ML14175A840
| ML14175A840 | |
| Person / Time | |
|---|---|
| Site: | Robinson  (DPR-23-A-085-ER, DPR-23-A-85-ER) |
| Issue date: | 11/14/1984 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML14175A841 | List: |
| References | |
| NUDOCS 8411280597 | |
| Download: ML14175A840 (7) | |
Text
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 85 FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 Revise Appendix A as follows:
Remove Pages Insert Pages i thru vi (Table of Contents) i thru vii (Table of Contents) 1-3 thru 1-4 1-3 thru 1-8 3.5-1 thru 3.5.14 3.5-1 thru 3.5-30
.3.9-1 thru 3.9-4 3.9-1 thru 3.9-11 3.16-1 thru 3.16-8 3.17-1 thru 3.17-13 4.1-5 4.1-5 4.10-1 thru 4.10-3 4.10-1 thru 4.10-10 4.19-1 thru 4.19-7 4.20-1 thru 4.20-4 4.21-1 thru 4.21-2 6.5.1 6.5.1 6.5.1a 6.5.1a 6.5.7 6.5.7 6.5.7a 6.5.7a 6.5.14 6.5.14 6.5.15 6.5.15 6.9-3 thru 6.9-9 6.9-3 thru 6.9-16 6.10-2
- 6.
10-2 6.14-1 6.14-1 6.15-1 6.16-1 6.17-1 thru 6.17-2 8411280597 841114 PDR ADOCK 05000261 PDR Amendment No. 85
TABLE 3.5-2 (Cont'd)
REACTOR TRIP INSTRUMENTATION LIMITING OPERATING CONDITIONS 1
2 3
MINIMUM OPERATOR ACTION.
MINIMJM DEGREE IF CONULTIONS OF OPERABLE OF COUJMN I OR 2 NO.
FUNCTIONAL UNIT CHANNELS REDUNDANCY CANNOT BE MET
- 12.
Lo Lo Steam Generator 2
1 Maintatn Hot Water Level Shutdown
- 13.
Underfrequency 4 KV System 2
1 Maintain Hot
- 14.
Undervoltage on 4 KV System 2
1 Maintain Hot Shutdown
- 15.
Control Rod Misalignment Monitor****
- a. Rod Position Deviation 1
0 Log individual rod position once/hour, and after a load change >10% or after >30 inches of control rod motion
- b. Quadrant Power Tilt 1
0 Log individual upper Monitor (upper and and lower ion cham lower ex-core neutron ber currents once!
detectors) hour and after a load change >10% or after
>30 inches of contro' rod motion M
- 16.
Steam Flow/Feedwater Flow 1
0 Maintain Hot rt Mismatch Shutdown
- 17.
Low Steam Generator 1
0 Maintain Hot Water Level Shutdown Oo
- For zero power physics testing, it is permissible to take one channel out of service.
- When two of four power channels are greater than 10% full power, hot shutdown is not required.
When one of two intermediate range channels is greater than IE-10 amps, hot shutdown is not required.
- if both rod misalignment monitors (a and b) are inoperable for two hours or more, the nuclear overpower trip shall be reset to 93 percent of rated power in addition to the increased surveillance noted..
R.P. = Rated Power
TABLE 4.1-1 (Continued)
Channel Description Check Calibrate Test Remarks
- 9.
Analog Rod Position S (1,2)
R M
(1) With step counters (2) Following rod motion in excess of six inches when the computer is out of service
- 10.
Rod Position Bank Counters S (1,2)
N.A.
N.A.
(1) Following rod motion in ex cess of six inches when the computer is out of service (2) With analog rod position
- 11.
Steam Generator Level S
R M
- 12.
Charging Flow N.A.
R N.A.
- 13.
Residual Heat Removal Pump Flow N.A.
R N.A.
- 14.
Boric Acid Tank Level D (1)
R N.A.
(1) Bubbler tube rodded weekly
- 15.
Refueling Water Storage W
R N.A.
Tank Level
- 16.
Boron Injection Tank Level W
R N.A.
- 17.
Volume Control Tank Level N.A.
R N.A.
- 18.
Containment Pressure D
R B/W (1)
(1) Containment isolation valve signal o
- 19.
Deleted by Amendment No. 85
- 20.
