ML17191A795
| ML17191A795 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 10/24/1997 |
| From: | Stang J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17191A796 | List: |
| References | |
| NUDOCS 9807220290 | |
| Download: ML17191A795 (19) | |
Text
UNITED STATES
- NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-<<>01 COMMONWEALTH EDISON COMPANY POCKET NO. 50-237 DRESDEN NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 163 License No. DPR-19
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
- 2.
A.
The application for amendment by the Commonwealth Edison Company
. (the licensee) dated March 5, 1997, as supplemented* October 3, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The f ac 11 i ty wi 11 operate in conformity with the application, the provisions of the Act and the rules and regulations of the Commission;
- C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable
- . requirements have been satisfied.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and paragraphs 2.C. (2) and 2.C. (7) of Facility Operating License No. DPR-19 are hereby amended to read as follows:
- I
[
. 9807220290 971024 '
~DR ADOCK 05000237'.
~-
____________ PDR,
\\
j
2.C.(2) 2.C. (7) *
- Technical Specifications The Technical Specifications contained in Appendix A, as
~evised through Amendment No. 163, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
Additional Conditions The Additional Conditions contained in Appendix B, as revised through Amendment No. 163 are hereby incorporated into this license. Commonwealth Edison Company shall operate the facility in accordance with the Additional Conditions.
- 3.
This license amendment is effective as of the date of its issuance and
- shall be implemented wtthin.60 days.*
Attachments:
- 1. Appendix B
- 2.
Changes to the Technical Specifications FOR THE NUCLEAR REGULATORY COMMISSION
~~~Senior Project Manager Project Directorate III-2 Division of Reactor Projects -*III/IV Office of Nuclear Reactor Regulation Date of Issuance: October 24, 1997
APPENPIX B ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. PRP-19 Coirunonwealth Edison Company shall comply with the following conditions on the schedules noted below:
Amendment Number Additional Condition 157 The license is amended to authorize changing the UFSAR to allow credit for 157 160 163 containment overpressure as det~iled below, to assure adequate Net Positive Suction Head is available for low pressure Emergency Core Cooling System pumps following a design basis accident.
Time
<seconds) 0-240 240-480 480-6.000 6000-accident end Containment Pressure CPSIGl 9.5 2.*9 1.9 2.5 The EOPs shall be changed to alert operator to NPSH concerns and to make.
containment spray operation consistent with the overpressure requirements for NPSH.
This amendme~t authorizes the licensee to incorporate in the Updated Final Safety Analysis Report (UFSAR), the description
. of the Reactor Coolant System design pressure, temperature and volume that was remtived from Technical Specification Section 5.4, and evaluated in a safety evaluation dated June 12, 1997.
The licensee shall review the Dresden Operation Annunciator and General Abnormal Conditions Procedures and revise them as required to ensure operator action is taken in a timely manner to limit occupational doses ~nd environmental releases.
Implementation Date Effective as of the issuance of Amendment No. 157 and shall be implemented within 30 days.
Shall be implemented within 30 days after
- issuance of Amendment No. 157.
30 days from the date of issuance of Amendment
.No. 160.
60 days from the date of issuance of Amendment No. 163 Amendment No. 163
y
- Amendment*
Number Add1t1onal Condition 163 The licensee shall change the setpo1nts for the Main Steamline Radiation Monitor and Offgas System Radhtion Monitor alarms to 1.5 times the normal full power N-16 background (with hydrogen addition) dose
- .rates.
Implementation Date 60 days from the,
date of issuance of Amendment No. 163 Amendment No. 163
- \\;.
UNITED STATES
- NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 COMMONWEALTH EDISON COMPANY DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION. UNIT 3 AMENPMENT TO FACILITY OPERATING LICENSE Amendment No. 158 License No. DPR-25
- 1.
The Nuclear Regulatory Commission {the Commission) has found that:
A.
The application for amendment by the Commonwealth Edison Company
{the licensee) dated March 5, 1997, as supplemented October 3, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the
- provisions of the Act and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public;
~d E.
. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and paragraphs 3.8. and 3.0. of facility Operating License No. DPR-25 are hereby amended to read as follows:
- 3.B~ Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 158, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.0 *. Additional Conditions The Additional Conditions contained in Appendix B, as revised through Amendment No.158, are hereby incorporated into this license. Conunonwealth Edison Company shall operate the facility in accordance with the Additional Conditions.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.
Attachments:
- 1. Append ix B
- 2. Changes to the Technical Specifications Date of Issuance: October 24, 1997 FOR THE NUC.LEAR REGULATORY COMMISSION
~~-,erg,
~VF. Stang Se~ior ProjeciMariager Project Direc orate 111~2 Division of Reactor Projects - Ill/IV Office of Nuclear Reactor Regulation
\\
APPENDIX B ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. PRP-25 Conunonwealth Edison Company shall comply with the following conditions on the schedules noted below:.
Amendment Number Additional Condition 152 The license is amended to authorize changing the UFSAR to allow credit for 152 152 155
. containment overpressure as detailed below, to assure adequate Net Positive Suction Head 1s available for low pressure Emergency Core Cooling System pumps following a design basis accident.
Time (seconds) 0-240 240-480 480-6000 6000-accident end Containment Pressure CPSIG>
9.5 2.9 1.9 2.5 The licensee shall complete. the evaluation of the torus attached piping.
The EOPs shall be changed to alert operator to NPSH concerns and to make containment spray operation consistent with the overpressure requirements for NPSH.
This amendment authorizes the licensee to incorporate in the Updated Final Safety Analysis Report (UFSAR), the description of the Reactor Coolant System design pressure, temperature and volume that was removed from Technical Specification Section 5.4, and evaluated in a safety evaluation dated June 12, 1997.
Implementation Pate Prior to Unit 3
- returning to Mode 3 from refueling outage D3Rl4.
Prior. to Unit 3 returning to Mode 3 from refueling outage D3Rl4.
Shall be implemented within 30 days after issuance of Amendment No. 152.
30.days from the date of issuance of Amendment No. 155 Amendment No. 158
- *Amendment Number Additional Condition 158 The licensee shall review the Dresden Operation Annunciator and General Abnormal.
Conditions Procedures and revise them as required to ensure operator action is taken in a timely manner to limit occupational doses and environmental releases.
158 The licensee shall change the set points for the Main Steam Line Radiation Monitor and Offgas System Radiation Monitor alarms to 1.5 times the normal full power N-16
. background (with hydrogen addition) dose rates.
Implementation Date 60 days from the date of issuance of Amendment No. 158 60 days from the date of issuance of Amendment No.
158 Amendment No.
158
ATTACHMENT TO LICENSE AMENDMENT NOS. 163 ANQ 158 FACILITY OPERATING LICENSE NOS. OPR-19 AND QPR 25 POCKET NOS. 50-237 ANP 50-249 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are.
identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 2'.'"4 2-4 B 2-8 B 2-8 3/4.1-3 3/4.1-3 3/4.1-5 3/4.1-5 3/4.1-7 3/4. 1-,7 3/4.1-10 3/4.1-10 3/4.2-3 3/4.2-3 3/4.2-7
- 3/4.2-7 3/4.2-8 3/4.2-8 3/4.2-10 3/4.2~10
. - - - -------------.. -:**---*-**-:-:--~---
LSSS 2.2 TABLE 2.2.A-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS Functional Unit
- 1. Intermediate Range Monitor:
- a.
Neutron Flux - High
- b.
Inoperative
- 2. Average Power Range Monitor:
- a.
Setdown Neutron Flux - High
- b.
Fl.ow Biased Neutron Flux - High
- 1) Dual Recirculation Loop Operation a)
Flow Biased b)
High Flow Maximum
- 2)
Single Recirculation Loop Operation a)
Flow Biased b)
High Flow Maximum
- c.
Fixed Neutron Flux - High
- d.
