Part 55 except

• hat Radiological Controls training may De uncer the direction of the Vice President - Radiological and Environmental Controls. Licensed operators shall meet the supplemental requirement specified in Section A and C of Enclosure 1 of the March 28, 1980 NRC letter to all. licensees.

5.4 a A training program for the Fire Brigade shall be maintained under the direction of the Manager Plant Training - TMl-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 CCNTROL 6-3 Amendment No. R, R,R, 77

I The Vice President of each division within GPU Nuclear Corporation as Indicated in Figure 6-1, shall be responsible for ensuring the preparation, review, and approval of documents recuired 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 performed 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 saf ety, and changes thereto which are important to safety, shall be preparec by a designated individual (s)/ group knowledgeable in the area affected by the procedure. Each such procedure, and change thereto, shall be reviewed for acequacy by an individual (s)/ group other than the preparer, but who may be from the same organ 12ation as the individual who prepared the procedure 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 tne individual (s) group who prepared the change.

6.*.I.3 Proposec modifications to unit structures, systems and components important to safety shall be designec by an individual / organization Knowledgeable in the areas af f ectec by the proposed modi fication.

Each sucn 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 tne individual wno designed the modification.

6.5.1.4 Proposed tests and experiments thct are important to safety shall be reviewed by a knowledgeable individual (s)/ group other than the prepar " but who may be from the same division as the individual who preparec the tests and experiments.

6.5.1.5 investigation of al l violations of the Technical Specifications including the preparation anc form :rding of reports covering eval-ation anc recommendations to prevent recurrence, shall be reviewed by a knowleageable 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 sh a.l l

• ? reviewed by an individual / group other than tne indivi-dual y cup which prepared the report.

6.5.1.7 Special reviews, investigations or analyses and repcrts thereon as requested by the Vice President TMi-1 shall be performed by a knowledgeable individual (s)/grouc.

6.5.1.S The Security Plan and implementing procedures sneli De reviewed Dy a knowiecgeable incivicual(s)/ group otner tnan tne incivicualis)/

Amendnent No. JFr, 77 6-4

grcup which prepared them.

6.9.1.9 The Emergency Plan and implementing procedures shall be reviewed by a knowledgeable Individual (s)/ group other than the Individual (s)/

3roup whIch prepared them.

6.5.1.10 A knowledgeable individual (s)/ group shall review every unplanned onsite release of radioactive material to the environs including the prepara-tion and forwarding of reports to the Vice President TMI-l covering eval ua tion, recommendations and disposition of the corrective action to prevent recurrence.

6.5.1.11 Major changes to redweste systems shall be reviewed by a knowledgaable 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.

tnrough 6.5.1.4 shall incluce a determination of whether or not acditional cross-discip l inary review is necessary.

It ceemec necessary, such review shall be performed by the appropriate personnel.

Individuals responsible for reviews considered under 6.5.1.1 througn 6.5.1.5 shall rencer determinations in writing with regarc to whether or no? 6.5.1.1 through 6.5.1.5 constitute an unreviewed saf ety cuestion.

RECDRDS 6.5.1.13 nritTen recorcs of activities pertermec under specifications 6.5.1.1 tnrougn 6.5.1.11 shall be maintainea.

QUALIFICATIONS

_ 6.5.1.14 Responsible Technical Reviewers shall meet or exceed the qualifications of ANSI / ANS 3.1 of 1978 Section 4.6, or 4.4 for applicable disciplines, or have 7 years of appropriate experience in the field of his specialty.

Credit toward experience will be given for advanced degrees on a one-l to-one basis up to a maximum of two years. Responsible Technical l

Reviewers shall be designated in writing.

l 6.5.2 INDEPENDENT SAFETY REVIEW F UNO! ! ON_

6.5.2.1 Tne Vice Presicent of eacn. civision witnin GDU Nuclear Lorporation as indicatec in Figure 6-1 shall be responsible for ensuring the periodic incepencent safety review of the subjects cescribed in 6.5.2.5 witnin his assignec area of safety review responsibility, as assignec in the GPUN Review anc Approval Matrix.

safety review shell be completed oy an individual / group 6.5.2.2 I nder e.1 dent l

not having direct responsibility for the performance of tne activi-l ties under review, but who mey be f rom the same functionally cogni-zant organi:ation as tne individual / group performing the original w or k.

