ML041170165

Technical Specifications, Approve Administrative Procedures and Offsite Dose Calculation Manual

ML041170165
Person / Time
Site:	Perry
Issue date:	04/23/2004
From:	Office of Nuclear Reactor Regulation
To:
Sands S, 415-3154, NRR/DLPM
Shared Package
ML041170317	List: ML040340317 ML041170165
References
TAC MB7518
Download: ML041170165 (4)

Text

Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The plant manager shall be responsible for overall unit operation

- and shall delegate in writing the succession to this responsibility during his absence.

The plant manager, or his designee, shall approve. prior to implementation. each proposed test, experiment, or modification to systems or equipment that affect nuclear safety.

5.1.2 The shift supervisor (SS) shall be responsible for the control room command function. During any absence of the SS from the control room while the unit is in MODE 1. 2. or 3. an individual with an active Senior Reactor Operator (SRO) license shall be designated to assume the control room command function. During any absence of the SS from the control room while the unit is in MODE 4 or 5. an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function.

PERRY - UNIT 1 5.0-1 Amendment No. 129

Procedures 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Procedures 5.4.1 Scope Written procedures/instructions shall be established. implemented, and maintained covering the following activities:

a. The applicable procedures recommended in Regulatory Guide 1.33. Revision 2. Appendix A. February 1978;

b. The emergency operating procedures required to implement the requirements of NUREG-0737 and NUREG-0737, Supplement 1:

c. Quality assurance for effluent and environmental monitoring:

and

d. All programs specified in Specification 5.5.

5.4.2 Responsibility The above procedures will be approved by procedurally authorized individuals.

PERRY - UNIT 1 5.0-5 Amendment No. 129

Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs and manuals shall be established. implemented. and maintained.

5.5.1 Offsite Dose Calculation Manual (ODCM)

a. The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints. and in the conduct of the radiological environmental monitoring program; and

b. The ODCM shall also contain the radioactive effluent controls and radiological environmental monitoring programs.

and descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release reports.

Licensee initiated changes to the ODCM:

a. Shall be documented and records of reviews performed shall

.be retained. This documentation shall contain:

1. sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s). and

2. a determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302. 40 CFR 190. 10 CFR 50.36a, and 10 CFR 50, Appendix I. and not adversely impact the accuracy or reliability of effluent. dose, or setpoint calculations:

b. Shall become effective after review and acceptance including approval by the procedurally authorized individual: and (continued)

PERRY - UNIT 1 5.0-6 Amendment No.129

D. FENOC is exempted from: 1)the requirements of Section IlI.D.2(b)(ii), containment airlock testing requirements, Appendix J to 10 CFR Part 50, due to the special

. circumstance described in Section 6.2.6 of SER Supplement No. 7 authorized by 10 CFR 50.12(a)(2)(iii) and 2) the requirements of Section IV.F., Full Participation Exercise, of Appendix E to 10 CFR Part 50, due to the special circumstance described in the Exemption dated November 6, 1986. These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. The exemptions are hereby granted pursuant to 10 CFR 50.12. With the granting of these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.

E. FENOC shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans, including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Perry Nuclear Power Plant Physical Security Plan," with revisions submitted through September 11, 1987; "Perry Nuclear Power Plant Guard Training and Qualification Plan,"

with revisions submitted through August 12, 1986; and "Perry Nuclear Power Plant Safeguards Contingency Plan" (Chapter 8 of the Security Plan), with revisions submitted through May 15, 1986. Changes made In accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

F. Except for Section 2.C.(2), FENOC shall report any violations of the requirements contained in Section 2.C of this license in the following manner Initial notification shall be made within 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> to the NRC Operations Center via the Emergency Notification System with written followup in accordance with the procedures described In 10 CFR 50.73(a)(1), (b), (c), and (e).

G. The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

Amendment No. 129