Text

Amends 95,83 & 66 to Licenses NPF-41,NPF-51 & NPF-74, Respectively,Implementing Recommendations of GL 93-07 to Revise TS Section 6.0, Administrative Controls
	ML17311B056
Person / Time
Site:	Palo Verde
Issue date:	07/07/1995
From:	Thomas C; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML17311B058	List: ML17311B056; ML17311B059;
References
	GL-93-07, GL-93-7, NUDOCS 9507210320
	Download: ML17311B056 (74)
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 ARIZONA PUBLIC SERVICE COMPANY ET AL.

DOCKET NO.

STN 50-528 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.

1 AMENDMENT TO FACILITY'OPERATING LICENSE Amendment No.

95 License No.

NPF-41 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric

Company, Southern California Edison

Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority dated April 6,

1995, as supplemented by letter dated June 7,

1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) 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 Commission's regulations; D.

The issuance of this amendment w'ill 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 Commission's regulations and all applicable requirements have been satisfied.

2.

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.

NPF-41 is hereby amended to read as follows:

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(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix.A',. as revised through Amendment No.

95, and the Environmental Protection Plan contained in Appendix 8, are hereby incorporated into this license.

APS shall operate the facility in accordance with the Technical Speci.fications and the Environmental Protection

Plan, except where otherwise stated in specific license conditions.,

3.

This license amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION r

/-'e~

.-. Charles R. Thomas, Project Manager

'roject Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes

'to the Technical Specifications Date of Issuance:

0

~ '

'1 ll

ADMINISTRATIVE CONTROLS

6. I RESPONSIBILITY

6. 1.1 The Department

Leader, Operations shall be responsible for overall unit operation and shall delegate in, writing the succession to this responsibility during his absence.

6. 1.2 The Shift Supervisor, or during his absence from the Control

Room, a

designated

.individual per Table 6.2-1, shall be responsible for the Control Room command function.

A management directive to this effect, signed by the Vice President-Nuclear Production shall be reissued to all station personnel on, an annual basis.

6. 2 ORGANIZATION 6.2.1 OFFSITE AND ONSITE ORGANIZATIONS An offsite and an onsite organization shall 'be established for unit operation and corporate management.

The offsite and onsite organization shall include the positions for activities affecting the safety of the nuclear power plant.

a ~

b.

C.

d.

Lines of authority, responsibility and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions.

Those relationships shall be documented and updated, as appropriate, in the form of organizational charts.

These organizational charts will be documented in the FSAR and updated in accordance with 10 CFR 50.71(e).

There shall be an individual executive position (Executive Vice President Nuclear) in the offsite organization having corporate responsibility for overall plant nuclear safety.

This individual shal-1 take any measures needed to ensure acceptable performance of the staff in operating, maintaining and providing technical support in the plant so that continued nuclear safety is assured.

There shall be an individual management position (Vice President, Nuclear Production) in the onsite organization having responsibility for overall, unit safe operation and having control over those onsite resources necessary for safe operation and maintenance of the plant.

Although the individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate.

management

onsite, they shall have sufficient organizational freedom to be independent from operating pressures.

6.2.2 UNIT STAFF a.

Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

PALO VERDE - UNITI'-1 Amendment No. SS,

'll l

(4

ADMINISTRATIVE CONTROLS UNIT STAFF (Continued) b.

C.

d.

e.

6.2.2.1 a0 At least one licensed Reactor Operator shall be in the Control Room when fuel is in the reactor.

In addition, while the reactor is in MODE 1, 2, 3, or 4, at least one licensed'enior, Reactor Operator shall be in the Control Room.

A radiation protection technician" shall be onsite;when fuel is in the reactor.

All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor'Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

A site Fire Team of at least five members shall be maintained onsite at all times*.

The Fire Team shall not include the Shift Supervisor, the STA, nor the 3 other, 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.

The unit staff working hours shall be as follows:

Administrative procedures shall be deve'loped and implemented to limit the working hours of unit staff who perform safety-,related functions;

e. g., Senior Reactor 'Operators, Reactor Operators, radiation protec-tion technicians, auxiliary operators, and key maintenance personnel.

"The radiation protection technician and Fire Team composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to accommodate unexpected

absence, provided immediate action is taken to fill the required positions.

PALO VERDE - UNIT 1 6-la AMENDMENT NO. 40

ADMINISTRATIVE'CONTROLS b

Adequate shift coverage

',.h ll b t h ve perating p.

shall be ma>nta)ned w'ithout

,use of overt>me.

The,ob'ective, s

a

However,

.'roblems requi

's o

k, ominal 40-hour week.w 1

e ire substantial amounts o

vent that, unfore.e n p, followed ~th mporary b~~is 1

d s the STA and PVNGS Fire'pa ld, not be permitted to work more I)

An )ndsvsdual should, no 16 hour~ straight, excluding s i k more than, 2)

'A indsvsdual, should not be p'ermitted to d'or 2 ho '-d d

ll 48-hour period, nor more than 72 ours i excluding shift turnover time..

4

't least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months s ou h

ld be allowed between work hift tur nover time.

periods, including s s

d shutdown periods, the use.

. of overtime 4)

Except during d

1 b

d t f th should be considered.

on an indiv'~ ua in

'tire staff on a shift.

e ui esness b

c ny e

. uidelines shall be,.authorized y

c.

Any dev>at>on from the above gu o

Leader level or ia o e,,

1 b 'd th es

.'d with docuo)en' i

ho are at the Department hall be i 1

d d th granting the'eviation.

Controls s

a these aut orize h

d di d

1 o

th i s

a

't excessive ours

>a designees to assure tha; h

i vg robot been assigned e

uidelines is riot <<uthonze Routine deviation from the above gus' i

e PALO VERDE UNIT I Amendment No. $8, 995,

TABLE 6. 2-1 HININN SHIFT CREW GNPOSITION POSITION NNBER OF INDIVIDUALSRE/VIREO TO FILL POSITION SS SRO RO AO STA HODE 1, 2, 3, OR 4 1

1 2

2 1

ISDE.S OR 6 None 1

1 None SS

- Shift Supervisor with a Senior Reactor Operators License SRO - Individual with a Senior Reactor Operators License RO

- Individual with a Reactor Operators License AO - Nuclear Operator I or. II STA - Shift Technical Advisor The Shift Crew Composition may be one less than the minimum requirements of Table 6.2-1 for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided iasediate action is taken to resotre 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 ao oncoming shift crewman being late or absent.

During any absence of the Shift Supervisor from the Control Room while the unit is in NODE 1, 2, 3, or 4, an individual with a valid Senior Operator license shall be designated to assume the Control Room ceanand function.

During any absence of'he Shift Supervisor from the Control Room while the unit is in NODE 5 or 6, an individual with a valid Senior Operator or Operator license shall be designated to assume the Control Room command function.

PALO VERDE - UNIT 1 6-5 aMENDNENT NO- >>

ADMINISTRATIVE CONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERIIIG DEPARTHE~NT ISE)

FUNCTION 6.2.3.1 The ISE Department shall function to selectively examine plant operating characteristics, NRC, issuances, industry advisorie

', Licensee Event

Reports, and other sources of plant design and operating experience information, including plants of similar design, whi<h may indicate areas for improving plant safety.

COMPOSITION 6.2.3.2 The ISE Department shall be composed of at 'least five, dedicated, full-time engineers located on site.

Each shall hav'e a Bachelor's Degree in engineering or related science and at least two years professional

'level experience in his field.

RESPONSIBILITIES 6.2.3.3 The ISE Department shall be responsible for maintaining surveillance of selected.plant activities to provide independent verification* that these

~

activities are performed correctly to reduce human errors as much as practical, and to detect potential nuclear safety hIazkrdis.

'UTHORITY 6.2.3.4 The-ISE Department shall make detailed recommendations for rev'ised'rocedures, equipment modi.fications, maintenance activities, operations activities or other means of improving p'lant saf'et/

t~o the Director, Site Operations, and the Chairman, Offsite Safety Revie* Committee (OSRC).

RECORDS 6.2.3.5 Records of activities performed by the ISE Department shall be

prepared, maintained, and forwarded each calendar month to the Director, Nuclear Assurance or designated alternate.

6.2.4 SHIFT TECHNICAl ADVISDR 6.2.4.1 The Shift Technica1 Advisor (STA).sha11 provide advisory technical support to the -Shift Supervisor in the areas'of'hermal hydraulics, reactor'ngineering, and plant analysis with regard to 'th0 strafe operation of the un'it.

The STA shall be onsite and shall be available in the control room within 10 minutes whenever one or more units are in MODE I, 2, 3, or 4.

6.3 UNIT STAFF UAL IF ICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qual'ifi-cations of ANSI/ANS 3.1-1978 and Regulatory Guide 1.8, September 1975, except for the Director, Site Radiation Protection who sha'll meet or exceed the qualifications of Regulatory Guide 1.8, September

1975, and the Shift Technical Advisor who shall have a bachelor's degree or ~eqdilallnt in a, scientific or engineering discipline with specific training in plant design and plant operating

",Not responsible for sign-off function.

PALO VERDE - UNIT I 6-fi Amendment No. $$,95

ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF UALIFICATIONS (Continued) characteristics, including, transients and accidents.

An additional exception is that the Senior Reactor Operator (SRO) license requirement for the Operations Department Leader shall be met if either the Operations Department Leader or the Operations Supervisor holds a valid SRO license.

The holder of the SRO license shall direct the licensed activities of the licensed operators.

6.4 TRAINING 6.4.1 A training program for the unit staff shall be maintained under the direction of the Director, Nuclear Training and shall meet or exceed the requirements of Section 5.0 of ANSI/ANS 3. 1, 1978 and 10 CFR 55.

The program shall include familiarization with relevant industry operational experience.

6.5 REVIEW AND AUDIT 6.5. 1 PLANT REVIEW BOARD PRB FUNCTION 6.5.1. 1 The Plant Review Board shall function to advise the Vice President Nuclear Production or. his designee on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The PRB shall be composed of at least seven members from the Palo Verde management staff.

These positions will be designated by the Vice President Nuclear Production or his designee in Administrative Procedures.

The Vice President Nuclear Production or his designee shall designate the Chairman and designated alternate in writing.

The Chairman and designated alternate may be from outside the members provided that they meet ANSI/ANS 3.1, 1978.

ALTERNATES 6.5.1.3

.All alternate members shall be appointed in writing by the PRB Chairman to serve on a temporary basis;

however, no more than two alternates shall participate as voting members in PRB activities at any one time.

MEETING FRE UENCY 6.5. 1.4 The PRB shall'eet at least once per calendar month and as convened by the PRB Chairman or designated alternate.

PALO VERDE UNIT 1 6-7 Amendment No. 58,95

ADMINISTRATIVECONTROLS gUORUN 6.5.1.5 The quorum of the PRB necessary for the per'formance of the PRB responsi i;i y an b'lity and authority provisions of these Technical Specifications shall consist of the Chairman or a designated alterdale And a maj ri y o t of the members including alternates,.

RESPONS I BI LITIES 6.5.1.6 a ~

b.

c ~

d.

e.

The PRB shall be respon ible for".

Review of all proposed changes to Append'ix "A" Technical Specifications.

Investigation of all vio'llations,of the Technical Specifications including the preparation,and forward'ing of reports covering evaluation and recoimmendations to prevent recurrence to the Offsite

'afety Review Committee (OSRC).

Review of REPORTABLE EVENTS.

Review of unit operations to detect potentia1l nuclear safety

hazards, Performance oF special reviews, investigations or analy'ses and

.reports thereon as requested by the Vice President-Nuc,lear Production or PRB Chairman.

R view and documentation of,judgment concerning prolonged operation in bypass, channel trip,.and/or repair'of defective protection channels of process variables placed iA bypass'ince the last PRB meeting.

AUTHORITY 6.5.1.7 The PRB shall::

b.