6.5.2.3 GPU Nuclear Corporation shall collectively nave or have access to the experience and competence required to independently review sub.iects in the following areas:

Amendment No. JPf, Jdf, 77 6-5

a.

Nuclear power plant operations b.

Nuclear engineering c.

Chemistry and radiochemistry d.

Metallurgy e.

Nondestructive testing f.

Instrumentation and contral g.

Raciological safety h.

Meenanical engineering

i. Electrical engineering J.

Administrative controls anc quality assurance practices k.

Emergency plans and related organization, procedures anc equipment 1.

Other appropriate fields associated with the unique characteristics of TMI-1.

6.5.2.4 Censultants may ce utilizec as cetermined by the cognizant Vice-I Presicent to provide expert aavice.

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

a. Written saf ety evaluations of changes in the f acility as cescribec in the Safety Analysis Report, of changes in pro-cecures as described in the Safety Analysis Re ert, and of tests or experiments not described in the Safety Analysis Report, which are completea without prior NRC approval under tne provisions of 10CFR 50.59(a)(1). This review is to verify tnat sucn changes, tests or experiments dic not involve a change in tne Technical Specifications or an unreviewed safety question as cefined in 100FR 50.59(a)(2). Sucn reviews need not be performed prior to implementation.

D. Proposed changes in procedures, proposed changes in the f acility, 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). Matter s of this kinc snall be reviewec prior to submittal to the NRC.

c. Proposed changes to Technical Specifications or license amenc-ments relatec to nuclear safety shall be reviewec prior to submittel to the NRC for approval.

d. Violations, deviations, anc reportable events wnich require recorting to the NRC in writing. Such reviews are performed af ter the f act.

Review of events covered unce" this subsection shall include results c.

any investigations mace anc the recom-mencations resulting from such investigations o preyent or recuce the procability of recurrence of the even.

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

I Amendment No. J-T, 77 6-6 7

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

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 cf 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 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 activities shall be performed by the Quality Assurance Department in accordance with the TMl-1 Operational Quality Assurance Plan. These audits shall encompass:

The conformance of unit operations to provisions contained s.

within the Technical Specifications and applicable license conditions at least once per 12 months.

b.

The performance, training and quellfications of the entire unit staff at least once per 12 months.

The veri f ication of the non-conformances and corrective c.

actions program to be properly implemented and documented as related to actions taken 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.

d.

The performance of activities required by the Operational Qual ity Assurance P lan to meet the criteria of Appendix "B",

10 CFR 50, at least once per 24 months.

The Emergency Plan and implementing procedures at least once e.

per 24 months.

f.

The Security Plan and implementing procedures at least once per 24 months.

g.

The Fire Protection Program anc implementing procecures at least once per 24 months.

h.

The Offsite Dose Calculation Manual and implementing proce-6-7 Amendment tio.X, 77 m

dures at least once per 24 months.

1.

The Process Control Program and implementing procedares 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 10SRG 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 independant fire protection and loss prevention program inspection and audit shall be performed annually utilizing either quali f ied of f site 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 forwarded for action to the management positions responsible for the areas audited within 60 days after completion of the audit. Upper management shall be informed per the Operation Quality Assurance Picn.

6.5.4 INDECENDENT ONSITE SAFETY REVIEW GROUP (10SRG)

FUNCTION 6.5.4.1 The 10SRG shall be a full-time group of engineers, independent of the unit staff, and located onsite.

ORGANIZATICN 6.5.4.2 The 10SRG shall consist of the Safety Review Manager and a minimum statt of 3 members, each of whom shall have an academic degree in engineering or a physical science field.

