ML17300A655

Proposed Tech Specs Re Semiannual Radioactive Effluent Release Repts,Special Repts,Record Retention & Fire Protection Program.Fsar Pages Encl

ML17300A655
Person / Time
Site:	Palo Verde
Issue date:	12/02/1986
From:	ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
Shared Package
ML17300A654	List: ML17300A653 ML17300A655
References
TAC-62008, NUDOCS 8612100451
Download: ML17300A655 (8)

Text

ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued)

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

f. Solidification agent or absorbent (e.g., cement, urea formaldehyde).

The Semiannual Radioactive, Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radio-active materials in gaseous and liquid effluents made during the reporting period.

The Semiannual Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM and to the OFFSITE DOSE CALCULATION MANUAL, as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 3. 12.2.

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.

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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.

Records of radioactive shipments.

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

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

.PALO VERDE " UNIT 1 6-20 86 '100451 861202 I PDR 4DOCK 05000528 p PDR

ADMINI STRATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued)

The Semiannual Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and, other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with .40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regula-tory Guide 1.109, Rev. 1, October 1977.

The Semiannual Radioactive Effluent Release Reports shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report period:

a. Container volume,

b. Total curie quantity (specify whether determined by measurement or estimate),

c. Principal radionuclides (specify whether, determined by measurement or estimate),

d. Source of waste and processing employed (e. g., dewatered spent resin, compacted dry waste, evaporator bottoms),

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

f. Solidification agent or absorbent (e.g., cement, urea formaldehyde).

The Semiannual Radioactive Effluent Release Reports shall include a list and.

description of unplanned releases from the site to UNRESTRICTED AREAS of radio-active materials in gaseous and liquid effluents made during the reporting perl od.

The Semiannual Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM and to the OFFSITE DOSE CALCULATION.MANUAL, as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 3.12.2.

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.

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

PALO VERDE - .UNIT 2 6-20

Insert B 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 <'.l>>;".',

ability to achieve and maintain safe shutdown in the event of a fire shall be reported in accordance with 10CFR50.73.

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(6) Environmental (}uglification (Section 3.11, SSER 7 and SSER 8)

Prior to November 30, 1985, APS shall-environmentally qualify all electr ical equipment according to the provisions of 10 CFR 50.49.

(7) Fire Protection Program (Section 9.5.1, SSER 6, SSER 7, and SSER 8)

(a) APS shall maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility through Amendment No. 14, and as provided in the SER through Supplement 8, subject to provisions (b) 5 (c) below.

(b) APS may make no change in features of the approved fire protection program which would decrease the level of fire protection in the plant without prior approval of the Commission. To make such a change APS must submit an application for license amendment pursuant to 10 CFR 50.90.

(c) APS may make changes to features of the approved fire protection program which do not decrease the level of fire protection without prior Commission approval, provided:

(i) such changes do not otherwise involve a change in a license condition or technical specification or result in an unreviewed safety ouestion (see 10 CFR 50.59), and (ii) such changes do not result in failure to carry out the fire protection program approved by the Commission prior to license issuance.

APS shall maintain, in an auditable form, a current record of al,l such changes including an analysis of the effects of

the change on the fire protection program and shall make such,, records a a;;lable to NRC inspector-; tpor request.. Al'i changes to the approved program made without ~rior Commiss.ion approval shall be reported annually to the Director of the Office of Nuclear Reactor Regulation, together with supporting analyses.

(8) Emerqency Preparedness In the event that the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Management Agency's fina)-- rule, 44 CFR Part 350, is an indication that a major substantive problem exists in achieving or maintaining an adequate state of preparedness, the provisions of 10 CFR Section 50.54(s){2) will apply.

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APS shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility, as supple-mented and amended, and as approved in the SER through Supplement 8, subject to the following provision:

APS may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

PVNGS FSAR PLANT PROCEDURES H. Station Security Procedures Station security procedures provide f or the implementa-tron of the Security Plan (refer to section 13.6).

Fire Protection Procedures Fire protection procedures are provided to instruct applicable station personnel in methods of fire prevention. fire fighting. and maintenance of fire protection equipment. Procedures provide specific instructions to members of the'ir t xn fire ire team fighting techniques.

In addition to the above, limiting conditions for operation, action statements and surveillance requirements for the Fire Protecion program will be established within PVNGS Station Manual. This will provide an equivalent level of protection as described in the following sections of the Combustion Engineering Standard Technical Specifications:

Section 3/4.3 - Instrumentation Specification 3.3.3.7 - Fire Detection Instrumentation (limiting conditions of operation, surveillance requirements)

Section 3/4.7 - Plant Systems Specification,'..3 7:11.1- Fire Suppression Mater System (limiting conditions of operation, surveillance requirements)

Specification 3.7.11.2 - Spray and/or Sprinkler System (limiting conditions of operation, surveillance requirements)

Specification 3.7.11.3 - C02 Systems (limiting conditions of operation, surveillance requirements)

Specification 3.7.11.4 - Fire Hose Station (limiting conditions of operation, surveillance requirements)

Specification 3.7.11.5 - Yard Fire Hydrant and Hydrant Hose Houses (limiting conditions of operation, surveillance requirements)

Specification 3.7.11.6 - Halon Systems (limiting conditions of operation, surveillance requirements)

Specification 3.7.12 - Fire Rated Assemblies (limiting conditions of operation, surveillance requirements)

February 1985 13.5-9 Amendment 14