Render.determi'nations

'in writing with regard to whether or not each item considered under Specification 6.5.i.6b.

above constitutes a~,

unreviewed safety question.

Prov'ide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Executive Vice President

Nuclear, Vice President Nuc)ear Production and OSRC of

'isagreement between the PRB and the Vice President Nuclear Production;,however,.

the Vice President Nuclear Production shall have responsibility for resolution;of~ sdch~di'sagreements.

RECORDS 6.5.1.8 The PRB shall maintain written minutes of, each PRB meeting that, at a

minimum, document the result.;. of all PRB activities performed under the responsibility and authority provisions of these Technical Specifications.'opies shall be provided t;o the, Executive Vice'resident Nuclear, Vice President Nuclear Production, and OSRC.

PALO VERDE UNIT I Amendment No. S895

ADMINISTRATIVE CONTROLS..

6.5. 2 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.2. 1 The Vice President Nuclear Production or his designee shall assure that each procedure and program required by Specification 6.8 and other procedures which affect -nuclear safety, and changes

thereto, is prepared by a qualified individual/organization.

Each such procedure, and'hanges

thereto, shall be reviewed by an individual/group other than the individual/group which prepared the procedure, or changes

thereto, but who may be from the same organization as the individual/group which prepared the procedure, or changes thereto.

6.5.2.2 Phase I IV tests described in the FSAR that are performed by the plant operations staff shall be approved by the Director, System Engineering or his designee as'previously designated by the Vice President Nuclear Production.

Test results shall be approved by the Director, System Engineering or his designee.

6.5.2.3 Proposed modifications to unit nuclear safety-related structures, systems and components shall be designed by a qualified individual/organization.

Each such modification shall be reviewed by an individual/group other than the individual/group which designed the modification, but who may be from the same organization as the individual/group which designed the modification.

Proposed modifications to nuclear safety-related structures, systems and components shall be approved prior to implementation by the Department 'Leader, Operations; or by the Director, Site Operations as previously designated by the Vice President Nuclear Production.

6.5.2.4 Individuals responsible for reviews performed in accordance with 6.5.2.1, 6.5.2.2, and 6.5.2.3 shall be identified in station procedures.

Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary.

If deemed necessary, such review shall be performed by the appropriate designated review personnel.

6.5.2.5 Proposed tests and experiments which affect station nuclear safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by the Vice President Nuclear Production or his designee.

6.5.2.6 Not used.

6.5.2.7 Not used.

6.5.2.8 The Director, Site Radiation Protection shall assure the performance f

of a review by a qualified individual/organization of every unplanned onsite release of radioactive material to the environs including the prepar ation and forwarding of reports covering the evaluation, recommendations and disposition of the corrective action to prevent recurrence.

PALO VERDE UNIT I 6-9 Amendment No. 58,95

ADMINISTRATIVECONTROLS

6. 5.3 OFFSITE SAFETY.REVIEW CORR~ITFEE OSR+C FUNCTION 6.5.3.1 The OSRC shall function to providi independent review and sha'ill be responsible for the audit of desigr>ated,activities in the,:areas of:

a.

nuclear.power plant operati'one b.

,nuclear engineering c.

chemistry and, radiochemistry d.

metallurgy e.

instrumentation and control f.

radiol,ogical safety g.

mechanical and electr'ical engineering h.

quality assurance practices COMPOSITION

';5.3;2 The OSRC shall be composed of tlie OSRC Chairman and a,minimum of four OSRC members.

The Chairman and members are desi'gnated-by,the Eyecut'ive Vice President, Nuclear and'hal'I have the qualificatio'ns ithat pest 'the requirements of Section 4.7 of ANSI/ANI 3.1; 1978.'ONSULTANTS 6.5.3'.3 Consultants sha'll be util'ized as determined by the OSRC Chairman to provide expert advice to the OSRC.

REVIEW 6.5.3.4 The OSRC sha11. review:

a ~

The safety evaluations program and its implementation for (1) changes to procedures, equipment, systems or facilities within the power block, and '{2) tests or experiments completed under the provision. of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question; PALO VERDE - UNIT 1 6-1O:

Amendment No. $8,95

ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

The NRC Operations Center shall be notified by telephone as soon as possible and'n all cases within: I 'hour.

The Vice President Nuclear Production, Director, Site Operations and Chairman of the OSRC shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

A Safety Limit Violation 'Report shall be prepared.

The report shall be reviewed by the PRB.

This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components,

systems, or structures, and (3). corrective action taken to prevent recurrence.

c.

The Safety Limit Violation Report shall be submitted to the Commission, the Chairman of the OSRC and the Vice President Nuclear Production within 30 days of the violation.

d.

Critical operation of the unit shall not be resumed until authorized by the Commission.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced'elow:

'a ~

b.

C.

The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February

1978, and those required for implementing the requirements of NUREG-0737.

Refueling operations.

Surveillance and test activities of safety-related equipment.

d.

Not used.

e.

Not used.

f.

Fire Protection Program implementation.

g.

Modification of Core Protection Calculator (CPC) Addressable Constants.

NOTES:

(I) Modification to the CPC Addressable Constants based on information obtained through the Plant Computer CPC data link shall not be made without prior approval of the PRB.

(2) Modifications to the CPC, software (including algorithm changes and changes in fuel cycle specific data) shall be performed in accordance with the most recent version of CEN-39(A)-P, "CPC Protection Algorithm Software Change Procedure," that has been determined to be applicable to the facility.

Additions or deletions to CPC Addressable Constants or changes to Addressable Constant software limit values shall not be implemented without prior NRC approval'.

PALO VERDE UNIT 1 6-13 Amendment No.. 87., 95

NISTRATIVE CONTROLS

EOURES AND PROGRAMS Continu~ed h.

PROCESS CONTROL PROGRAM timplemeqtatiqn.

0FFSITE DOSE CALCULATION MANUAL implqmentation.'o ram for effluent and environmental monitoring,,

'd 1 21 R

J 1974 d

I sing the guidance in Regulatory Gus e

e e

ri'il 1975.

Regulatory Guide 4.1, Revision 1, p '

Pre-planned Alternate Sampling Program implementat>on.,

1.

Secondary water chemistry program implementation.

shall erform a secondary water che6istrp monitonng and

'th th o

d S

t"o ontrol program that is in confqrmynce ws

. e 0 3.4.1 of the CESSAR FSAR or another NRC'pproved program.

r e

~

m.

Post-Accident Sampling System implementation.*

Settlement Monitoring Program implementation, ement monitorikg program throughout the

'OTE:

The licensee shall maintaits a settlement moni g p l'ife of the plant in accordance with the program presented in Ta e

PVNGS FSAR or another NRC approved iirogram.~

o.

CEA Reactivity Integrity Program 'implementation a ter initial fuel'oad'r after -each reload, NOTE:

The licensee shall perform, after snit>a s mmetr test or worth measurements of all fu

eng,'VNGS SER dated November 11, 1981..

address Section 4.2.2 of the p.

Fuel Assembly Sukvetillance

~Prqgr'am Implementa'tion, fuel assembly su'rveil'lance. program in NOTE:

The licensee shall perform a fuel ass y

conformance ws e

th th program di~cussed in Section 4.2.4 o

e T

November 11, 1981.

ro ram or procedure of Specification 6,.8.1, and changes thereto, ified in Specification 6.5 and approved prior to.

Pro rams, admi istrative control procedures and implementing d b th V'resident-Nuclear Production or a ternate who is at supervisory level or above.

Programs and p

6 8 1

hall be reviewed periodically as set forth procedures of Specification s

a in administrative procedures.

6.8.3 Temporary changes to procedures of ~pecificaton'6.'8.1 above may be made pt.ovided:

a.

The intent of the original procedure is not altered.

ff han e is a

roved by two members of the plant supervisory sta Sh'ft S

ervisor; or Control Room Supervisor at least one of whom is a

s

upervi, with an SRO on the affected unit.

The chan e is documented, reviewed sn accordance

'ith S eci fication d b the cognizant department

head, as designate y

6.5.2 and approve y

e the Vice President-Nuclear Production,~ within ay implementation.

Not required until prior to exceeding 5X of RATED'HERMAL POWER.

PALO VERDE - UNIT 1 6-14 Amendment No. SS, 95

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'DMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS Continued 6.8.4 The.followi'ng programs shall be.established, implemented, maintained, and shall be audited under the cognizance of the OSRC at least once per 24 months:

a.

Primar Coolant Sources Outside Containment A program to reduce leakage from those portions of systems. outside containment that could contain. highly radioactive fluids during a

serious transient or accident to as low as practical levels.

The systems include the recirculation portion of the high pressure safety injection system, the shutdown cooling, portion of the low pressure safety injection system, the post-accident sampling subsystem of the reactor coolant sampling system, the containment spray system, the.post-accident sample return piping of the radioactive waste gas

system, the post-accident sampling return piping of the liquid radwaste

system, and the post-accident containment atmosphere sampling piping of the hydrogen monitoring

'ubsystem.

The program shall include the following:

(I)

Preventive maintenance and periodic visual inspection requirements,,

and (2)

Integrated leak test requirements for each system at refueling cycle intervals or less.

b.

In-Plant Radiation Monitorin C.

A program which will ensure the capabi:lity to accurately determine the airborne iodine concentration in vital areas under accident conditions.

This program shall include the following:

(I)

Training of personnel, (2)

Procedures for monitoring, and (3)

Provisions for maintenance of sampling and analysis equipment.

Secondar Water Chemistr A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation.

This program shall include:

(I)

Identification of a sampling schedule for the critical variables and'ontrol points for these variables, (2)

Identification of the procedures used to measure the values of the critical variables, (3)

Identification of,process sampling points, which shall include mon'itoring the discharge of the condensate pumps for evidence of condenser in-leakage, (4)

Procedures for the recording and management of data,.

PALO VERDE UNIT I 6-15 Amendment No. 87,95

ADMINISTRATIVE CDNTRDLS

~.

I, I PROCEDURES AND PROGRAMS (Continued

-(5)

Procedures defining corr'ective actions for alT off"control point chemistry conditions, and-d.

e.

(6)

'A procedure identifying (a) the authority responsible for'. the interpretation of the data, and (b) the sequence and 'timing of

'dministrative events required to ilnitialte Icor rective action.

ll

' -,~S 1

~N' program which will ensure the capabil,ity to accurately monitor the Reactor Coolant System subcooling margin..

i This~ program shall 'include the.fol 1 owing:

(1)

Training of personnel, and (2)

Procedures for monitoring.

Post-Accident Sa~m lin A program which will ensure the capabi'lity. to 'obtain and analyze reactor coolant, radioactive iodines and 'particulates in plant gaseous effluents, and containment atmosphere,sampl,,es under accident conditions.

The program shall include. the following:

(1)

Training of personnel, (2)

Procedures for sampling and analysis,

{3)

Provisions for mai'ntenance of sampling and analysis eq0ipment,.

g.

A program:which will identify and describe the parameters'an'd activities used to control and monitor thei Essential Spray Pond and Piping.

The program shall be conducted in accordance with station

,'anual procedures.

Radioactive Effluent Controls~Pro ran A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and~ for maintaining the doses to MEMBERS OF THE PUBII.IC from radioactive

'effluents as low as reasonably achievable.

The program {1) shall be contained in the ODCM, (2) hall be implemented by operating procedures, and'(3) l shall include remedial actions to be t5ken whenever the program

'imits are exceeded.

The program shall include /he following elements:

{1).Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including. urveillance te. ts and setpoint determination in accordance with the meth'odol'ogy in the

ODCM, PALO VERDE - UNIT 1 6"16 AMENDMENT NO gj. 62

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS Continued (2)

(3)

(4)'5)

(6)

(7)

(9)

(10)

Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix 8, Table Il, Column 2, Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20. 106 and with the methodology and parameters in the

ODCM, Limitations on the annual

.and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive.materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10'FR Part 50, Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days.

