ML20139A324
| ML20139A324 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 09/27/1985 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20139A318 | List: |
| References | |
| NUDOCS 8510080434 | |
| Download: ML20139A324 (9) | |
Text
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ATTACHE NT A PROPOSED CHANTS TO APPENDIX A TECHNICAL SPECIFICATIONS OF FACILITY OPERATING LICENSE NPF-37 Revised Pages: 3/4 3_15 3/4 6-7 3/4 7-44 3/4 8-5 3/4 11-8 6-13 gg0ogogy P
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ATTACHMENT B REASONS FOR PROPOSED CHANCES
- 1) On Table 3.3-3 (pg. 3/4 3-15) item Id, "( Above P-7)" is changed to
"(Above P-ll)".
This is a typographical error since the ESF function of a safety injection on low pressurizer pressure is enabled above P-11 and not P-7.
2)
In surveillance 4.6.1.5 (pg 3/4 6-7) delete the periods after locations A, B, C and D.
This change is typographical.
- 3) On Table 3.7-5b (pg 3/4 7-44) Fire Hose Station M-ll should be changed to N-11.
This is a typographical change.
4.
In surveillance 4.8.1.1.2f 6b (pg 3/4 8-5) an "s" must be added to the word " operate" to make the sentence grammatically correct.
5.
In LCO 3.11.1.4 (pg 3/411-8) a comma should be added after " gases" to clarify the sentence.
6.
In Section 6.5.2b 9 (pg 6-13) "shall submit" should be changed to
" submittal of" to improve the grammar of the sentence.
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TA8tE 3.3-3 ENGlHEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION MINIMUM c
TOTAL NO.
CilANNELS CilANNELS APPLICA8tE i
3 FUNCTIOPAL UNIT OF CilANNELS TO TRIP OPERABLE MODES ACTION 3
w 1.
Safety Injectio.i (Reactor Trip, Feedwater Isolation, e-Start Diesel Generators, m
Containment Cooling fans, Control Room Isolation, Phase "A" Isolation, Turbine Trip, Auxiliary feedwater, Containment Vent Isolation, and Essential Service Water).
i a.
Manual Initiation 2
1 2
1,2,3,4 18 U
b.
Automatic Actuation 2
1 2
1,2,3,4 14 Logic and Actuation l
M Relays c.
Containment 3
2 2
1,2,3 IS*
Pressure-liigh-1 i
d.
Pressurizer Pressure-4 2
3 1, 2, 3#
19*
Low (Above P-e.
Steam Line Pressure-3/ steam line 2/s' team line 2/ steam line 1, 2, 3#
IS*
Lpw (Above P-ll) any steam line 2.
Manual Initiation 2 pair 1 pair 2 pair 1, 2, 3, 4 18 b.
Automatic Actuation 2
1 2
1,2,3,4 14 Logic and Actuation Relays Containment Pressure-G H
ft W
M c.
CONTAINMENT SYSTEMS AIR TEMPERATURE LIMITING CONDITION FOR OPERATION 3.6.1.5 Primary containment average air temperature shall not exceed 120'F.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
With the containment average air temperature greater than 120*F, reduce the average air temperature to within the limit within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />' or be in at least HOT STANDBY within the next 6 heurs and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.5 The primary containment average air temperature shall be the arithmetical average of the temperatures of the running fans at the following locations and shall be determined at least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
Location A
RCFC Dry Bulb Inlet Temperature RCFC Dry Bulb Inlet Temperature C
RCFC Dry Bulb Inlet Temperature D
RCFC Dry Bulb Inlet Temperature.
6 BYRON - UNITS 1 & 2 3/4 6-7
TABLE 3.7-5b (Continued)
(Unit 2) g FIRE HOSE STATIONS i
j LOCATION ELEVATION HOSE RACK REEL ANGLE VALVE l
[
Aux. Bldg. (Continued)
)
V-19:
By West Door to Decon Pad & Storage 430 59 0FP344 i
d Q-26:
Back of Div. 21 SWGR Room-430 284 0FP641
[
S-21:
By U-2 Pzr. HIR. Transformer (elec. pen. area) 419 175 0FP347 Q-26:
By U-2 Elect. Penetration Area 419 206 0FP346 L-II:
By waste oil tank room 405 90 0FP315 l
i P-18:
By elevator 405 91 0FP318 P-23:
By spent resin pumps 405 92 0FP349
]
Q-II: By laundry tanks 405 93 0FP314 l
5-21:
East of U-2 hydrogen recombiner 405 94 0FP348 3
V-21: West of U-2 hydrogen recombiner 405 95 0FP345 1
V-15: West of U-1 hydrogen recombiner control 1
panel 405 96 0FP316 ta 1
5-15:
East of U-l hydrogen recombiner 405 97 0FP317 3
Y
-11:
By the recycle holdup tanks 368 130 0FP373 M-13:
By the U-1 stirs 368 131 0FP374 P-13:
By panel IPL84JB 368 132 0FP369 L-20: By the U-2 stairs 368 133 0FP355 P-21:
By the blowdown condenser 368 134 0FP356 L-25:
By the PW M/U ptaips 368 135 0FP361 N-25:
By chemical drain tank 368 136 0FP357 i
S-18:
By panel IPL86J 368 138 0FP362
)
Q-ll:
By Aux. Bldg. floor drain tanks 368 139 0FP368 4
i Q-25:
By' spent resin flushing pump 368 137 OFP360 l
U-21:
By y-2 spray add tank 368 142 0FP358 V-18:
By U-2 cent. chg. pump room 368 141 0FP366 P-11:
By recycle evaporator feed pumps 350 151 0FP381 M-13:
By U-l stairs 350 152 0FP370 N-23:
By gas decay tanks 350 154 0FP352 Q-19:
By "B" Aux. Bldg. Equip. drain tank 350.