6.5.4.3 The 10SRG shal l report to the Nuclear Saf ety Assessment Director.

6.5.4.4 The periodic review functions of the 10SRG shall inclu'ce the foi-lo.ing on a selective and overview basis:

1) Evaluation for technical adequacy and clarity of procedures important to the safe operation of the unit.

I Amendment No. )4',77 6-8

2) Evaluation of unit operations from a safety perspective.

3) Assessment of unit saf ety programs.

4) Assessment of the unit performance regarcing conformance to requirements related to saf ety.

5) Any ciner matter involving saf e operation of the nuclear power plant that the Saf ety Review Manage-deems appropriate i

f or consiceration.

I I

i AUTHORITY 6.5.4.5 The 10SRG shall have access to tne unit anc unit recorcs as necessary to pe-form its evaluations and assessments. Basec on its reviews, tne 10SRG shall provide recommendations to tne management positions responsible for tne areas reviewec.

6.5.4.6 CUALl~lCATIONS Tne 10SRG engineers shall have a Bachelor's Degree in Engineering or tne Dnyscia! Sciences and tnree (3) years of professional level ex-ce-ience in the nuclear power fiele including tecnnical supporting

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functions or 6 years of appropriate expe-lence. Orecit towerc experience will be given for acvance degrees on e one-to-one basis up to a maximum of Two years.

RE DRDS r

6.5.4.7 Reports of evaluations anc assessments encompessec in Section 6.5.4.4 shall be preparec, acprovec, anc transmitTec tc the Nuclear Saf e?y Assessment Director, division Vice President, and the management positions responsible for the arees reviewed.

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l Amendnent flo. Jd', 77 6-9 l

r

616 REP'ORTABLE OCCURRENCE ACTION 6.6.1 The following ccticns sh0Il be takcn in Th3 Gvent of a rcportIblO occurrence requiring prompt notification with written follow-up:

a.

Each occurrence shall be reported innediately to the cognizant manager and the cognizant division Vice 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 TM.-l.

l b.

The Nuclear Regulatory Conmission shall be notified in accordance with the requirements of Technical Specification 6.9.2.A.

6.6.2 The following actions shall be taken in the event of a reportable occurrence requiring a inirty-day written report, a.

Each such occurrence shall be reported pranptly to the cogni-zant manager and the cognizant Vice President and the Vice President TMi-1.

A written report for each occurrence shall be prepared by the functionally cognizant division staff and 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.

b.

The Nuclear Regulatory Commission shall be notified in ac-cordance with the requirements of Technical Specification 6.9.2.B.

6.7 OCCURRENCES INVOLVING A SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a safety limit is violated:

a.

The reactor shall be shut down and operation shall not be resumed ur.tll authorized by the Nuclear Regulatory Commission.

b.

An innediate report shall be maae to the Operations anc Maintenance Director, and Vice President TMI-1, and the-occurrence shall be promptly reported to the Nuclear Regulatory Commission in accorcance with Technical f

Specification 6.9.2.A.

A complete analysis of the circumstances leacing up to and c.

resulting from the occurrence shall be prepared by the Amendment flo. X, 77 6-10

.,e=

unit staf f.

This rcport shall includ3 analysis cf tho offects of the occurrcnca tnd rccomm:ndations c:necrning operation of the unit and prevention of recurrence. This report shall be submitted to the Operations and Maintenance l

Director and the Vice President TMl-1.

Appropriate analysis of reports will be submitted to the Nuclear Regulatory Commission in accordance with Technical Specification 6.9.2.A.

6.8 PROCEDURES 6.8.1 Written procedures important to safety shall be established, imple-mented and maintained covering the items referenced below:

a.

The applicable procedures reconrnended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.

b.

Surveillance and test activities of equipment important to safety and radioactive weste management of equipment.

c.

Refueling Operations.

d.

Security Plan Implementation.

e.

Fire Protection Program implementation.

f.

Emergency Plan implementation.

g.

Process Control Program implementation.

h.

Offsite Dose Calculation Manual implementation.

i.