Limitations on the operability and use of the liquid and gaseous'ffluent treatment systems to ensure. that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10,CFR Part 20, Appendix B, Table II, Column 1, Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10"CFR Part 50, Limitations on the annual and quarterly'doses to a

MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, Limitations on the annual dose or dose commitment to any 'MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

PALO VERDE UNIT 1 6-17 Amendment No. -62, 95

ADMINISTRATIVE CONTROLS Radiolo ical Environmental'onitoring Program A program shall be provided to monitor the radiation and radionuclides in the environs of the plant.

The program shall provide (1) representative measure'ments of radioactivity in the highest potential exposure

pathways, and (2') verification of the accuracy of the effluent monitoring program and imodel,ing of environmental exposure pathways.

The program shall (I) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

(1)

Monitoring, sampling, analysis, and reporting, of rad'iation and radionuclides in the env'ironment in accordance with the methodology and parameters in the

ODCM,

{2)

A Land Use Census to ensure that changes in the. use of areas at and beyond the

SITE, BOUNDARY are identified and that modifications to the monitoring program are made if required by the. results of this census, and (3)

Participation in a Interlaboratory Comparison Program to ensure that independent checks on the preci'sion and accuracy of the measurements of r'adioactive materials in environmen'tal sample matrices are performed as part of the quality,assurance program

'or environmental monitoring.

6. 9 REPORTING RE UIREMENTS ROUTINE REPORTS 6.9. 1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submi tte,d to the Regional Administrator of the Regional Office of the NRC unleSs otherwise noted.

STARTUP REPORT

6. 9. 1.1 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 manufactured by a d'ifferent fuel supplier, and.(4) modifications that may have significantly altered the nucle'ar>

thermal, or hydraulic pe.rformance of the plant.

PALO VERDE - UNIT 1 6-18 AMENDMENT NO.

27, 62

ADMINISTRATIVE CONTROLS.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time, period specified for each report.

6.9.3 Violations of the requirements of the fire protection program described in the Final Safety Analysis Report which would have adversely affected the ability to achieve and maintain safe shutdown in the event of a fire shall be reported in accordance with 10 CFR 50.73.

6. 10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6. 10. 1 The following records shall be retained for at least 5 years:

a.

Records and logs of unit operation covering time interval at each power level.

b.

. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

c.

All REPORTABLE EVENTS submitted to the Commission.

d.

Records of surveillance activities;,inspections and calibrations required by these Technical Specifications.

e.

Records of changes made to the procedures of Specification.6.8.1.

f.

'Records of radioactive shipments.

g.

Records of sealed source and fission detector leak tests and results.

h.

Records of annual physical inventory of all sealed source material'f record.

6. 10.2 The following records shall be retained for the duration of the unit Operating License:

a.

Records and drawing changes reflecting unit design modifications made to systems and equipment described in the FSAR.,

b.

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

c.

Records of radiation exposure for all individuals entering radiation control areas.

d.

Records of gaseous and liquid radioactive material released beyond the SITE BOUNDARY.

e.

Records of transient or operational cycles for those unit components identified in Tables 5.7-1 and 5.7-2.

f.

Records of reactor tests and experiments.

g.

Records of training and qualification for current members of the unit staff.

h.

Records of inservice inspections performed pursuant to these Technical Specifications.

PALO VERDE - UNIT 1 6-21 AMENDMENT NO; g7, 62

ADMINISTRATIVECONTROLS RECORD RETENTION Continued i.

Records of quality assurance activities required by the qA Manual not listed in Section 6.10.1.

Records of reviews performed for'hanges made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

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Records of PRB meetings and of OSRC activities.

Records of'he service lives of all hydraulic and mechanical snubbers required by Specification 3.7.9 including the date.at, which the service life commences and associatedl installiation and maintenance records.

Records of audits performed under the requirements of Specifications 6.5.3.5 and 6.8.4.

Records of analyses required by the radiological environmental monitoring 'program that would permit evaluation of the accuracy. of the analysis at a later date. 'his. shou'ld include procedures effective at specified times and gA records showing that these procedures were followed.

Meteorological data, summarized and reported in a format consistent with the recommendations of Regulatory 'Guides 1,21 and 1.23.

Records of secondary water sampling and water quality.

Records of reviews performed for'hanges made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PRO(RAN.,

6. 11 RADIATION PROTECTION PROGRAM 6.11. 1 Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained, and adhered to for all operatiotss involving personnel radiation exposure.

PALO VERDE UNIT 1 6-22 Amendment No. N-,68, 95

EI

~

ADMINISTRATIVE CONTROLS 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, Part 20, each high radiation area in which the intensity of radiation is greater than 100 mrem/hr but less than 1000 mrem/hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Exposure Permit (REP)*.

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied

.by one or

,more of the following:

a.

A radiation monitoring device which continuously indicates the radiation dose rate in the area.

b.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when, a preset integrated dose is received.

Entry into such areas with this monitoring device may be. made after the dose rate level in the area has been established and personnel

.have. been made knowledgeable of them.

c.

- A radiation protection qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency speci. fied by the facility Radiation Protection Section Leader or his designated alternate in the REP.

6. 12.2 In addition to the requirements of Specification 6. 12.1, areas accessible to personnel with radiation.levels such that a major portion of the body could receive in I hour a dose greater than 1000 mrem shall be provided with locked doors to prevent unauthorized

entry, and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or radiation protection supervision.

Doors shall remain locked except during periods of access

.by personnel under an approved REP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area.

For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in I hour a dose in excess of 1000 mrems**, that are located within large areas, such as PWR containment,,where no enclosure exists for purposes of locking, and,no enclosure can be reasonably constructed around the individual areas, then that area sha11 be roped off, conspicuously posted and a fl'ashing light shall be activated as a warning device.

In lieu of the stay time specification of the REP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.

Radiation Protection personnel or personnel escorted by Radiation Protection personnel shall be exempt, from the REP issuance requirement during the performance of their assigned radiation protection duties, provided they are otherwise following plant radiation protection procedures for entry into high radiation areas.

- Measurement made at 18 inches from source of radioactivity.

PALO VERDE UNIT I 6-23 Amendment No. 87-;62,95

ADMINISTRATIVE CONTROLS

6. 13 PROCESS CONTROL PROGRAM PCS Changes to the PCP:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6. 10.L.q.

This docualentation shall contain:

(1)

Sufficient, information to support the change together with the appropriate analyses or evaluations justifying the change(s) and (2)

A determination that the change wil') maintain the overall conformance of the sol'idified waste product. to existing requirements of Federal,

State, or bther'pplicable regulations.

b.

Shall become effective. after review and acceptance by the PRB and the approval of the Director, Site Radiation,Protect'ion.

6.14 OFFSITE DOSE CALCULAI'10N IIANUAL~ODCN Changes to the ODCM:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6,.10.2.q.

This documentation'hall contain::

())

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change{s) and (2)

A determination that the change will maintain the level of radioactive effluent control required-by 10. CFR 20. 106.

40 CFR Part

190, 10 CFR 50.36a,,

and Appendix I to 10 CFR, Part 50 and not adversely impact the accuracy or reliability of ef'fluent,

dose, or setpoint Icalcu'lations.

b.

Shall become effective after review and acceptance by the PRB and the approval of the Director, Site Chemis'try.

Shall be submitted to the Commission in t'e,'fo'rm of'

complete, legible copy of the entire ODCM as park df 6r Iconcurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM, was made.

Each change shall be identified by markings in the margin of the affected

pages, clearly indicating the area of the page that was changed, and shal'1 indicate the date {e.g., month/year) the'change was implemented.

6.15 MAJOR CHANGES TO RADIOACTIVE ~LI VID GASE US ND SOLID WASTE TREATMENT SYSTEMS*

6.15.1 Licensee-initiated major changes to the radioactive waste systems

{liquid, gaseous, and so'llid):

Shall be reported to the Commission it> the AnnualRadioactive Effluent Release Report for the period i'n whi'ch the evaluation was reviewed by the PRB.

The discussion ~f Ieach change shall contain:

1)

A summary of the evaluation that led to the determination that

'the change could be made in acco'rd4knc~e With 10 CFR'50.59.

"Licensees may chose to submit the information called for in this specification as part of the annual FSAR update.

PALO VERDE UNIT 1 6-24 dr d

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555-0001 ARIZONA PUBLIC SERVICE COMPANY ET AL.

DOCKET NO.

STN 50-529 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 83 License No.

NPF-51 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A. 'he application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of.itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric

Company, Southern California Edison

Company, Public Service Company of New Mexico, Los Angeles Department of Mater and Power, and Southern California Public Power Authority dated April 6,

1995, as supplemented by letter dated June 7,

1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the app'lication, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) 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 Commission'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 Commission's regulations and all applicable requirements have been satisfied.

2.

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. NPF-51 is hereby amended to read as follows:

~

(2) Technical S ecifications and Environmental Protection Plan The Technical Specifi'cations contained in Appendix A, as revised through Amendment No. 83, and the 'Environmental Protection Plan contained in Appendix B, are hereby incorporated into. this license.

APS shall operate the facility in accordance with the Technical Specifications

.and the Environmental Protection

Plan, except where otherwise stated in specific license conditions.

3.

This license amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

',.,, y,E/

, Charles R. Thomas, Project Manager Project Directorate, IV-2 Division of Reactor Projects III/IV'ffice of Nuclear Reactor Regulation

Attachment:

Changes to the Technical

'Specifications Date of Issuance:

Ouly 7, 1995

it 4

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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.

83 TO FACILITY OPERATING LICENSE NO. NPF-51 DOCKET NO.

STN 50-529 Replace the following pages of the Appendix A'echnical Specifications with the enclosed pages.

The revised pages are identi.fied by amendment number and contain vertical lines -indicating the areas of change.

The corresponding overleaf pages are also provided to maintain document completeness.

REMOVE 6-1 6-la*

6-2 6-5*

6-6 6-7 6-8 6-9 6-10'-13 6-14 6-15 6-16*

6-21*

6-22 6-23 6-24 INSERT 6-1 6-2 6-6 6-7 6-8 6-9 6-10 6-13

.6-14 6-15 6-22 6-23 6-24.

No changes were made to these pages; reissued to become overleaf pages.

it r ~

ADMINISTRATIVE CONTROLS

6. I RESPONSIBILITY 6.l.l The Department

Leader, Operations shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Shift Supervisor, or during his absence from. the Control

Room, a

designated individual per Table 6.2-1, shall be responsible for the Control Room command function.

A management directive to this effect, signed by the Vice President-Nuclear Production shall be reissued to all station -personnel on an annual basis.

6. 2 ORGANIZATION 6.2.1 OFFSITE AND ONSITE ORGANIZATIONS An offsite and an onsite organization shall be established for unit operation and corporate management.

The offsite and onsite organization shall include the positions for activities affecting the safety of the nuclear power plant.

a ~

Lines of authority, responsibility and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions.

Those relationships shall be documented and updated, as appropriate, in the form of organizational charts.

These organizational charts will be documented in the FSAR and updated in accordance with 10 CFR 50.71(e).

b.

There shall be an individual executive position (Executive Vice President Nuclear) in the offsite organization having corporate responsibility for overall plant nuclear safety.

This individual shall take any measures needed to ensure acceptable performance of the staff in operating,. maintaining and providing technical support in the plant so that continued nuclear safety is assured.

c.

There shall be an individual management position (Vice President, Nuclear Production) in the onsite organization having responsibility for overall unit safe operation and having control over those onsite resources necessary for safe operation and maintenance of the plant.

d.

Although the individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate management

onsite, they shall have sufficient organizational freedom to be independent from operating pressures.

6.2.2 UNIT STAFF a.

Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

b.

At least one licensed Reactor Operator shall be in the Control Room.

when fuel is in the reactor.

In addition, while the reactor is in NODE I, 2, 3, or 4,.at least one licensed Senior Reactor Operator shall be in the Control Room.