Inoperative
- 3. Reactor Vessel Steam Dome Pressure - High
- 4. Reactor Vessel Water Level - Low
- 5. Main Steam !-ine Isolation Valve - Closure
- 6. Deleted Trip Setpoint s 120/125 divisions of full scale NA s 15 % of RATED THERMAL POWER
. s0.58W181 + 62%,
with a maximum of s 120% of RATED THERMAL POWER s0.58W181 + 58.5%,
with a maximum of s 116.5% of RATED THERMAL POWER
.s120% of RATED THERMAL POWER NA s1060 psig
~ 144 inches above top of active fuel1b1 s10% closed a
W shall be the recirculation loop flow expressed as a percentage of the recirculation loop flow which produces a rated core flow of 98 million lbs/hr.
b The top of active fuel is* defined to be 360 inches above vesel zero.
DRESDEN - UNITS 2 & 3 2-4 Amendment Nos. 163, 158
. ~*.
LSSS 8 2.2
. BASES decrease as *power Is Increased to 100% *1n comparison to the level outside the shroud, to a maximum of seven Inches, due to the pressure drop across the steam dryer.
Therefore, at 100% power, an Indicated water level of +8 Inches water level may be as low as + 1 inches Inside the shroud which corresponds to 144 Inches above the top of active fuel and 504 inches above vessel zero. The top of active fuel is defined to be 360 Inches above vessel zero.
- 5.
Main steam Line Isolation Valve - Closure Automatic Isolation of the main steam lines is provided to give protection against rapid reactor depressurlzatlon and cooldown of the vessel. When the main steam line isolation valves begin to close, a scram signal provides for reactor shutdown so that high power operation at low reactor pressures does not occur. With the scram setting at 10% valve closure <from full open), there Is no appreciable Increase In neutron flux during normal or Inadvertent Isolation valve closure, thus providing protection for the fuel cladding Integrity Safety Limit. Operation of the reactor at pressures lower than the MSIV closure setting reQulres the reactor mode switch to be In the Startup/Hot standby position, where protection of the fuel cladding integrity Safety Limit Is provided by the IRM and APRM high neutron flux scram signals. Thus, the combination of main steam line low pressure Isolation and the Isolation valve closure scram with the mode switch In the Run position assures the availablllty of the neutron flux scram
- protection over the entire range of appllcablllty of fuel cladding Integrity safety Limit.
- 6.
Deleted DRESDEN
- UNITS 2 & 3 8*2*8 Amendment Nos. 163, 1 sa
'?'
1, 0
TABLE 3.1.A-1 (Continued)
- 0 m
en 0 m REACTOR PROTECTION SYSTEM INSTRUMENTATION z
c Applicable Minimum z
OPERATIONAL OPERABLE CHANNEL(s)
-t en Functional Unit MODE ls) g~r IBie SYSIEM1.,
AC!ION N
Ro w
- 5. Main Steam Line Isolation Valve - Closure 1, 2m 4
10
- 6. Deleted
- 7. Drywall Pressure - High 1, 21h1 2
11
- 8. Scram Discharge Volume Water Level - High w
~
- a.
t.P Switch, and 1, 2 2
11 51b,ll 2
13 I w
- b.
Thermal Switch (Unit 2), or 1, 2 2
11 Float Switch (Unit 3) 51b.ll 2
13
- 9. Turbine Stop Valve - Closure 11dl 4
16 *
)>
- 10. Turbine EHC Control Oil Pressure - Low 1 'di 2
16 3
CD 11
16 Q.
3 CD
- 12. Turbine Condenser Vacuum - Low 1, 2ID 2
10 z
- 0 0
"'O
!It en w
O'I
~
w U'1 CX>
REACTOR PROTECTION SYSTEM INSTRUMENTATION ACTION ACTION 10 -
Be in at least STARTUP with reactor pressure less than 600 psig within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
ACTION l 1 -
Be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- ACTION 12 -
Verify all insertable control rods to be fully inserted in the core and lock the reactor mode switch in the Shutdown position within one hour.
ACTION 13 -
Suspend all operations involving CORE ALTERATIONS, and fully insert all insertable control rods within one hour. If SRM instrumentation is not OPERABLE per Specification 3.1 O.B, also suspend replacement of LPRMs.
ACTION 14 -
Be in at le*ast STARTUP within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
ACTION 15 -
Deleted ACTION 16 -
Initiate a reduction in THERMAL POWER within 15 minutes and reduce reactor power to less than 45% of RATED THERMAL POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
ACTION 17 -
Verify all insertable control rods to be fully inserted in the core within one hour.