Quality Assurance Program for ef fluent and environmental monitoring using the guidance in Regulatory Guide 4.15.

6.8.2 Further, each procedure required by 6.8.1 above, and changes thereto which are 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 procecures.

6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

a.

The intent of tne original procedure is not altered; b.

The change is approved by two members of GPUNC Management Staff authorized under Section 6.5.1.12 and knowledgeable l

In the area affected by the procedure. For changes which l

may affect the operational status of unit systems or equip-ment, at least one of these individuals shall be a member of unit management or supervision holding a Senior Reactor Operator's License on the unit.

The change is documented, reviewed and approved as cescribed c.

in 6.5.1.1 within 14 days of i=plementation.

Amendment No..,W, A J 2,77 j_11 y,-s

6.9 REPORTING REQUIREMENTS In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identitled reports shall be submitted to the Adminis tra to r of the NRC Region 1 Office unless otherwise noted.

6.9.1 Routine Reports A.

Startuo Report. 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 increase in power level, (3) installation of fuel that has a different design or has been renufactured 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 identitled in the FSAR and shalI in general include a description of the measured values of the operating conditi as 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 commitments shalI be included in this report.

Startup reports shall be submitted within (1) 90 days following completion of 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), supp{ementery reports shall be submitted at least every three months untiI alI three events have been completed.

I B.

Annual Reports. Annual reports covering the activities of the unit as described below curing the previous calender year shall be submitted prior to March 1 of each year.

(A single sub-l mittal may be made for the station. The submittal should combine those 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 greater than 100 mrem /yr and their associated man rem exposure according to work and job functions, (e.g., reactor operations and surveillance, inservice inspection, routine maintenaace, special maintenance (describe maintenance), waste processing, and refueling).

The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be i

I accounted for.

In the aggregate, at least 80% of the total whole body Jose received from external sources shall be assigned to specific major work functions.

(This tabulation supplements the requirements of Section 20.407 of 10 CFR Part 20.)

6-12 2

Amendment flo. X, X, 77

2.

The following information on aircraft movements at the Harrisburg International Airport:

a. The total number of aircraft movements (takeof fs 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 measurements,

b. Results of visual inspections, and

c. Maintenance undertaken as a result of Leakage 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 and time of incident,

b. Description of occurrence, and

c. Corrective measures taken if incident resulted from an equipment failure.

C.

Monthly Ooeratina Reports. Routine reports of operating statistics and shutcown experience shall be submitted on a monthly basis to the U. S. Nuclear Regulatory Ccmmission at the address specified in R.G. 10.1, no later than the fifteenth of each month following the calendar month covered by the report.

6.9.2 Reoortable Occurrences Reportable 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.

Promet Noti f ication With Written Fol low-Vo.

The types of events listed Delow shall be reported as expecitiously 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 acsimi!e transmission to the Administrator of the NRC Region 1 Of fice, or his designate no later than the first working day following the event, with a written Amendment No. E, X, 77

=

e follow-up rcport within two teeks. Tha eritton follow-up report shall include matcrial to provide complcta cxplcnstion, cause of the 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 para-meter reaches the setpoint specified as the limiting safety system setting in the Technical Specifications or failure to complete the required protective function.

Note:

Instrument drift discovered as a result of testing neec 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 reportable under item 6.9.2.B.2 below.

3.

Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment.

l Note: Leakage of valve packing or gaskets within the limits j

for identified leakage set forth in the Technical j

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 operation greater than or equal to 1% ak/k; a calculated reactivity balance incicating a shutdown margin less conservative than specified in the Technical Specifica-tions; short term reactivity increases that correspond to a reactor period of less than 5 secones or, if sub-critical an unplanned resetivity insertion of more than 0.5%

Ak/k-or occurrence of any unplanned criticality.

5.

Failure or malfunction of one or more components which l

prevents or could prevent, by itself, the fulfillment of the f unctional requirements of systems (s) used to cope with accidents analyzec in the FSAR.