PALO'ERDE UNIT 2 6-1 Amendment No. 4S, 83

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ADMINISTRATIVE CONTROLS UNIT STAFF (Continued)

C.

A radiation protection technician* shall be onsite when fuel is in the reactor.

d.

e.

All 'CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

A site Fire Team of at least five members shall be maintained onsite at all times*.

The Fire Team shall not include the Shift Supervisor, the STA, nor the 3 other 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.

6.2.2.1 The unit staff working hours shall be as follows:

ao Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions;

e. g., Senior Reactor Operators, Reactor Operators, radiation protec-tion technicians, auxiliary operators, and. key maintenance personnel.

"The radiation protection technician and Fire Team composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to accommodate unexpected absence,,

provided immediate action is taken to fill the required positions.

PALO VERDE - UNIT 2 6-Za AMENDMENT NO. 27

ADMINISTRATIVE CONTROLS UNIT STAFF (Continued) b.

Ade uate shift coverage shall be maintaineg without, routine heavy use of overt>me.

>e o jec t,

~

Ti b'ective shall b~z t have-operating personnel wor a nomina k

1 46-hour week while the, pl,an

>'s operating.

Howe in the event that unforeseen problems requ>re substantial amo n

overtime to be used, or during extended periods of shutdown for refueling, major maintenance, or majot plant modifications, on a

temporary basis,. the fol'lowing guidel,ings phyll be fol'iowed (this'xcludes, the'TA and 'PVNGS Five Depar'tm~!nt'orking'ours)".

1)

An individual should not be, permitted, tq work more than 16 houvs stvaight,,

excluding shift turnover time.

2)

An individual should not be permitted to work more than 16 h

any 24-hour period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, nov more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day p

ours in an eriod all excluding shif't tuv'nover time.

3)

A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work

periods, including shift turnover,'time.')

Except, during extended shutdown periods, the use: of overtimg should be considered on an individual basis and not for the~'ntire staff on a shift.,

C.

Any deviation from the above guidelines shall be authorized v onnel who are at the Director level or above, ov their desigpeps who are at the Department Leader level~or~ aPovq,,in, accovdan ce with establishecl procedures and w'ith documentaticln of the basis for ranting the deviation.-

Controls shall be included in the procedures such that individual overtime, in, their respective group~

shall be reviewed month'ly by these a'utIior'ized indivHuals or their designees to assure that excessive hours, have not been assigned.

Routine deviation from the above guidelin'es'is not authorized.

PALO VERDE - UNIT 2 Amendment No. 4S, 83

TABLE 6.2-1 MINIMUMSHIFT CREW COMPOSITION POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION NODE1,2,3,0R4 HODE 5 OR 6 SS SRO RO AO STA 1

1 2

2.

1 None 1

1 None SS - Shift Supervisor.with a Senior Reactor Operators License SRO - Individual with a Senior Reactor Operators License

'RO

- Individual with a Reactor Operators License AO - Nuclear Operator I or'II STA - Shift Technical Advisor The Shift Crew Composition lay be one less than the minimum requirements of Table 6.2-1 for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided ianediate 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 oncoming shift crewman being late or

,absent.

During any absence of the Shift Supervisor from the Control Room while the unit is in MODE 1, 2, 3, or 4, an individual with a valid'enior Operator license shall be designated to assume the Control Room command function.

During any absence of the Shift Supervisor from the Control Room while the unit is in NODE 5 or 6, an individual with a valid Senior Operator or Operator license shell be designated to assume the Control Room comnand function.

PALO VERDE UNIT 2

ADMINISTRATIVECONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING DEf'ARTMENT~ISE'i.

FUNCTION 6.2.3.1 The ISE Department shall function to selectively examine plant operating characteristics, NRC issuances, industry~ad~viCories, Licensee Event Reports and other sources of plant design and,operating experience information, including plants of similar design, which,may.indicate areas for improving plant safety.

COMPOSITION 6.2.3.2 The ISE Department shall be composed of at least five, dedicated, full-time engineers located on site.

Each shall have a, Bachelor's Degree. in engineering or related science and at least two years professional level experience in his field.

RESPONSIBILITIES 6.2.3.3 The ISE Department sha'll be responsib'lie for maintaining surveillance of selected plant activities to provide independent verification+ that these activities are performed correctly to reduce human errors as much as practical, and t'o detect potentiall nuclear safety hazards.

AUTHORITY 6.2.3.4 The ISE Department shall make detail.ed recommendations for revised procedures, equipment modifications, maintenance'ac'tiditties, operations activities or other means of improving plant safety'6. the Director, Site Operations, and the Chairman, Offsite Safety Review Cdmm~ittee

{OSRC).

RECORDS

~

I 6.2.3.5 Records of activities performed by the ISF'epartment shall be

prepared, maintained, and forw'arded each calendar month 'to'he Director, Nuclear Assurance or desigriated,alternate.

6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4. 1 The Shift Technic'a'I Advisor (STA) shall provide advisory technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor

'ngineering, and plant analysis with regard to the safe operation of the unit.'he STA shall be onsite and shall be ava,ilable in the contro'I room within 10 minutes whenever one or more units are in MOf)E I, '2,', or 4.

6.3 UNIT STAFF UAL IF ICATIONS 6.3.1 Each member of the unit staff shall meet~ or exceed the minimum qualifi-cations of ANSI/ANS 3,.1-1978 and Regulatory Guide ~1.8, 'September

1975, except for the Director, Site Radiation Protection who shall meet or exceed the qualifications of Regulatory Guide 1.8, September

1975, and the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design ancI plant operating

Not responsible for sign-off function.

PALO VERDE - UNIT 2 Amendment No. 4S, 83

ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF UALIFICATIONS (Continued) characteristics, including transients and accidents.

An additional exception is that the Senior Reactor Operator (SRO) license requirement for the Operations Department Leader shall be met if either the Operations Department Leader or the Operations Supervisor holds a valid SRO license.

The holder of the SRO license shall direct the licensed activities of the licensed operators.

6. 4 TRAINING 6.4.1 A training program for the unit staff shall be maintained under the direction of the Director, Nuclear Training and shall meet or exceed the requirements of Section 5.0 of ANSI/ANS 3.1, 1978 and 10 CFR 55.

The program shall include familiarizati'on with relevant industry. operational experience.

6. 5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW BOARD PRB FUNCTION 6.5. l.l The Plant Review Board shall function to advise the Vice President

'Nuclear Production or his designee on a11 matters related to nuclear safety.

COMPOSITION 6.5. 1.2 The PRB shall be composed of at least seven members from the Palo Verde management staff.

These positions will be designated by the Vice President Nuclear Production or his designee in Administrative Procedures.

The Vice President Nuclear Production or his designee shall designate the Chairman and designated alternate in writing.

The Chairman and designated alternate may be from outside the members provided that they meet ANSI/ANS 3.1, 1978.

ALTERNATES 6.5. 1.3 All alternate members shall be appointed in writing by the PRB Chairman to serve on a temporary basis;

however, no more than two alternates shall participate as voting members in PRB activities at any one time.

MEETING FRE UENCY 6.5. 1.4 The PRB shall meet at least once per calendar month and as convened by the PRB Chairman or designated alternate.

PALO VERDE UNIT 2 6-7 Amendment No. 4S, 83

ADMINISTRATIVE CONTROLS gUORUN 6-.5.1.5 The quorum of the PRB neces. ary for the per;formance of the PRB responsibility and authority provisions of these Technical Specifications shall consist of the Chairmari or a designated alternate and a majority of the members including alternates.

RESPONSIBILITIES 6.5.1.6 a 0 b.

C.

d..

e.

AUTHORITY The PRB shall be responsible for:

Review of all proposed changes to Appendix "A" Technical Specifications.

Investigation of all violations of the Technical Spec'ifications including the preparation and Forwarding of reports covering evaluation and recommendations to prevenII: r'ecurrhnce to the Offsite Safety Review Comittee (OSRC).

Review of REPORTABLE EVENTS.

Review 'of unit oper ations to detect, potential nuclear safety hazards.

Performance of special reviews, investigations or analy'ses and reports thereon as requested by the Vice President,-Nuclear Production or PRB. Chairman.

Review and documentation of judgment copcerning prolonged 'operation in:bypass, chan'nel trip, and/or repair of 'defective protection channels of process variables placed in 'bypass since the last PRB meeting.

6.5.1.7 The PRB shall:

a ~

b.

RECORDS Render determinations. in writing with regard tp whether or not each item considered under Specification 6.5.1.6b.

above constitutes an

'nrevi'ewed safety question.

Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Executive Vice President

Nuclear, V'ice President Nuclear'IIoduction and OSRC of disagreement between the PRB and the V'iceI PI'es'ident'uclear Production; however,,the Vice President Nuclear Producti,on.shall have responsibility For:resolution-of such disag0'eements.

6.5. 1.8 The PRB shall maintain written minutes of each PRB meeting that, at a

minimum, document the results of al.l PRB activit;ies perFormed under the responsibility and authority provisions of these Techni'cal Specifications.

Copies shall be pi ovided to the Executive Vice )re'siden~t Nuclear, Vice President Nuclear Production, and OSRC.

PALO VERDE UNIT 2 6-8 Amendment No. 4&,83

ADMINISTRATIVE CONTROLS 6.5. 2 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.2.1 The Vice President Nuclear Production or his designee shall assure that each procedure and program required by Specification 6.8 and other procedures which affect nuclear safety, and changes

thereto, is prepared by a qualified individual:/organization.

Each such procedure, and changes

thereto, shall be reviewed by an individual/group other than the indiv'idual/group which prepared

.the procedure, or changes

thereto, but who may be from the same organization as the individual/group which prepared the procedure, or changes thereto.

6.5.2.2 Phase I IV tests described in the FSAR that are performed by the plant operations staff shall be approved by the Director, System Engineering or his designee as previously designated by the Vice President Nuclear Production.

Test results shall be approved by the Director.,

System Engineering or his designee.

6.5.2.3 Proposed modifications to unit nuclear safety-related, structures, systems and components shall be designed by a qualified individual/organization.

Each such modification shall

.be reviewed by an individual/group other than the individual/group which designed the modification, but who may be from the same organization as the individual/group which designed the modification.

Proposed modifications to nuclear safety-related structures, systems and components shall'e approved prior to implementation by the Department

Leader, Operations; or by the Director, Site Operations as previously designated by the Vice President Nuclear Production.

6.5.2.4 Individuals responsible for reviews performed in accordance with 6.5.2. 1, 6.5.2.2, and 6.5.2.3 shall be identified in station procedures.

Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary.

If deemed necessary, such review shall be performed by the appropriate designated review personnel.

6.5.2.5 Proposed tests and experiments which affect station nuclear safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by the Vice President, Nuclear Production or his designee.

6.5.2.6 Not used.

6.5.2.7 Not used.

6.5.2.8 The Director, Site Radiation Protection shall assure the performance of a review by a qualified individual/organization of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering the evaluation, recommendations and disposition of the corrective action to prevent recurrence.

PALO VERDE UNIT 2 6-9 Amendment No. 48,83

DMINISTRATIVE CONTROLS i.S.3 OFFSIT SAFETY REVIEM CORRI I'TEE

~OSRC

.=UNCTION 6.5.3.l respons b.

c d.

e.

f~

g, h.

The OSRC'hall function to provide independent review and shall be ible for the audit of~designa~teP activities in tthe areas of:,

nuclear power plant operations nuclear engineering chemistry.and radiochemistry metallurgy instrumentation and control radiological safety mechanical and electrical engineering quality assurance practices

, COMPOSITION

/

6.5.3.2 The OSRC shall be'composed kf thk OSRC Chairman and a minimum of four OSRC members.

The Chairman and members are designated by, the Executive Vice President, Nuclear and shall have the qua'lifications that meet the requirements of Section. 4.7 of ANSI/ANI 3.1; 1978.

CONSULTANTS 6.5.3.3 Consultants shall be utilized as determined by the OSRC Chairman to provide expert advice to the OSRC.