ACTION 18 -
Lock the reactor mode switch in the Shutdown position within one hour.
ACTION 19 -
Suspend all operations involving CORE ALTERATIONS, and fully insert all insertable control rods and lock the reactor mode switch in the Shutdown position within one hour.
If SRM instrumentation is not OPERABLE per Specification 3.1 O.B, also suspend replacement of LPRMs.
DRESDEN - UNITS 2 & 3 3/4.1-5 Amendment Nos. 163, 158
ii 0
.TABLE 4.1.A-1
- 0
- 0 m
m J>
(/)
REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS q
0 m 0
z
. :::0 i
Appllcable.
CHANNEL "U
I c:
- 0 z
OPERATIONAL CHANNEL FUNCTIONAL CHANNEL131 0
=i
-f i
Functional Unit MODES CHECK TEST CALIBRATION m
(/)
q I
9'>
i RO 0
I c.1'I
- 1. lnt~rmedlate Range Monitor:
z I
(/)
- I I
- .I
- a. Neutron Flux - High 2
Sib)
S/U1d wo' EIOI
~
\\ !
'I 3,4,5 s
wo>
.Elol i
- I
- b. Inoperative 2,3,4,5 NA wol NA
. I
'i
- 2. Average Power Range Monitor',,:
c.1'I
- a. setdown Neutron Flux - High 2
Sib' S/U1d, W°'
SA101 Ii 3, 511111 s
. w-01 SAIOI I......
Vtfd*e1, SA
- b. Flow Biased Neutron Flux-*Hlgh 1
S, D w
- c.
Fixed Neutron Flux - High 1
s w
Wcf), SA
- d. Inoperative 11111 1, 2, 3, 5 NA w
NA
- 3. Reactor vessel steam Dome Pressure - Hfgh 1, 2m
- l'JA M
a *
)>
3 CD
- 4. Reactor Vessel Water Level :. Low
- 1, *2 D
M Elhl
- s a.
3 CD
- 5. Main Steam Line Isolation Valve - Closure 1, 211:11 NA M
E
- s rt z
0
- 6. Deleted
- 0 "U
(/)
. O' 1, 21"'
c.1'I w
- 7. Drywell Pressure - High NA M
a
'!i w
~
U1
)>
CX>
REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS (I)
. With THERMAL POWER greater than or equal to 45% of RATED THERMAL POWER.
(m) Required to be OPERABLE only prior to and during required SHUTDOWN MARGIN demonstrations performed per Specification 3.12.B.
(n) This function is not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is not required.
(o) The provisions of Specification 4.0.D are not applicable to the CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION surveillances for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after entering OPERATIONAL MODE 2 or 3 when shutting down from OPERATIONAL MODE 1.
(p) This function is not required to be OPERABLE when reactor pressure is less than 600 psig.
(q) Delete DRESDEN - UNITS 2 & 3 3/4.1-10 Amendment Nos. 163, 158
- f,:
i 0
TABLE 3.2.A-1 z
- u m
-t en ISOLATION ACTUATION INSTRUMENTATION
- u o*
c m
z s:
m c
z
-t z
Minimum Applicable
)>
- j Trip CHANNEL(s) per OPERATIONAL
-1.
en 0
N Functional Unit Setgoint11l TRIP SYSTEM181 MODEis)
ACTION z
QO w
~* PRIMARY CONTAINMENT ISOLATION
- a.
Reactor Vessel Water Level - Low
- 144 inches 2
1, 2, 3 20 *
- b.
Drywall Pressure - High1dl S2 psig 2
1, 2, 3 20
- c.
Drywall Radiation - High s 100 R/hr 1
1, 2, 3 23
- 2.
SECONDARY CONTAINMENT ISOLATION w
- a.
Reactor Vessel Water Level -: Low'c'
- 144 inches 2
1, 2, 3 &
- 24 i;
- b.
Drywall Pressure - Highlc.dl s2 psig 2
1, 2, 3
- 24.
N I w
- c.
Reactor Building Ventilation Exhaust s10 mR/hr 2
1, 2, 3 & *
- 24 Radiation - High1c1
- d.