155 0FP365 Q-17:
By "A" Aux. Bldg. Equip. drain tank 350 156 0FP371 I
~.
)
l ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 3)
Verifying the diesel generator capability to reject a load of i
5500 kW without tripping.
The generator voltage shall not exceed 4784 volts during and following the load rejection, 1
4)
Simulating a loss of ESF bus voltage by itself, and:
a)
Verifying de-energization of the ESF busses and load shedding from the ESF busses, and b)
Verifying the diesel starts on the auto-start signal, energizes the ESF busses with permanently connected loads within 10 seconds, energizes the auto-connected
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safe shutdown loads through the load sequencing timer and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads.
After energization, the steady-state voltage and frequency of the ESF busses shall be maintained at 4160 + 420 volts and 60 + 1.2 Hz during this test.
4 5)
Verifying that on an ESF Actuation test signal without loss of ESF bus voltages, the diesel generator starts on the auto-start signal and operates on standby for greater than or equal i
to 5 minutes.
The generator voltage and frequency shall be 4160 + 420 volts and 60 + 1.2 Hz within 10 seconds after the auto-start signal; the generator steady state generator voltage and frequency shall be maintained within these limits during this test; 6)
Simulating a loss of ESF bus voltage in conjunction with an ESF Actuation test signal, and a)
Verifying deenergization of the ESF busses and load shedding from the ESF busses; i
b)
Verifying the diesel starts on the auto-start signal, energizes the ESF busses with permanently connected loads within 10 seconds, energizes the auto-connected emergency (accident) loads through the LOCA sequencer and 3_ operate 7 for greater than or equal to 5 minutes while its generator is loaded with emergency loads.
After i
energization, the steady-state voltage and frequency of j
i the ESF busses shall be maintained at 4160 + 420 volts and 60 + 1.2 Hz during this test; and
[
j c)
Verifying that all automatic diesel generator trips, except engine overspeed and generator differential, are automatically bypassed upon loss-of-voltage on the emergency bus concurrent with a Safety Injection Actuation signal.
BYRON - UNITS 1 & 2 3/4 8-5
RADIDACTIVE EFFLUENTS LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material, excluding tritium and dissolved or entrained noble gases, contained in any outside tanks shall be limited to the following:
a.
Primary Water Storage Tank
$ 2000 Curies, and b.
Outside Temporary Tank 5 10 Curies.
APPLICABILITY:
At all times.
ACTION:
a.
With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.7.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of' the above tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.
m BYRON - UNITS I & 2 3/4 11-8
ADMINfSTRATIVE CONTROLS ONSITE (Continued) 3)
Review of all proposed changes to the Technical Specifications; 4)
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety; 5)
Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Division Vice President and General i4anager - Nuclear Stations and to the Supervisor of the Offsite Review and Investigative Function;
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6)
Review of all REPORTABLE EVENTS; 7)
Performance of special reviews and investigations and reports thereon as requested by the Supervisor of the Offsite Review and Investigative Function; 8)
Review of the Station Security Plan and implementing procedures and submittal of recommended changes to the Division Vice President and General Manager - Nuclear Stations; 9)
Review of the Emergency Plan and station implementing procedures T #and.......---.. recommended changes to the Division Vice submdtal dff President and General Manager - Nuclear Stations; 10)
Review of Unit operations to detect potential hazards to nuclear safety; 11)
Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Division Vice President and General Manager - Nuclear Stations and the Supervisor of the Offsite Review and Investigative Function; and J
l 12)
Review of changes to the PROCESS CONTROL PROGRAM, the OFFSITE DOSE CALCULATION MANUAL, and the Radwaste Treatment Systems.
c.
Authority The Technical Staff Supervisor is responsible to the Station Superintendent and shall make recommendations in a tir.ely manner in all areas of review, investigation, and quality control phases of plant maintenance, operation, and administrative procedures relating to facility operations and shall have the authority to request the action necessary to ensure compliance with rules, regulations, and procedures when in his opinion such action is necessary.
The Station Superintendent shall follow such recommend.1tions or select a course BYRON - UNITS 1 & 2 6-13
ATTACHMENT C SIGNIFICANT HAZARDS CONSIDERATION Commonwealth Edison has evaluated the proposed amendment and has determined that it does not represent a significant hazards consideration.
Based on the criteria for defining a significant hazards consideration established in 10 CFR 50.92, operation of Byron Station Unit 1 in accordance with the proposed amendment will not:
- 1) Involve a significant increase in the probability or consequences of an accident previously evaluated because the proposed changes are purely administrative and only involve corrections of typographical errors and improvements in grammar and punctuation.
- 2) Create the possibility of a new or different kind of accident from any accident previously evaluated because the proposed changes are purely administrative and only involve corrections of typographical errors and improvements in grammar and punctuation.
- 3) Involve a significant reduction in a margin of safety because the proposed changes are purely administrative and only involve corrections of typographical errors and improvements in grammar and punctuation.
Based on the preceding assessment, it is concluded that the proposed amendment meets the standards provided in 10 CFR 50.92 and therefore, does not constitute a significant hazards consideration.
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