REVIEM 6.5.3.4 The OSRC shall review:

The safety evaluations program and its implementation for (I) changes to procedure.,

equipment, systemst op f'acilities within the power block, 'and (2) tests or experiments completed'nder the provision of 10 CFR 50.59,. to verify that such actions did not constitute an unreviewed safety question; I

PALO VERDE - UNIT 2 6-10 Amendment No. 4S,83

ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION The following actions, shall be taken in the event a Safety Limit is violated:

'a ~

The NRC Operations Center shall be notified by tel'ephone as soon as possible and in all cases wi.thin I hour.

The Vice President Nuclear Production, Director, Site Operations and. Chairman of the OSRC shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by the PRB.

This report shall describe (I) applicable circumstances preceding the violation, (2) effects of the violation upon facility components,

systems, or structures, and- (3) corrective action taken to prevent recurrence.

c.

The Safety Limit Violation Report shall be submitted to the Commission, the Chairman of the OSRC and'he Vice President Nuclear-Production within 30 days of the violation.

d.

Cri,tical operation of the unit shal.l. not be resumed until authorized

'by the 'Commission.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:

a.

The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February

1978, and those required for implementing the requirements. of NUREG-0737.

b.

Refueling operations.

c.

Surveillance and test activities. of safety-related equipment.

d.

Not used.

e.

,Not used.

f.

Fire Protection Program implementation.

g.

Modification of Core Protection Calculator (CPC) Addressable Constants These procedures should.include provisions to ensure that sufficient margin is maintained in CPC Type I Addressable Constants to avoid excessive operator interaction with the CPCs during reactor operation.

NOTES:

(I) Modification to the CPC Addressable Constants based on information obtained through the Plant Computer CPC data link shal,l not be made without prior approval of the PRB.

(2) Modifications to the CPC software (including algorithm changes and changes in fuel cycle specific data) shall be performed in accordance with the most recent version of CEN-39(A)-P, "CPC Protection Algorithm Software Change Procedure,"

that has been determined to be applicable to the facility.

Additions or deletions to CPC Addressable Constants or changes to Addressable Constant software limit values shall not be implemented without prior NRC approval.

PALO VERDE UNIT 2 6-13

.Amendment 'No. 44,83

ADMINISTRATIVE CON1'ROILS PROCEDURES AND PROGRAMS ~Continued}

k.l.

PROCESS CON'I'ROL PROGRAM impilementat,ion.

OFFSITE DOSIE CALCULATION MANUAL implementation.

Quality Assurance, Program f'r effluent hand, environmental monitoring, using the, guidance in Regulatory Guide jl,.21, Revision 1, ')une 1974 and Regulatory'uide 4.1, Revision 1, April 1975.

Pre-planned Alternate Sampling Program implementation.

Secondary water chemi try pirogram implementat,ion.

NOTE:

The licensee shall perform a secondary water chemistry monitoring and control program that is in conformance with the program discusped'n Section 10.3.4.1 of'he CESSAR FSAR or another NRC approved program m.

'Post-Accident Sampling System implementati,on.*

n.

Settlement Monitoring Program implementation.

NOTE:

The. licensee shall maintain a settlement monitoring program throughout, the life of the plant in accordance witlh the: program presented in Table 2.5-18 of the PVNGS FSAR or another NRC approved program o.

CEA React,iv'ity Integrity Prog'ram implement~ation NOTE:

The l,icensee shall perform, af'te'r initial 1t'uel loaid or after each reload, either a

CEA symmetry test or wort'h measurements of all full-length CEA groups to address Sectlion 4.2.2 aif the PVNGS SER dated November ll, 1,981.

p.

Fuel Assembly Surveillance Program Implementation NOTE:

The licensee shall perform a f'uel assembly surveillance program in con-formance with the program discussed in Section 4.2.4 of the PVNGS SER dated November 11, 1981.

6.8.2 Each program or procedure of Speci'fication 6.8.1, and change.. thereto, shall be reviewed as specif'ied in Specification 6.5 and approved prior to implementation.

Programs, administrative control procedures and implementing i

procedures shall be approved 'by"the Vice President,-Nuclear Production, or designated alternate who is at supervisory level air above Programs and procedures of Speci fication 68. 1 shall, be reviewed periodically as set fiorth in administr ative procedures.

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

'a ~

b.

c ~

The intent of the original Iprocedure is not altereid.

The change is approved by two members of the plant supervisory staff, at least one of whom is a Shiift Supervisor or Control Raloml Supervisor with an SRO on the affected unit.

.The change is documented, reviewed in accordance with Specification 6.5.2 and approved by the cognizant depar'tment

head, as designated by the Vice President-Nuclear Production, within 14 days of implementation,.

Not required until prior to exceeding 5X of RATEDI THERMAI, POOWER.

PALO VERDE UNIT 2 6-,14 Amendment No. 4S, 83

~

ADM IN I STRATI VE CONTROLS PROCEDURES AND PROGRAMS Continued 6.8.4 The following programs shall be established, implemented, maintained, and shall be audited under the cognizance of the OSRC at least once per 24 months:

a.

Primar Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.

The systems include the recirculation portion of the high pressure safety injection system, the shutdown cooling portion of the low pressure safety injection system, the post-accident sampling subsystem of the reactor coolant sampling system, the containment spray system, the post-accident sample return piping of the radioactive waste gas system, the post-accident sampling return piping of the liquid radwaste

system, and,the post-accident

.containment atmosphere sampling piping of the hydrogen monitoring subsystem.

The program shall include the following:

(I)

Preventive maintenance and periodic visual inspection requirements, and (2)

Integrated leak test requirements for each system at refueling cycle.intervals.or less.

b.

In-Plant Radiation Monitorin A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions.

This program shall include the following:

(I)

Training, of personnel, (2)

Procedures for monitoring, and (3)

Provisions for maintenance of sampling and analysis equipment.

c.

Secondar Water Chemistr A,program for monitoring of secondary water chemistry to inhibit steam generator tube degradation.

This program shall include:

(I)

Identification of a sampling schedule for the critical variables and control points for these variables, (2)

Identification of the procedures used to measure the values of the critical variables, (3)

Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in-leakage, (4)

Procedures for the recording and management of data, PALO VERDE UNIT 2 6-15 Amendment No.

'RATIVE CONTROLS RES AND PROGRAMS Continued e.

{5)

Procedures defining corrective ac'tions for all off-control point chemistry conditions, and

{6)

A procedure identifying (a) the autlhority responsible for the interpretation of the data, and (b) the sequepcq and timing of administrative events required to initiate corrective'otion.

Backu method for Detarm~inin Subcoo1inq Marcrin A program which will ensure the capability to accurately monitor the Reactor Coolant System subcooling margin.

This program shall include the following:

(1)

Training of personnel, and (2)

Procedures for monitoring.

Post-Accident Sam lih A program which will ensure'he capability to obtain and analyze reactor coolant, radioactive iodines and= particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions.

The program shall inc'lude the following:

(1)

Training of personnel, (2)

Procedures for. ampling and analysis, (3)

Provisions for maintenance of sampling and analysis equipment, S ra Pond Monitorin A program which will identity and describe the parfum teerasnd activities used to contrdl and monitor the Essential Spray Pond and Piping.

The program sha1ll be conducted in aclcordance with station manual procedures.

Radioactive Effluent Controls ProcCram A program shalil be provided conforming with 10 'CFR 50.36a for the control of radioactive effluents and for maiptyining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as~low as reasonably achievable.

The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3') Shall include remedial, actions to be taken whenever the program liInits are exceeded.

The, program shall include the following element~s:

I (1)

Limitations on the operability of radioactive liquid and gaseous monitoring i'nstrumentation including surveillance te. ts and set-point determination in accordance with the,'ethodology in the

ODCM, OLD VERDE - UNIT 2 6-16 AMENDMENT NO. 48

ADMINISTRATI VE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report.

6. 9.3 Violations of the requirements of the fire protection, program described in the Final Safety Analysis Report which would have adversely affected the ability to achieve and maintain safe shutdown in the event of a fire shall be reported in accordance with 10 CFR 50.73.

6. 10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the.following records shall be retained for, at least the minimum period indicated.

6. 10. 1 The following records shall be retained for at least 5 years:

a.

Records and logs of unit operation covering time interval at each power level.

b.

. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

c.

All REPORTABLE EVENTS submitted to the Commission.

d.

Records of surveillance activities; inspections and calibrations required by these Technical Specifications.

e.

Records of changes made to the.procedures of Specification 6.8.1.

f.

Records of radioactive shipments.

g.

Records of sealed source and fission detector leak,tests and results.

h.

Records of.annual physical inventory of all sealed source material of record.

6. 10.2 The following records shall be retained for the duration of the unit Operating License:

a.

Records and drawing changes reflecting unit design modifications made to systems and equipment described in the FSAR.

b.

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

c.

Records of radiation exposure for all individuals entering radiation control areas.

d.

e.

Records of gaseous and liquid radioactive material released beyond the SITE BOUNDARY.

Records of transient or operational cycles for those unit components identified in Tables 5.7-1 and 5.7-2.

f.

Records of reactor tests and experiments.

g.

Records of training and qualification for current members of the unit staff.

h.

Records of inservice inspections performed pursuant to these Technical Specifications.

PALO VERDE - UNIT 2 6-21 AMENDMENT NO.

8, 48

iNISTRATIVE CONTROLS 3RD RETENTION {Continued)

I i

Records of quality assurance ac4ivities, required by the gA Manual not listed in Section 6.10.1.

Records of reviews performed for changes made to procedures, or e'quipment or reviews of tests and experiments pursuant to m.

n.

0 ~

P.

Records of PRB meetings and of OSRC activities.

R o

o

.re eso y

f all h draulic an'd kechanical llation and ubbers required by Specification 3.7.9 inclu >ng e

~ a e the service life commences and associated insta maintenance records.

I Records of audits performed under the requirement.;

o

~p f S ecifications 6.5.3.5 and 6.8.4.

Records of. analyses required by the radiological environmental monstorsng program

't am that would permit evaluation of the accuracy of s

the ana ysss a

a a e l

t a later date.

This should include procedure effective at specified times and gA records, showing tha that these procedures were followed.

/

Meteorological data, summarized and reported in a format consistent with the recommendations of Regulatory Guides 1.21 and 1.23.

Records of. secondary water sampling and water qual'ity.

'ecords of reviews performed for changes made to -the OF OFFSITE. DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

6.11 RADIATION PROTECTION PROGRAM 6

11 1

P edures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 2

roc maintained, and adhered to for all operations invol,ving per'sonne ra ia son exposure.

PALO YERDE - UNIT 2 Amendment No. &-,48,8'~

~

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4 ~

4

~I ADMINISTRATIVE CONTROLS 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 Part 20, each high radiation area in which the intensity of radiation is greater than 100 mrem/hr but less than 1000 mrem/hr shall be.barricaded and conspicuously posted as,a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radi-ation Exposure Permit (REP)*.

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a ~

b.

C.

A radiation monitoring device which continuously indicates the radiation dose rate in the area.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.

Entry into such areas with this monitoring devi'ce may be made after the dose rate level in the area has been established and,personnel have been made knowledgeable of them.

A radiation protection qualified individual (.i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Radiation Protection Section Leader or his designated alternate in the REP.

6.12.2 In addition to the requirements of Specification 6.12'.I, areas accessible to personnel with radiation levels such that a major portion of the body could receive in I hour a dose greater than 1000 mrem shall be provided with locked doors 'to prevent unauthorized

entry, and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or radiation protection supervision.

Doors shall remain locked except during periods of access by personnel under an approved REP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area.

For individual areas accessible to personnel, with radiation levels such. that a major portion of the body could receive in I hour a dose in excess of 1000 mrems**, that are located within large areas, such. as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas,.

then that area shal.l be roped off, conspicuously posted and a flashing light shall be activated as a warning device.

