ML031820583

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Tech Spec Pages for License Amendments 146, 146 & 146 on Elimination of Plant Organization Positions
ML031820583
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 06/26/2003
From:
NRC/NRR/DLPM/LPD4
To:
Donohew J N, NRR/DLPM,415-1307
Shared Package
ML031820386 List:
References
TAC MB8458, TAC MB8459, TAC MB8460
Download: ML031820583 (4)


Text

SLs 2.0 2.0 SAFETY LIMITS MS~s) 2.1 Sts 2.1.1 Reactor Core SLs 2.1.1.1 In MODES 1 and 2. Departure from Nucleate Boiling Ratio (DNBR) shall be maintained as follows:

2 1.3 (through operating cycle 10) 2 1.34 (operating cycle 11 and later) 2.1.1.2 In MODES 1 and 2. the peak fuel centerline temperature shall be maintained < 50800 F (decreasing by 580F per 10.000 MWD/MTU for burnup and adjusting for burnable poisons per CENPD-382-P-A).

2.1.2 Reactor Coolant System (RCS) Pressure SL In MODES 1. 2. 3. 4. and 5. the RCS pressure shall be maintained at £ 2750 psia.

2.2 SL Violations 2.2.1 If SL 2.1.1.1 or SL 2.1.1.2 is violated. restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2.2.2 If SL 2.1.2 is violated:

2.2.2.1 In MODE 1 or 2. restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2.2.2.2 In MODE 3. 4. or 5. restore compliance within 5 minutes.

2.2.3 Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. notify the NRC Operations Center. In accordance with 10 CFR 50.72.

2.2.4 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the Director, Operations and the Senior Vice President. Nuclear.

(continued)

PAOVREUNT .. 2.0- AMNMN. ND . 4 PALO VERDE UNITS 1.2.3 2.0-1 AMENDMENT NO. U& 146

SLs 2.0 2.0 SLs 2.2 SL Violations (continued) 2.2.5 Within 30 days of the violation. a Licensee Event Report (LER)

I shall be prepared pursuant to 10 CFR 50.73. The LER shall be submitted to the NRC and the Director. Operations and the Senior Vice President. Nuclear. I 2.2.6 Oeration of the unit shall not be resumed until authorized by the NRC.

AMENDMENT NO.

1 7 T

3 3 146 2.0-2 UNITS 1,2,3 VERDE UNITS PALO VERDE 1,2,3 2.0-2 AMENDMENT NO. 447T433 146

Org ani zati on 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations Onsite and oftsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant.

a. Lines of authority. responsibility, and communication shall be defined and established throughout highest management levels. intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, inorganization charts. functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or Inequivalent forms of documentation. These requirements shall be documented in the UFSAR:
b. The Senior Vice President. Nuclear shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant:
c. The Senior Vice President. Nuclear shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff inoperating. maintaining, and providing technical support to the plant to ensure nuclear safety: and
d. The individuals who train the operating staff. carry out health physics, or perform quality assurance functions may report to the a ropriate onsite manager: however, these individuals shal have sufficient organizational freedom to ensure their independence from operating pressures.

5.2.2 Unit Staff The unit staff organization shall include the following:

a. A non-licensed operator shall be assigned to each reactor containing fuel and an additional non-licensed operator (continuedf-PALO VERDE UNITS 1.2,3 5.2-1 AMENDMENT NO. M 146

Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The follownrg programs shall be established. implemented, and maintained.

5.5.1 Offsite Dose Calculation Manual (OCM)

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 activities and descriptions of the information that should be included in the Annual Radiological Environmental Operating, and Radioactive Effluent Release Reports required by Specification 5.6.2 and Specification 5.6.3.

Licensee initiated changes to the O0CM:

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).
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 the approval of the Director.

Radiation Protection; and

c. Shall be submitted to the NRC in the form of a complete.

legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made.

Each change shall be identified by markings in the margin of

. : . . -. n

_ - (continued)

PALO VERDE UNITS 1.2,3 5.5-1 AMENDMENT NO. 420 146