6.

Personnel error or procedural inadequacy wnich prevents or Amendment No. )4', 77 6-14 em I

1 L

=.

could pecycnt, by Itcalf, tha fulfillm:nt of th3 functicnal requirements of systems required to cope with accid nts analyzed in the FSAR.

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 l

reportable under items 6.9.2.B.2 and 6.9.2.B.3.

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 required by Technical Specifications.

6.

Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the FSAR or in the bases for the Technical Specifications that have or could have permitted reactor operation in a manner less conservative than assumed in the safety analyses.

9.

Performance of structures, systems, or components tnat requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the FSAR or Technical Specifications bases; or discovery during plant life of conditions not specifically considered in the FSAR or Technical Specifica-tions 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.

10.

Failure or malfunction of the pressurizer power operated reiief valve or pressurizer safety valves which prevents or could prevent, by itself, the fulfillment of the functional requirements of system (s) used to cope with accidents analyzed in the FSAR or as specified in tne basis of Technical Specifications.

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.

12.

Exceeding the limits in Technical Specification 3.22.2.6 for the storage of radioactive materials in the listed tanks.

B.

Thirty Dey Written Reports. The reportable occurrences dis-cussed below shall be the subject of writ +en reports to the Administrator of the NRC Region 1 Offir.e within thirty days of occurrence of the event. The written reocrt shall include

[

narrative material to provide a complete explanation of the

(

cause of the event, circumstances surrounding the event, any corrective action, and component failure cata.

i Amendment No. E, X, 77 6-15 l

i

1.

Rc ctor pretcetion system or cngin:2rca satcty fc;turo instruntent settings which are found to be less conservative than those established by the Technical Specifications but which do not prevent the fulfillment of the functional requirements of affected systems.

2.

Conditions leading to operation in a degradeo mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation.

Note: Routine surveillance testing, instrument calibration, or preventive maintenance which require system configurations as described in items 6.9.2.B.1 and 6.9.2.B.2 need not be reportec except where test results tnenselves reveal a degraded mode as described above.

3.

Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.

4.

Abnormal degradation of systems other than those specified in item 6.9.2.A.3. designed to contain radioactive material resulting from the fission process.

Note:

Sealec sources or calibration sources are not included uncer this item. Leakage of valve packing or gasnets within the limits for identified leakage set forth in Technical Specifications need not be reported under this item.

5.

An unplanned offsite release of 1) more than 1 curie of radioactive material in liquid effluents, 2) more tnan 150 curies of noble gas in gaseous effluents, or 3) more than 0.05 curies of radiolodine in gaseous effluents.

6.

Measured levels of radioactivity in an environmental sampling medium determined to exceed the reporting level values of Table 3.23-2 when averaged over any calendar quarter sampling period.

6.9.3 Unicue Reportino Recuirements A.

Special reports shall be submitted to the Regional Administrator of the NRC Region 1 Office within the time period.specified for each report. These reports shall be submitted covering the activities identified below:

Tests Submittal Dates (1) Containment Structural Witnin 3 mor.ths after integrity Test - Tencon oerformance of survell-Surveillence Program lance program.

Amendment flo. R, X, 77 6-16

(2) Stccm G:ncrator Tuba tiithin 3 months aftcr inspection Program completion of inspection.

(See Section 4.19.5)

(3) Containment Integrated Within 6 inonths af ter Leak Rate Test '

completion of test.

I (4) Inservice Inspection Within 6 months after five Program years of operation.

(5) Radioactive Sealed Source Within 90 days after Leakage Test revealing the completion of Tett.

presence of.h 0.005 micro-curies of Removable Contami-nation.

6.9.4 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Note: A single submittal may be mace for the station. The submittal should combine those sections that are common to both units at the station however, for units with separate radwaste systems, the submittal shall specify the release of radioactive material from each unit.

5.9.4.1 Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

6.9.4.2 ine annual radiological environmental operating reports shall include summaries, interpretations, and an analysis of trencs of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include tne results of the land use censuses required by Technical Specifica-tion 3.23.2.