In lieu of the stay time specification of the 'REP., direct or. remote (such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection, procedures to provide positive exposure control over the activities within the area.

Radiation Protection personnel or personnel escorted by Radiation Protection personnel shall be exempt from the REP issuance requirement during the performance of their assigned radiation protection duties, provided they are otherwise following plant radiation protection procedures for entry into high radiation areas.

- Measurement made at 18 inches from source of. radioactivity.

PALO VERDE UNIT 2 6-23 Amendment 'No. 8-,48, 83

ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM

~PC~P Changes to the PCP:

'a ~

Shall be documented and records of reviews performed shall be retained ass require'd by Specification 6.10.2.q.

This documentation shal,l cont,ain:

(1)

Sufficient, information to support the change together with the appropriate analyses or evaluai;ions justify'ing the change(.;)

anci (2)

A det:ermination that the change will maintain the oyera'll conformance of the solidified waste product to existiI>g requirements of Federal, State,~

or other applicable regulations.

b.

Shall become effective after. revfewi and acceptance by the PRB and the approval of',tlhe Director, Site Radiation Protection.

6.14 OFFSITE DOSE CALCUl.ATIOhl MANU'AL ODOM Changes to the ODCM.:

a.

Shall be documented and records of reviews performed shall be retained as. requireci by Specification 6.50.2.q.

This documentation shall contain:

(1)

Sufficient infcirmation to support the, change together with, the appropriate analyses or evalualtiqns justifying the charige(s) and (2)

A determination tlhat, the change will maintain the level of, radioactive effluent control required, by 10, CFR 20.106, 40'FIR Part 190, 10 CFR 50.36a, and Appendix, I to 10 CFR f'art 50 and not.adversel,y impact the accuracy or reliability ot effluent, dose or setpoint ca1culations.

b.,

Shall become ef'fective after review and accIeptance by the 'PRB and the approval of tlhe Director, Site Chemistry.

c.

Shall be submit;ted to the Commission in the form of a comp'lete, legible copy of'he entire ODCM as a part of or concurrent with the Annual Ractioactivie -Eff'luent Re1ease'eiport,'for tpe,periqd of the report in which any change to the ODCM was made.

Eaclh c:hange shalll be identif'ied by markings in tlhe margi'n Of,'thy affected

pages, clearly indicat;ing the area of the page that was changed, andi shall indicate the date (e.g

, month/year) the change was implemented.

6.15 MAJOR CHANGES TO RADIOACTIVE LI(}UIID GA E

US ND SO ID WASTE TREATMENT SYSTEMS*

6.15.1 Licensee-initiated major changes to the radioactive waste systems (liquid, gaseous, and solid):

Shall be reported to the Commission in the Annual Radioactive Effluent release Report for the period in which the eva1luation Nasl review by the PRB.

Thee d,iscussion of leach ichange shall contain:

Licensees may chose to submit the information calledl for in.this specification as part of the annual IFSAR update.

PALO VERDE UNIT 2 6-24 Amendlment No. 8-,4r~8-,EV, 83

P ll

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VNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C.

2055&4001'RIZONA PUBLIC SERVICE COMPANY ET AL.

DOCKET NO. 'STN 50-530 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.

3 AMENDMENT TO FACILITY OPERATING LICENSE 2.

Amendment No.

66 License No. NPF-74 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power Distri'ct, El Paso Electric

Company, Southern California Edison

Company, Public Service Company of New Mexico, Los Angeles Department of Mater and

Power, and Southern California Public Power Authority dated April 6,

1995, as supplemented by letter dated June 7,

1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance,(i) 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 Commission'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 Commission's regulations and all applicable requirements have been satisfied.

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. NPF-74 is hereby amended to read as follows:

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3.

(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revi'sed through Amendment No. 66, and the Environmental Protection Plan contained in Appendix B, are 'hereby incorporated into this license.

APS shall operate the facility in accordance with. the Technical Specifications and the Environmental Protection Plan, except where otherwise: stated in specific license conditions.

This license amendment

.is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

,~ Cgi

'Charles R. Thomas, 'Project Manager Project Directorate IV-2 Division of Reactor 'Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Speci.fications Date of Issuance:

l~

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4

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ATTACHMENT TO LICENSE AMENDMENT'MENDMENT NO.

66 TO FACILITY OPERATING LICENSE NO. NPF-74

'DOCKET NO.

STN 50-530 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 areas of change.

The corresponding overleaf pages are also provided to maintain document completeness.

REMOVE

'6-1

6-la*

6-2 6-5*

6-6 6-.7 6-8 6-9 6-10 6-13 6-14'-15 6-16*

6-17.

6-18*

6-21*

6-22 6-23 6-24 INSERT 6-1 6-2 6-6 6-7 6-8 6-9

6-10 6-13 6'-l4 6-15'-17 6-22'-23 6-24

No changes were made to these pages; reissued to become overleaf pages

II

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s' s

v

~ s av sa ADMINISTRATIVE'CONTROL'S

6. 1 RESPONSIBILITY'.

1. 1 The Department

Leader, Operations shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Shift Supervisor, or during his absence from the Control

Room, a

designated individual per Table 6.2-1, shall be responsible for the Control Room command function.

A management directive to this effect, signed by the Vice President-Nuclear Production shall be reissued to all station personnel on an annual basis.

6. 2 ORGANIZATION 6.2.1 OFFSITE AND ONSITE ORGANIZATIONS An offsite and an onsite organization shall, be established for unit operation and corporate management.

The offsite and onsite organization shall include the positions for activities affecting the safety of the nuclear power plant.

a e Lines of authority, responsibility and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions.

Those relationshi'ps shall be documented and updated, as appropriate, in the form of organizational charts.

These organizational charts will be documented in the FSAR and updated in accordance with 10 CFR 50.71(e).

b.

There shall be an, individual executive position (Executive Vice President Nuclear) in the offsite organization having corporate responsibility for overall plant nuclear safety.

This individual shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining and providing technical support in the plant so that continued nuclear safety is assured.

C.

There shall be an individual management position (Vice President, Nuclear Production) in the onsite organization having responsibi1ity for overall unit safe operation and having control over those onsite resources necessary for safe operation and maintenance of the plant.

d.

Although the individuals who train the operating staff and those who carry out health physics and quality assurance functions may,report to the appropriate management

onsite, they shall have sufficient l

organizational freedom to be independent from operating pressures.

6.2.2 UNIT STAFF a.

Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

PALO VERDE UNIT 3 6-1 Amendment No. 84,66

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ADMINISTRATIVE CONTROLS UNIT STAFF (Conti'nued) b.

C.

d.

e.

At least one licensed Reactor Operator s'hall be in the Control Room when fuel is in the reactor.

In addition, while the, reactor is in MODE 1, 2, 3, or 4, at least one licensed Senior Reactor Operator shall be in. the Control Room.

A radiation protection technician* shall be onsite when fuel's in the reactor.

All CORE ALTERATIONS shall be observed and directly supervised by.

either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

A site Fire Team of at least five members shall be maintained onsite at all times".

The Fire Team shall not include the Shift Supervisor, the STA, nor the 3 other membe> s of the minimum shift crew necessary.

for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.

6.2.2.1 The unit staff working hours shall be as follows:

a.

Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; e.g.,

Senior Reactor Operators, Reactor Operators, radiation protec-tion technicians, auxiliary operators, and key maintenance personnel.

The radiation protection technician and Fire Team composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to accommodate unexpected

absence, provided immediate action is taken to fillthe required positions.

PALO VERDE - UNIT 3 6-la AMENDMENT NO..M.

~ ~

ADMINISTRATIVECONTROLS UNIT STAFF (Continued) e shall be maintained without routine heavy 11 b t h

t' 1

k hil the 1 t i o

at' Ho he ob ective sha e

o 1

'4-o p

in the event that unforeseen pro ems require overt>me to be used, or d ng p

h 11 h

follo d (th

, d PVNGS Fire Department working hours):

excludes the STlh and PV ire 1

An individual should not be permitted to wor,k more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months

straight, excluding shift turnover time.

not be emitted to work more than l6 hours 2)

An individual should not b p

24-hour period, nor more t an

period, nor more t an o

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day period al excluding shift turnover time.

3)

A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months shou ld be allowed between work periods, 'including shift turnover time.

ed shutdown periods, the use of overtime 4)

Except dunng extende s >u should be considered on an indivi ua 'is entire staff on a shift.

ve uidelines squall be authorized by 1

v 1

b v o

their d n

personnel who are at the Director le>te or a o

1 b' 1 d d 'h d

i 'h s 'i o

h 11 b

tion.

Controls shal e inc such that sndivs o e

>me s

re w

mo thl b

these authorized in ivi ua s

assure that excessive hour s ave no deviation from

, e a ovr.

th b

'uidelines is not authonzed.

PALO VERDE UNIT 3 6-2 Amendment No. 8%,66

TABLE 6.2-1 HINIMUM SHIFT CREW COMPOSITION POSITION SS SRO RO AO STA NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION HODE1, 2, 3,0R4 HODE 5 OR 6 None 1I None SS

- Shift Supervisor with a Senior Reactor Operators License SRO - Individual with a Senior Reactor Operators License RO

- Individual with a Reactor Operators License

. AO - Nuclear Operator I or II STA - Shift Technical Advisor The Shift Crew Composition may be one less than the minimum requirements of Table 6.2-1 for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift 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 shift crew position to be

~manned upon shift change due to an oncoming shift crewman being late or absent.

During any absence of the Shift Supervisor from the Control Room while the unit is in MODE 1, 2, 3, or 4, an individual with a valid Senior Operator license shall be designated to assume the Control Room command function.

During any absence of the Shift Supervisor from the Control Room while the unit is in MODE 5 or 6, an individual with a valid Senior Operator or Operator license shall be designated to assume the Control Room command function.

PALO VERDE - UNIT 3 6-5

STRATIVE CONTROLS INDEPENDENT SAFETY ENGINEERING DFPARTI~IENT ISE

/

i.l The ISE Department shall /fu/ncfiop $o selectively examine plant

>ting characteristics, NRC issuances, ihduktdy advisories; Licensee Event

rts, and other sources of plant design and operating expeti'ienc rmation, including plants of isiiiliarideisign, which may indicath areas for oving plant safety.

POSITION

.3.2 The ISE Department shal'1 be, composed of at least five, dedicated, 1-time engineers located on site.

Each shal'1 have a Bachelor's Degree in

~ineering or related science and at least two years professi,onal level perience in his field.

SPONSIBILITIES

.2.3.3 Th ISE Department shkll/ be r/esponpible for maintaining survei'lllance F 'selected plant activities to provide hand'ependent verification* that these ctivities are performed correctly to reduce human errors as much as practical, nd to detect potential nuclear safety h/azards.

AUTHORITY 6.2.3.4 The ISE Department shall make detailed recommendations f'r revised p3 ocedures, equipment modificat;ions,.maintenance activities, operations activities or other means of-imProving plant safety to ti/ie Director, Site Operations, and the Chairman, Offditie Safety Review Committ'ee (OSRC).

RECORDS 6.2.3.5 R cords of activities performed, by ttie ISE Department sha'll be,

prepared, maintained, and forwarded each calendar month to the Director, Nuclear Assurance or designated alternate.

6.2. 4 SHIFT TECHNICAL ADVISO)

/

6.2.4.1 The Shift Technical Advisor (STA) shall provide hdvisory, technical support to the Shift Supervisor in the areas'of, thermal hydraulics, reactor engineering, and plant analysis'ith regard to the safe operation of the unit.

The STA shall be onsite and."hall be available in the control room withi~

10 minutes whenever one or more units are in NODE li P, Y, or 4.