Boric Acid Makeup Flow Channel N.A.
R N.A.
.* S TABLE 4.10-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Type of Sampling Minimum Analysis Required Activity Required LLDa Release Frequency Frequency Analysis i Ci/mi Batch Waste P
P Principal Gamma 5E-07 Releasesb Grab Sample on Grab Sample Emittersc
- 0.
Monitor Tanks 1-131 1E-06
- 2.
Waste Conden sate Tanks P
M Dissolved and 1E-05
- 3. Drainage of Grab Sample on Grab Sample Entrained Gases Systems One Batch/M (gamma emitters)
P M
Tritium IE-05 Grab Sample on Composite Each Batch d
and Composited Gross Alpha 1E-07 P
'Grab Sample on Composite Each Batch and Composited Fe-55 IE-6 Continuous D
W Principal gamma 5E-07 Releasese Grab Sample on Grab Sample Emitters
- 11. Steam I
Generator Blowdown 1-131 1E-06 M
l M
Dissolved and IE-05 Grab Sample on Grab Sample Entrained Gases (gamma emitters)
D M
Tritium 1E-05 Grab Sample on Composite and Compositedd~
Gross Alpha 1E-07 D
Q Sr-89, Sr-90 5E-08 Grab Sample on Composite and Compositedd,f Fe-55 1E-6 4.10-5 Amendment No. 85
6.5.1.6.7, In the event of disagreement between the recommendations of the Plant Nuclear Safety Committee and the actions contemplated by the General Manager, the course determined by the General Manager to be more conservative will be followed. The Manager -
Robinson Nuclear Project and the Manager - Corporate Nuclear Safety will be notified within the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the disagreement and subsequent actions.
6.5.1.6.8 The PNSC shall maintain written minutes of each meeting that, at a minimum, document the results of all PNSC activities performed under the provisions of these Technical Specifications; and copies shall be provided to the Manager -
Robinson Nuclear Project and to the Manager -
Corporate Nuclear Safety.
6.5-7a Amendment No. 85
(4) The verification of compliance and implementation of the requirements of the Quality Assurance Program to meet the criteria of Appeddix B, 10CFR5O, at least once per 24 months.
(5) The Emergency Plan and implementing procedures at least once per 12 months.
(6) The Security Plan and implementing procedures at least once per 12 months.
(7) The Facility Fire Protection Program and implementing procedures at least once per 24 months.
(8)
Any other area of facility operation considered appropriate by the Corporate Quality Assurance Performance Evaluation Unit; the Executive Vice President -
Power Supply and Engineering & Construction; or the Senior Vice President Nuclear Generation.
(9) The Radiological Environmental Monitoring Program and the results thereof at least once per 12 months.
(10) The Offsite Dose Calculation Manual and implementing procedure at least once per 24 months.
(11) The Process Control Program and implementing procedures for solidification of radioactive wastes at least once per 24 months.
(12) The performance of activities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 4.15, December 1977 at least once per 12 months.
- e.
Distribute reports and other records to appropriate managers.
6.5-14 Amendment No. 85
6.5.3.3
- a.
Audit personnel shall be independent of the area audited.
Selection for auditing assignments is based on experience or training that establishes that their qualifications are commensurate with the complexity or special nature of the activities to be audited. In selecting auditing personnel, consideration shall be given to special abilities, specialized technical training, prior.pertinent experience, personal characteristics, and education.
- b.
Qualified outside consultants or other individuals independent from those personnel directly involved in plant operation shall be used to augment the audit teams when necessary. Individuals performing the audits may be members of the audited organization; however, they shall not audit activities for which they have immediate responsibility, and while performing the audit, they shall not report to a management representative who has immediate responsibility for the activity audited.
6.5.3.4 Results of plant audits are approved by the Manager -
QA Services Section and transmitted to the Executive Vice President -
Power Supply and Engineering & Construction; the Senior Vice President Nuclear Generation; Manager - Robinson Nuclear Project; General Manager; and the Vice President -
Corporate Nuclear Safety &
Research; and others, as appropriate within 30 days after the completion of the audit.
6.5.3.5 The Corporate Quality Assurance Audit Program shall be conducted in accordance with written, approved procedures.
6.5-15 Amendment No. 85