If harmful effects of evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

The annual radiological environmental operating recorts shall include summarized and tabulated results in the format of tne Radiological j

l Assessment ST? on the REMP March 1978 of all radiological environ-mental samoles taken during the report period.

In the event that some l

results are not available for inclusion with the report, the report shall De submitted noting anc explaining the reasons for the missing results. The missing data shall be submittec as soon as possiDie in a suoplementary report, r

The reports snall also include the foi!c.ing:

a su r:try description

~

of the radio'ogical environmental monitoring progra?,; a mao of all sam;: ling locations keyed to a table giving dis ances anc directions from one reactor; and tne results of lice 9see parti:i:ation in tne l

Amendnent No. Jdf, S(, M, 77 6-17 l

Intsrlaboratory Comscrison Program, receired by Tecnnical Spscifica-tion 3.23.3.

6.9.5 Semi Annual Et t luent Release Reoert Note: A single submittal may be mace for the station. The submittal should combine those sections ?nat are common to both units at the station however; f or units with separate racwaste systems, the submittal shall specify tne release of racicactive material f rom each unit.

6.9.5.1 Routine radioactive ettluent release reports covering the coerations of the unit curing the previous 6 months of operation snall be su:-

mitted within 60 days after January 1 anc July I cf each year.

6.9.S.2 The radioactive ef f l uent release reports shall include a summary of the quantities of radicactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guice 1.21,

" Measuring, Evaluating and Reporting Radioactivity in Solid Wastes anc Releases of Racioactive Materials in Liquic anc Gaseous Ettluents from Light-Water-Cooled Nuclear Power Plants", Revision 1, June 1974, with data summari:ec on a quarterly casis following the format of Appendix 3 inerect.

The radioactive ett l uent release report to be sucmitted 60 days after January 1 of eacn year snall include an annual summary of hourly meteorological cata collected over tne previous year.

This annua l summary may Oe eitner in tne form of an hour-by-hour listing of.inc speed,.inc cirection, atmospheric stability, and precipitatior. (it measurec) on magnetic tape, or in tne form of joint f requency distribution of wind speed, ind direction, and atmospheric stacility. Tnis same reocr? shall include an assessment of the radia-tion ccses cue to the racioactive liquid anc gasecus ef fluents released trem tne unit or sta-lon during tne previous calendar year.

This same repor snail also incluce an assessment cf +he radiation coses trem radicactive liquid anc gaseous effluents to individuals due to tneir activities insice the site Scuncery (Figures 5-3 and 5-4) during tne report period. All assumotions used in making tnese assessments (i.e., sceci f ic activity, exposure time and location) shall be inclucec in tnese rescrts. The me ecrological cencitions con-current witn tne time et release of radicactive materials in gaseous ettluents (as ceterminec by samoling trecuency anc measurement) snel!

De use: for cetermining the gaseous pa n.ay ccses. The assessmen ct l'

raciation ecses shali ce pertermed in accorcance witn ne Of fsite Dose Calculation Manual (000Y).

The radioactive effluent release repor* To be submittec 60 days af ter January 1 ct eacn year shall aiso inc!uce an assessmen* of raciation ccses to 'ne likely most exposed real individual from reactor releases onc cther nearDy uranium tuet cycle sources (!qcluding ccses trem primari etfluent Oa nways anc ci ect racia-ict t - tne Orevices 10 censecutive men ns to snca cente-ance i?n 40 07: 90 " Environ-men al Raciation c sc*ien Stancarcs +cr Nuclea-o.er Opera-icn".

Accep a:le mernces ter calculating tne ecse cont-i:u-icns ' rom !!cui Amendment No. M, 77 6-15

and g:seous 'tflu:nts aro giv;n in Rcgulatcry Guida 1.109, R;v. 1.

c The radioactive effluent release reports shall include the following information for each type of solid waste shipped of f site during the report period:

I

a. container volume,

b. total curie quantity (specify whether cetermined by measurement or estimate),

c. principal radionuclides (specify whether cetermined by measurement or estimate),

d. type of waste (e.g. spent resin, compacted dry waste, evaporator bottoms),

e. type of container (e.g., LSA, Type A, Type B, Large Quentity) and

f. solidification agent (e.g., cement, urea formaldehyde).