6.3 UNIT STAFF VALIFICATIONS 6.3el Each member of the unit staff sha'll meet or exceed the, minimum qualifi-cations of ANSI/ANS 3.1-1978 and Regulatory Guide 1.8, September 1975, except for the Director, Site Radiation Protection who shall meet or exceed the qualifications of Regulatory Guide 1.8, September,'19)5, and the Shift 'liechnical Advisor who shall have a bachelor's degree or equivalent in a scientific or engi-'eering discipline with specific training in plant design arid plant operating

~ s w ~

Not responsible for sign-off function.

PALO VERDE UNIT 3 Amendment No. 3k, 66

ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF UALIFICATIONS (Continued) characteristics, including transients and is that the Senior Reactor Operator (SRO)

Operations Department Leader shall be met Leader or the Operations Supervisor holds the SRO license shall direct the licensed operators.

6.4 TRAINING accidents.

An additional exception license requirement for the if either the Operations Department a valid SRO license.

The holder of activities of the licensed 6.4.1 A training program for the unit staff shall be maintained under the direction of the Director, Nuclear Training and shall meet or exceed the requirements of Section 5.0 of ANSI/ANS 3. 1, 1978 and 10 CFR 55.

The program shall include familiarization with relevant industry operational experience.

6. 5 REVIEW AND AUDIT 6.5. I PLANT REVIEW BOARD PRB FUNCTION 6.5.1.1 The Plant Review Board shall.function to advise the Vice President Nuclear Production or his designee on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The PRB shal-1 be composed of at least seven members from the Palo.

Verde management staff.

These positions will be.designated by the Vice President Nuclear Production or his designee in Administrative Procedures.

The Vice President Nuclear Production or his designee shall designate the Chairman and designated alternate in writing.

The Chairman a::d designated.

alternate may be from outside the members provided that they meet ANSI/ANS 3.I, 1978.

.ALTERNATES 6.5.1.3 All alternate members shall be appointed, in writing by the PRB Chairman to serve on a temporary basis;

however, no more than two alternates shall participate as voting members, in PRB activities at any one time.

MEETING FRE UENCY 6.5.1.4 The PRB shall meet at least once,per calendar month and as convened by the PRB Chairman or designated alternate.

PALO VERDE UNIT 3 6-7 Amendment No. 8k,66

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4 ADMINISTRATIVE CONTROLS QUORUM 6.5.1.5 The quorum of the PRB necessary for the performance of the PRB responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or a desig'nated a'llternate and a majority of the members including alternates.

RESPONSIBILITIES 6.5.1.6 The PRB shall be responsible for:

a ~

b.

C.

d.

e.

AUTHORITY Review of a'll proposed changes to Appendix "A" 'l'echnical Specifications.

Investigation of all violations. of the Technical Specifications including the preparation and forwarding of reports covering evalua; tion and recommendations to prevent recurrence to the Offsite Safety Review Committee

{OSRC).

Review of REPORTABLE EVENTS.

Review of unit operations to detect potential nuc'lear safety hazards.

Performance of special reviews, investigations or analyses and reports thereon as requested by the Vice President-Nuclear Production or PRB chairman.

Review and documentation of judgment concerning prolonged operat~iorj in bypass, channel trip and/or repair. of defective protection channels of process variables p'laced in bypass'si'nce the last PRB meeting.

6.5.1e7 The PRB shall:

a ~

b.

RECORDS Render determinations in writing with s~egprd to whether or not each item considered under Spec,ification p.q. 1.6).

above constitutes, an, unreviewed safety question.

Provide written notification with'in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to-the Executive Vice President

Nuclear, V)ice President Nuclear Pi oduction and OSRC of disagreement between the PRB and the Vice President Nuclear Production; however, the Vice President Nuc'lear Production shalw have responsibility f'r resolution of such disagreements.

6.5.1e8 The PRB shall maintain written minutes of each PRB meeting that,, a4 a,

minimum, document the results of all PRB actiyitie>> performed under the responsibility and authority provisions of these Technical Specifications.

Copies shall be provided to the Executive Vicp prepid~ent Nuclear, Vice President Nuclear Production, and OSRC.

PALO VERDE - UNIT 3 Amendment No. Sk, 66

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ADMINISTRATIVE CONTROLS 6.5.2 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.2. 1 The Vice President Nuclear Production or his designee shall assure that each procedure and program required by Specification. 6.8 and other procedures which affect nuclear safety, and changes

thereto, is prepared by a qualified individual/organization.

Each such procedure, and changes

thereto, shall be reviewed by an individual/group other than the individual'/group which prepared the procedure, or changes

thereto, but who may be from the same organization as the individual/group which prepared the procedure, or changes thereto.

6.5.2.2

'Phase I IV tests described in the FSAR that are performed by the plant operations staff shall be approved by the Director, System Engineering or his designee as previously designated by the Vice President Nuclear Production.

Test results shall beapproved by the Director, System Engineering or his designee.

6.5.2.3 Proposed modifications to unit nuclear safety-related structures, systems and components shall be designed by a qualified individual/organization.

Each such modification shall be reviewed by an individual/group other than the individual/group which designed the modification, but who may be from the same organization. as the individual/group which designed the modification.

Proposed modifications to nuclear safety-related structures, systems and components shall be approved prior to implementation by the Department

Leader, Operations; or by the Director, Site Operations as previously designated by the Vice President Nuclear Production.

6.5.2.4 Individuals responsible for reviews performed in accordance with 6.5.2.1, 6.5.2.2, and 6.5.2.3 shall be identified in station, procedures.

Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary.

If deemed necessary, such review sha11 be performed by the appropriate designated review personnel.

6.5.2.5 Proposed tests and experiments which affect station nuclear safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by the Vice President Nuclear Production or his designee.

6.5.2.6 Not used.

6.5.2.7 Not used.

6.5.2.8 The Director, Site Radiation Protection shall assure the performance of a review by a qualified individual/organization of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering the evaluation, recommendations and disposition of the corrective action to prevent recurrence.

PALO VERDE UNIT 3 6-9 Amendment No. 34,66

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ADMINISTRATIVECONTROLS 6.5.3 OFFSITf SAFETY REVIEW COMMITTEE (OSRCQ FUNCTION 6.5.3.1 The.OSRC shall function to provide jnPepqndent review. and shall be responsible for the audit of desiginated activities in the areas af:

a 0 b.

C.

d.

.e.f.

9 ~

h.

nuclear powei plant.operations nuclear engineering chemistry and radiochemistry metallurgy instrumentation and c~)ntro11 radiological safety, mechanical andi electrical engineerIing quality assurance practice.

COMPOSITION 6.5.3.2 The;-OSRC,;hall be.composed of,the OSRC Chairman-and a minimum of four OSRC members.

The Chairman and members are deSignated by the Executive Vice President, Nuclear and shall have the qualifications that meet the requirements of Section 4.7 of ANSI/ANI 3.1;l 1/78.

CONSULTANTS 6.5.3.3 Co'nsultants shill be utilized as determi,ned by the OSRC,.Chairman to provide expert. advice to the OSRC.

REVIEW 6.5.3.4 The OSRC shall review:

a ~

The safety ev'aluations program and,:its,impleinentation for (I) changes to procedures, equipment, systems or facilities withjin, the power b'lock, a'nd (2)'tests or exper'iments completed under thy provision of 10 CFR 5O.59, to verify,that such actions did not constitute an unreviewed. safety question; PALO VERDE UNIT 3 6-10 Amendment No.

R,66

ADMINISTRATIVECONTROLS 6.7 SAFETY LIMIT VIOLATION The following actions shall be taken in the event a Safety Limit is violated:

a.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within I hour.

The Vice President Nuclear Production, Director, Site Operations and Chairman of the OSRC shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

A Safety 'Limit Violation Report shall be prepared.

The report shall be reviewed by the PRB.

This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components,

systems, or structures, and (3) corrective action taken to -prevent recurrence.

c.

The Safety Limit Violation Report shall be submitted to the

'Commission, the Chairman of the OSRC and the Vice President Nuclear Production within 30 days of the violati'on.

d.

Critical operation of the unit shall not be resumed until authorized

. by the Commission.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Mritten procedures shall be established, impleme'n'ted, and maintained covering the activities referenced below:

a.

The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February

1978, and those required for implementing the.requirements of NUREG-0737.

b.

Refueling operations.

c.

Surveillance and test activities of safety-related equipment.

d.

Not used.

e.

Not used.

f.

Fire Protection Program implementation.

g.

Modification of Core Protection Calculator (CPC) Addressable Constants These procedures should include provisions to ensure that sufficient margin is maintained in CPC Type I Addressable Constants to avoid. excessive operator interaction with the CPCs during reactor operation.

NOTES:

(I) Modification to the CPC Addressable Constants based on information obtained through the Plant Computer CPC data link shall not be made without prior approval of the PRB.

(2) Modifications to the CPC software (including algorithm changes and changes in fuel cycle specific data), shall be performed in accordance with the most recent version of CEN-39(A)-P, "CPC Protection Algorithm Software Change Procedure," that has been determined to be applicable to the facility.

Additions or deletions to CPC Addressable Constants or changes to Addressable Constant software limit values shall not be implemented without prior NRC approval.

PALO VERDE UNIT 3 6-13 Amendment No.

66

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAM'~SContinu~~!d h.

PROCESS

.CONTROL PROGRAM implementation.

i.

OFFSITE DOSE CALCULATION MANUAL implementatior>.

j.

Quality Assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 1,.21, Revision I, June 1974 and Regulatory Guide 4,.1, Revision

~Api il~ 1975,.

k.

Pre-planned Alternate Sampling Program implementation.

1.

Secondary water chemistry program ijnpl,empntation.

NOTE:

The licensee shall perform a, secondary water chemistry monitoring pnP control program that is in conformance with'he priogr am discussed in Section 10.3.4.1 of the CESSAR FSAR or another NRC approved program.

m.

Post-'Accident 'Sampling System implementaticpn.',~

n.

Settlement Monitoring Program implementation.

NOTE:

The licensee shall ma'intain a settlement monitoring program throughout the life of the plant in accordance with the program presented in Table 2.5-18 of the PVNGS FSAR or another NRC approved program.

o.

CEA Reactivity Integrity Program implementation NOTE:

The licensee shall perform, after initial fuel load or after each reload, either a

CEA symnetry test or worth rica,surements of alll full-length CEA groups to address Section 4.2.2 of the PVNGS SER dated November ll, j98$.

p.

Fuel Assemb1y Surveillance Program Implqmeptytiqn, NOTE:

The licensee shal'1 perform a fue1I assembly surveillance program in conformance with the program discussed in Section 4.2.4 of the PVNGS S'ER da)edl November ll, 1981.

6.8.2 Each program or procedure of Specification 6.8.1, and changes

thereto, shall be reviewed as specified in Specification 6.5 and approved prior to implementation.

Programs, administrative control procedures and im'plemeptipg procedures shall be approved by the Vice President,-Nuclear Production, or~

designated alternate who is at, super'visory level or above Programs and procedures of Specification 6,8.I shall be reviewed periodically as set f~'orth, in administrative procedures.

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

a.

The intent of the original procedure. is not altered.

b.

The change is approved by two members of the plant supervisory staff, at least one of whom is a Shift Supervisor or Conti ol Room-Supervisor with an SRO on the affected unit.

c.

The change is documented, reviewed in ac;cordance with Specification 6.5.2 and approved by the cognizant department

head, as designated by the Vice President-Nuclear Productior), within 14 days of implementation.

Not required until prior to exceeding 5X of RATEl) THERMAL POMER.

PALO VERDE - UNIT 3 6-14 Amendment No. %.,66

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ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS.,Continued 6.8.4 The following programs shall be established, implemented, maintained, and shall be audited under the cognizance of the OSRC at least once per 24 months:

a 0 Primar Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain, highly radioactive fluids during a

serious transient or accident to as low as practical levels.

The systems include the recirculation portion of the high pressure safety injection system, the shutdown cooling portion of the low pressure safety injection system, the post-accident sampling subsystem of the reactor coolant sampling

system, the containment spray system, the post-accident sample return piping of the radioactive waste gas

system, the post-accident sampling return piping of the liquid radwaste

system, and the post-accident containment atmosphere sampling piping of the hydrogen monitoring subsystem.