Refueling Floor Radiation - High1c1 s100 mR/hr 2
1, 2, 3 & *
- 24
- 3. MAIN STEAM LINE (MSL} ISOLATION
- a.
- 84 inches 2
1, 2, 3 21
)>
- Low Low c;;
0 3
iii" CD b~ Deleted
- J cs*
- a.
- J 3
- c.
- MSL Pressure - Low
- 825 psig 2
1 22
)>
CD
- J n
1, 2, 3
- d.
MSL Flow - High s 120% of rated 2/line 21 c
z C>>
0 1, 2, 3 en
- e.
MSL Tunnel Temperature - High s200°F 2 of 4 i.n 21 cs*
- J each of 2 sets
°'
w w
~
N U1
)>
CX>
~INSTRUMENTATION
- Isolation Actuation 3/4.2.A TABLE 3.2.A-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION TABLE NOTATION During CORE ALTERATIONS or operations with a potential for draining the reactor vessel.
- When handling irradiated fuel in the secondary containment.
(a) A CHANNEL may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance without placing the CHANNEL in the tripped condition provided the Functional Unit maintains isolation actuation capability.
(b) Deleted (c) Isolates the reactor building ventilation system and actuates the standby gas treatment system.
(d) This function is not required to be OPE~ABLE when PRIMARY CONTAINMENT INTEGRITY is not required.'
(e) Only one TRIP SYSTEM.
(f) Closes only reactor water cleanup system isolation valves.
(g) *. Deleted (h) Includes a time delay of 3 s t s 9 seconds.
(i)
Reactor vessel water level settings are expressed in inches above the top of active fuel (which is 360 inches above vessel zero).
(j)
All four switches in either. of 2 groups for each trip system.
DRESDEN - UNITS 2 & 3 3/4.2-7 Amendment Nos. 163, 158
- ~.
0 TABLE 4.2.A-1
-z
- D en m
-I en ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS
- D 0
c m z
~
m c:
CHANNEL Applicable z
-f z
CHANNEL*
FUNCTIONAL CHANNEL OPERATIONAL
)>
- j Functional Unit CHECK TEST CALIBRATION MODE(s)
-f en 0
N z
S20 w
L PRIMARY CONTAINMENT ISOLATION
- a.
Reactor Vessel Water Level - Low s
M E'.,
1, 2, 3 *
- b.
brywell Pressure - Highlbl NA M
a 1, 2, 3
- c.
Drywall Radiation - High.
s M
E 1, 2, 3
- 2. SECONDARY CONTAINMENT ISOLATION w
- a.
Reactor Vessel Water Level - Low1c1 s
M El*I 1, 2, 3 & *
~
- b.
Drywall Pressure - Highlb.cl NA M
a 1, 2, 3 N
I (I)
- c.
Reactor Building Ventilation Exhaust s
M a
1, 2, 3 & **
Radiation - High1cl
- d.
Refueling Floor Radiation - High1c1 s
M a
1, 2, 3 & **
- ~ MAIN STEAM LINE (MSLl ISOLATION
- a.
Reactor Vessel Water Level - Low Low s
M E'.,
1, 2, 3
)>
c;;
3 I b.
Deleted 0 iii CD
- s MSL Pressure - Low NA M
a 1
a*
Q.
- c.
- s 3
CD
- d.
MSL Flow - High s
M E
1, 2, 3
)>
- s 0
z c
- e.
MSL Tunnel Temperature - High NA E
E 1, 2, 3 Cl!
0 en a*
- s
°'
w w
~
N t11 co
'"',.INSTRUMENTATION
- Isolation Actuation 3/4.2.A TABLE 4.2.A-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATION During CORE ALTERATIONS or operations with a potential for draining the reactor vessel.
- When handling irradiated fuel in the secondary containment.
(a) Trip units are calibrated at least once per 31 days and transmitters are calibrated at the frequency identified in the table.
. (b) This function is not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is not required.
(c) Isolates the reac~or building ventilation system and actuates the standby gas treatment system.
(d) Deleted DRESDEN - UNITS 2 & 3 3/4.2-10 Amendment Nos. 16 3, 158
..... _____,,.,_.............. ----*-*-**-*----