The radioactive ef fluent release reports snall include a sumnary of unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid efflu-ents on a quarterIy basis.

The radioactive effluent release reports shall include any changes to the Process Control Program (PCP) made during the reporting period.

Any changes to tne Offsite Dose Calculation Manual shall be submitted witn the next Semiannual Radioac-Ive Effluent Report.

6.10 RECORD RETENT10N 6.10.1 The following records shall be retained for at least five years:

a. Records of normal station ooerotion including power levels and periods of operation at each power level.

b. Records of principal maintenance activities, inclucing inspec-tion, repairs, substitution, or replacement of principal items l

of equipment important to safety.

c. Records of reportable occurrences.

d. Recorcs ut periodic checks, tests anc celibrations.

l

e. Records of reactor physics tests anc othe* special tests l

important to safety.

I

f. Changes to coerating procedures important to safe +y.

j

g. Recorcs of solic radioactive snipme9*s.

1 l

Amendment No.X, 77 6-19 e

h. Test results, in units of microcuries, for leak tests performed on licensed sealed sources.

i. Results of annual physical inventor, verifying accountability of licensed sources on record.

/

J. Control Room Log Book.

k. Shift Foreman Log Book.

=

6.10.2 The following records shall be retained for the curation of Operating License DPR-50.

a. Record and crawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.

b. Recoras of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c. Routine unit radiation surveys and monitoring records.

l

d. Records of radiation exposure history and radiation exposure status of personnel, including all contractors anc unit visitors who enter radioactive material areas.

e. Recoras of radioactive liquid and gaseous wastes released to the environment, anc records of environmental monitoring surveys.

f. Records of transient or operational cycles for those f acility components important to safety for a limited number of transients or cycles as defined in tne Final Saf ety Analysis Report.

g. Records of training and qualification for current memce s of the unit staff.

h. Records of in-service inspections performed pursuant to these Technical Specifications.

i. Recorcs of Quality Assurance activities required by tne Operational Quality Assurance P lan.

J. Recorcs of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

(

k. Recoras of reviews by the Independent Onsite Safety Review Group (previously Plant Operations ?eview Committee and General Office l

l Review Board minutes).

1

1. Records c+ analyses required by the raciological environmental monito-ing program.

6-20 Amendment No. E, JW, Jr, 77

=

m.

m'. R: cords cf tho servico lives of all hydraulle snubb rs list:d on Table 3.16.1 Irtcluding the date at which the service life com-mences and associated installation anc maintenance records.

n. Recorcs for Environmental Qualification which are covered under the provision of paragraph 6.15.

I 6.11 RADIATION PROTECTION PROGRAM Procedures f or personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approvec, maintained and adhered to f or all operations involving personnel radiation exposure 6.12 HIGH RADIATION AREA 6.12.1 in lieu of the " control device" or " alarm signal" required by paragraph 20,203 (c)(2) of 10 CFR 20:

a. Each High Radiation Area shall be barricaded anc conspicuously posted as a High Radiation Area, anc personnel desiring entrance shall obtain a Radiation nork Permit (RWD).

Any individual enter-Ing a High Radiation Area shall (a) use a continuously indicating dose rate monitor!ng device or (b) use a radiation dose rate integ-rating device which alarms at a pre-set dose level, or (c) assure that a radiological control technician provides periodic radiation surveillance with a dose rate monitoring instrument.

b. Any area accessible to personnel where a major portion of the body could receive in any one hour a dose in excess of one thousand mrem shall be locked or guardec to prevent unauthorized entry. The keys to these locked barricades shall be maintained under the adminis-trative control of the Radiological Controls Foreman on duty.