The program shall include the following:

(I)

Preventive maintenance and periodic visual inspection requirements, and (2)

Integrated leak test requirements for each system at refueling cycle intervals or less.

b.

In-Plant:Radiation Monitorin C.

A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions.

This program shall include the following:

(I)

Training of personnel, (2)

Procedures for monitoring, and (3)

Provisions for maintenance of sampling and analysis equipment.

Secondar Water Chemistr A program.for monitoring of secondary water chemistry to inhibit steam generator tube degradation.

This program shall include:

(I)

Identification of a sampling schedule for the critical variables and control points for these variables, (2)

Identification of the procedures used to measure the values of the criti'cal variables, (3)

Identification of,process sampling points,, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in-leakage, (4)

.Procedures for the recording and management of data, PALO VERDE UNIT 3 6-15 Amendment No. 66

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js sr ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continuie~d (5)

Procedures defining corrective actions for all off"control point chemistry conditions, anId (6)

A procedure identifying (a) thy gut)ority responsib1e for,th) interpretation of the data, an) (Ib) the sequer>ce and timing of administrative events required to initiate corrective action.'.

~Backu Fiethod iFor Determinin Subco l n

liar in A program which wil'I ensure the capability,to accurately monitor /he, Reactor Coolant System, subcooling margin.

This program shal'l include the following:

(1)

Training of personnel, and (2)

Procedures f'r monitoring.

e.

Post-Accident San~)l ~in A program which will ensure the capability to obtain and analyze reactor

coolant, radioactive i'odines and particulates in plant, gaseous effluents, and containment atmosphere samples under

accident, conditions.

The program shall include the following:

(1)

Training of',personnel, (2)

Procedures for sampling and analysis, (3)

Provisions f'r maintenance of sampling and analysis equioment.

f.

S ra Pond Monitorin A program which will identify and describe the parameters and activities used to control and monitor the Essential Spray Pong and, Piping.

The program sha')1 be conducted in accordance with stagiop manual procedures.

g.

Radioactive Effluent Controls ~Pro ram A program shall be provided conforming with 10 CFR 50.36a for the, control'f radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achiievablee

'The program ($),shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remediial actions to Pe Itagen, whenever the program limits are exceeded.

The program shall include the following elements:

AMENDMENT NO. 34 (1)

Limitations on the operability qf paPioactive liquid and, gaseous monitori,ng in. trumentation, including'surveillance te~sts and setpoint determination in, accordance with the methodology, in the

ODCM, PALO VERDE - UNIT 3 6-16

(

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ADM IN ISTRATIVE CONTROLS PROCEDURES AND PROGRAMS Continued (2)

(3)

(4)

(5)

(6)

(7)

(8)

(9)

(10)

Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part,20, Appendix B, Table 11, Column 2, Monitoring, sampling, and analysis;of radioactive liquid and gaseous effluents in accordance with 10 CFR 20. 106 and with the methodology and parameters in the

ODCM, Limitations on the annual and quarterly doses or dose commitment to a MEHBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to. Appendix I to. 10 CFR Part 50, Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters

.in the ODCM at least every 31 days.

Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions.of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed,2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50,

.Limitations on the dose rate 'resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B, Table II, Column 1, Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides. in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and. to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

PALO VERDE UNIT 3 6-17 Amendment No. 34,66

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ADMINISTRATIVE CONTROLS

~Ri II:I IR~i,i I>>

A program shall be provided to monit~or the rad'iation and radionuclides in 'the environs of t;he plant.

The program shall provide (1) reprensentative measurements of radioactivity in the, highest potent,ial exposure pathways,, and (2) verification of the accuracy of the effluent monitoring program,and modeling of environmental exposure pathways.

The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 1O

CFR, Part 20, and i(3) include the following:

(1)

Monitoring, sampling, analysis, and'eporting of radiation and radionuclicles in the environment in accordance with the methoclology and parameters in the ODCM.

(2)

A Land Use Census to ensure that changes in the use of areas at and beyond the SITI. BOUNDARY:are identified and that, modifications to the monitoring program are made if required by the results of t.his census, and (3)

Participation in a Inter laboratory Comparison Program to ensure that independent.

checks on the precision and accuracy of the measuremients iof radioactive isaterials iin environmental sampl matrices are. performed as part of the quality assurance program for environmental monitoring.

I I

IP "lE".

I'OUTINE REPORTS 6.9. 1 In addition to the applicable reporting requirements of Tit'fe 10,,

Code of Federal Regulations, the 'following reports shall be. submitted to the RegiOnal Administrator of the Regional Office of the NRC unless otherwise noted.

STARTUP REPORT 6.9. 1. 1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating

license, (l ) amendment to the license involving a planned increase in power level, (3) installation of i

fuel that has a differ'ent design or has been manufactured by a different fuel

supplier, and (4) modlif'ications that may have significantly altered the nuclear, thermal, or hydraulic perf'ormance of the plant.

PALO YERDE - UNIT 3 6-18, AMENDMENT N0.34

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~ I ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional.Offi'ce of the NRC within the time.period specified for each report.

6.9.3 Violations of the requirements of the fire protection program described in the Final Safety Analysis Report which would have adversely affected the ability to achieve and maintain safe shutdown in the event of a fire shall be reported in accordance with 10 CFR 50.,73.

6. 10 RECORD RETENTION In addition to the applicable record retention requirements of Ti,tie 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6. 10. 1 The following records shall be retained for at least 5 years:

a.

Records and logs of unit operation covering time interval at each power level.

b.

Records and logs of.principal maintenance activities, inspections, repair and replacement of principal i'tems of equipment related to nuclear safety.

c.

All REPORTABLE EVENTS submitted to the Commission.

d.

Records of surveillance activities; inspections and calibrations required by these Technical Specifications.

e.

Records of changes made to the procedures of Specification 6.8.1.

f.

Records of radioactive shipments.

g.

Records of sealed source and fission detector leak tests and results.

h.

Records of annual physical inventory of all sealed source material of record.

6. 10.2 The following records shall be retained for the duration of the unit Operating 'License:

a.

Records and drawing changes reflecting unit design modificati'ons made to systems and equipment described in the FSAR.

b.

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

c.

Records of radiation exposure for all individuals entering radiation control areas.

d.

Records of gaseous and liquid radioactive material released beyond the SITE BOUNDARY.

e.

Records of transient or operational cycles for those unit components identified in Tables

5. 7-1 and 5. 7-2.

f.

Records of reactor tests and experiments.

g.

Records of training and qualification for current members of the unit staff.

h.

Records of inservice inspections performed pursuant to these Technical Specifications.

PALO VERDE - UNIT 3 6-21 AMENDMENT NO. 34

ADMINISTRATIVE CONTROLS P

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RECORD RETENTION (Continued) i.

Records of quality assurance activities 'required by the QA Manual not listed in Section 6.10.1.

j.

Records of reviews performed for changes made to procedures or equipment or review.'f tests and experiments pursuant to 10 CFR 50.59.

k.

Records of PRB meet.ings and of OSRC activities.

1.

Records of t:he service lives of all hydraulic and mechanical snubbers required b!y Specification 3.7.9 including the date at,which the service life commences and associated

'installation

and, maintenance records.

m.

Records of audits performed under the requirements -of Specificaitions 6.5.3.5 and 6.8.4.

n.

Records.of analyses required by the radiological environmental moni-toring program that w'ould permit eval,uat;ion of thy accuracy of the analysis at a later date.

This shqulg inc',lude procedures effective, at specif'ied times and gA records showing that these procedures were followed.

o.

Meteorological data, summarized an) rqpqrted in a format consi.tent with the recommendations of Regula):ory Guides 1.21 and 1.23.

p.

Records of secondary water sampling and water quality.

q.

Records of reviews performed for changes made to the OFFSITE

DOSE, CALCULATION MANUAI. and the PROCESSiCOQTQOLi PROGRAM.

6.11 RADIATION PROTECTION PRQGMM 6.11.1 Procedures for per onnel radiation protection shall be. prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained, and adhered to for ahull operations invqlving personnel radiation exposure.

PALO VERDE - UNIT 3 6-22 Amendment No. 34, 66

ADMINISTRATIVE CONTROLS 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 Part 20, each high radiation area in which the intensity of radiation is greater than 100 mrem/hr but less than 1000 mrem/hr shall be barricaded and conspicuously posted as: a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Exposure Permit (REP)*.

Any individual or group of individuals permitted to enter such areas shall. be provided with or accompanied by one or more of the following:

a.

A radiation monitoring device which continuously indi'cates the radiation dose rate in the area.

b.

A radiation monitoring device wh'ich continuously integrates

.the radiation dose rate in the area and alarms when a preset integrated dose is received.

Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.

c.

A radiation protection qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Radiation Protection Section Leader or his designated alternate in the REP.

6.12.2 In addition to the requirements of Specification 6. 12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in I hour a dose greater than 1000 mrem shall be provided with locked doors to prevent unauthorized

entry, and the keys shall be main-tained under the administrative control of the Shift Supervisor on duty and/or radiation protecti'on supervision.

Doors shall remain locked except during periods of access by personnel under an approved REP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area.

For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in I hour a dose in excess of 1000 mrems**, that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device.

In lieu of the stay time specification of the REP, direct or remote '(such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.

Radiation Protection personnel or personnel escorted by Radiation Protection personnel shall'e exempt from the REP issuance requirement during the performance of their assigned radiation protection duties, provided they are otherwise following plant radiation protection procedures for entry into high radiation areas.

- Measurement made at 18 inches from source of radioactivity.

PALO VERDE UNIT 3 6-23 Amendment No. 34,66

ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM ~PCS Changes to the PCP:

a.

Shall be documented and records of reviews,performed shall be retained as required by Specification,'. 10<2.,'q.

This documentat9)n shall contain:

{1)

Sufficient information to support the change together with the appropriate analyses or evaluations justifging the change(s) and

{2)

A determination that the ci'Iange will maintain the overall conformance of'l>e solidified wasteth product to existing requirements of Federal,

State, or ot'her applicable regulations.

b.

Shall become effective after review hand, acceptance by the PRB and the approval.of the Director, Site Rqdi'at[on'rotection.

Changes to the ODCM:

a.

Shall be documented and records of reviews performed shall be retained a.

required by Specificatioh 6.10.2.q.

This documentation shall'ontain:

{1)

Sufficient information to support the change together with the appropriate ana1lyses or evaluations justifying the change{s) and

{2)

A determination that the change. will maintain the level of

.radioactive effluent control required by 10 CFR 20.106, 40 CFR Part

190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 pnd, not adversely impact the accuracy or reliab'ility of effluent,

dose, or setpoint calculations.

b.

ShalI become effective after review an) ~cchptance by the PRB arid, the approval of the Director, gite hepiietry.

c; Shall be submitted to the Comm'issior> ip the form of a complete, legible copy of the entire ODCM as part qf 'or, concurrent with the Annual Radioactive Eff1luent Re'lease Report for'he period of the report in which any change to the OIiCH was made.

Each change shall be identified by markings in the mapgi~n qf 'the affected pages,,

clearly indicating the area of the page tha't was changed, and shall indicate the date (e.g.,

month/year) the change was implemented.

6.15 MAJOR CHANGES TO fNDIQACTI'/E LIgUID GASEOUS'ND SOLID MASlE 'TREATMENT, SYSTEMS*

6.15.1 Licensee-initiated ma.ior changes to the radioactive waste systems (liquid, gaseous, and so'liid):

Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the eva'luation,was~

reviewed by the PRB.

The discussiqn pf each change

. hall contqin,'.

~

f a

v

,i ea "Licensees may chose to submit the information called for in this specification as part of the annual FSAR updat'e.,'ALO VERDE - UNIT 3 6-24 Amendment No. 34-,34-,LiR, 66

ML17311B056

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