The Radiation Work Permit is not requicec by Radiological Controls personnel during the performance of their assigned raciation protection duties proviced they are following radiological control procedures for entry into High Radiation Areas.

6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP'chall be approved by the Commission prior to implementation.

6.13.2 GPU Nuclear Corporation initiated changes to the PCP:

1. Shail be submitted to the NRC in the Semlannual Radioactive l

Effluent Release Report for tne ceriod in which the changes were made. This submittal shell contain:

s.

sufficiently detallec information to justify tne changes

/

without benc+it of a; ltional or supplemental information; b.

a determination thet the changes did not recuce the overall conformance of the solidifiec waste product to existing criteria for solid wastes; anc Amendment No. M,.7f,Jfg 77 6-21 sea L

c.

documentaticn thct tha chcng:s havo been rcvier:d and approved purspent to 6.8.2.

2. Shall become ef fective upon review and approval by GPUNC Management.

6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODOM shall be approved by the Coemission prior to implementation.

6.14.2 GPU Nuclear Corporation initiated cnanges to tne CDCM:

1.

Shall be submitted to the NRO in the Semiennuel Radioactive Effluent Release Report for the period in which the changes were made. This submittal shall contain:

a.

sufficiently cetailed information to justify the changes without benefit of additional or supplemental information; b.

a determination'that the changes did not reduce the ac-curacy or reliability of dose calculations or setpoint determinations; and c.

documentation that the changes have been reviewed and eperoved pursuant to 6.8.2.

2.

Shall become effective upon review and approval by GPUNC Management.

6.15 ENVIRONMENTAL QUALIFICATION 1.

By no later than June 30, 1982 all safety-related electrical equipment in the facility shall be qualified in accordance witn the provisions of Division of Operating Reactors "Guicelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in Operating Reactors" (DDR Guidelines) or, NUREG-0588 " Interim Staf f Position on Environmental Quali f ication of Saf ety-Relatec Electrica l Equipment", December 1979. Copies of these documents are attached to Order for Modification of License DPR-50 dated October 24, 1980.

l 2.

By no late-than December 1,1980, comp lete and auditIDie l

records must be available anc maintained at a central loca-l tion which describe the environmente: qualification method l

used for all safety-related electrical equipment in suf-ficient detail to document the degree of compliance with the DDR Guidelines or NUREG-0588. Thereafter, such recorcs shoul l

be updated and maintained current as equipment is replaced, l

furtner tested, or otherwise f urther qua l i f ier.

6.16 ICDINE YONITORING PROGRAM A program wnien will ensure the capacility to accurately cetermine 10/24/QOOrder, Amendment fio. J P,77 6-22

tho airDorna lodino conccntratien in vital arcas und:r accid:nt c:nw ditions shall be implementcd. This program shall includ] th] fol-lowing:

1.

Training of personnel, 2.

Procedures for monitoring, and 3.

Provisions f or maintenance of secoling and analysis equipment.

6.17 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS 6.17.1 GPU Nuclear Corporation initiated saf ety related changes to the radioactive waste system (liquid, gaseous and solid):

l 1

1.

Shall be reported to the Commission in the Annual Report (Specification 6.9.1B) for the period in which the evalu-ation was reviewed. The discussion of each change shall l

contain:

a.

A summary of the evaluation that led to the determina-tion that the change could 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 of the equipment, components and processes involved and the interfaces with other plant systems; d.

An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto; e.

An evaluation of the change which shows the expected maximum exposures to individuals in the unrestricted area l

and to the general population tnet differ from those l

previously estimated in the license application and amencments thereto; t.

A comparison of the predicted releases of radioactive materials, in IIquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made; g.

An estimate of the exposure to plant operating personnel as a result of the change; and h.

Documentation of tne fact that the change was reviewed and Amendment No. Jf-77 6-2}

w l

w

Cpproved.

t 2.

Shall become effective upon review and approval in accordance with Section 6.5.1.

i I

I i

l 1

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1 6-24 Amendment No. E, 77 9