Letter Sequence Other |
|---|
|
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement
Results
Other: ML17255A937, ML19309H462, ML19318A584, ML19337B217, ML19343B804, ML20003H940, ML20009C964, ML20024B941, ML20038A631, ML20040E980, ML20049J615, ML20051M285, ML20054F383, ML20055C134, ML20133K973, ML20135A778, ML20137A994, ML20137N995, ML20140E550, ML20155E786, ML20155E791, ML20198C257
|
MONTHYEARML19289C2151978-11-28028 November 1978 Forwards List of Requests for Design Changes & Other Work Items Suppl Previous Lists.Items on This List Will Not Affect Load Carrying Capability of Any Major Shear Wall Project stage: Request ML19209C3961979-09-27027 September 1979 Forwards Request for Addl Info Re Plant Control Bldg Design Mods.Encl Questions Comprise NRC Positions Re Acceptable Util Response Project stage: Request ML19262C4321980-02-0505 February 1980 Forwards Response to NRC 791003 Generic Request for Info Re Auxiliary Feedwater Flow Requirements.Info Pertains to Design Bases for Auxiliary Feedwater Sys Project stage: Request ML19309H4621980-05-0707 May 1980 Forwards License Change Application (Lca) 60,replacing Lca 51.Certificate of Svc Encl Project stage: Other ML19318A5841980-06-16016 June 1980 Forwards Response to NRC Re Implementation of Five Addl TMI-2 Related Action Items Project stage: Other 05000344/LER-1980-017, Forwards LER 80-017/03L-01980-09-0505 September 1980 Forwards LER 80-017/03L-0 Project stage: Request ML19337B2171980-09-29029 September 1980 Notifies of Delay in Implementation of TMI-2 Lessons Learned Items Scheduled for 810101 Until Resolution of Matl Delivery Problems.Summary of Util Commitments Per NUREG-0578 & Comments on NRC to Licensees & Applicants Encl Project stage: Other ML19339B0061980-10-23023 October 1980 Forwards Safety Evaluation Re Implementation of Recommendations for Auxiliary Feedwater Sys.Requests Response to Two Unresolved Items Identified in Rept within 45 Days Project stage: Approval ML19339B0091980-10-23023 October 1980 Safety Evaluation Re Implementation of Recommendations for Auxiliary Feedwater Sys Project stage: Approval ML19343B8041980-12-23023 December 1980 Responds to NRC Requesting Response to NUREG-0737 Re Implementation of TMI-2 Action Items.Util Intends to Meet Requirements & Schedules Except Where Stated.Hardware Availability Problems Could Cause Delays Project stage: Other ML20003H9401981-05-0404 May 1981 Advises That Mods Needed Re TMI Action Item II.F.1.6, Containment Hydrogen Monitoring,To Achieve Acceptable Levels of Reliability Based on NUREG-0737 Criteria.Three solenoid- Operated Valves Will Be Added Inside Containment Project stage: Other ML20009C9641981-07-17017 July 1981 Suppls 801223 Response to NUREG-0737,Item II.B.1 Re Reactor Coolant Vent Sys.Also Submits Info on Items II.D.1,II.E.1.2, II.E.4.2,II.K.3.5,II.K.3.25,II.F.1.5,II.F.2 & III.A.2 Project stage: Other ML20031H1461981-10-21021 October 1981 Forwards Supplemental Info Re Implementation Status of TMI Action Items II.B.3,II.F.1.1,II.F.1.2,II.F.1.6,II.F.2, II.D.1.2,II.K.3.1,II.K.3.5 & III.A.2.Items Will Be Completed by 820801 Project stage: Supplement ML20038A6311981-11-0606 November 1981 Forwards Addl Info Requested in NRC Re Reactor Vessel Level Indication Sys Being Installed at Facility Project stage: Other ML20236A0681981-12-0404 December 1981 Safety Evaluation Re Containment Purging & Venting During Normal Operation of Plant.Purge/Vent Sys Design & Operating Practices for Facility Acceptable Subj to Implementation of Recommended Actions Project stage: Approval ML20039D4801981-12-28028 December 1981 Forwards Supplemental Info to Util Re Implementation of NUREG-0737 Items Requiring Licensee Action by 820101 Project stage: Supplement ML20040E9801982-01-29029 January 1982 Provides Addl Clarification of TMI Action Items II.F.1.1 & II.F.1.2 Re Capability of Radioactive Gaseous Waste Sys & Isokinetic Sampling,Per NRC .Diagram of Waste Gas Sys Recycle Vent Encl Project stage: Other ML20049J6151982-03-0404 March 1982 Advises That TMI Action Item II.K.3.3, Reporting Relief Valve & Safety Valve Failures & Challenges, Resolved Based on 801223 & 810102 Responses Project stage: Other ML20052D1261982-04-28028 April 1982 Forwards Supplemental Info Re Implementation Schedules for Outlined NUREG-0737 TMI Action Items in Response to Generic Ltr 82-05.Schedules for Items II.B.3 & II.F.1 Will Be Extended Due to Vendor Delays Project stage: Supplement ML20052F5451982-05-0707 May 1982 Responds to 820224 Request for Addl Info on NUREG-0737, Item II.B.1 Re RCS Vent.Design Parameters & Max Rate of Reactor Coolant Through Reactor Vessel Head Vent Sys Flow Restriction Orifices Provided Project stage: Request ML20051M2851982-05-10010 May 1982 Forwards Addl Info Re NUREG-0737 Action Items I.A.2.1, Upgraded Senior Reactor Operator & Reactor Operator Training & II.B.4,training for Mitigating Core Damage,Per NRC 820318 Request Project stage: Other ML20054F3831982-06-11011 June 1982 Forwards Addl Info Re Implementation Schedules for NUREG-0737 Items,In Response to Generic Ltr 82-10.Items Include I.A.1.3.1,I.A.1.3.2,I.C.1,II.D.1.2,II.D.1.3, II.K.3.30,II.K.3.31,III.A.1.2,III.A.2.2 & III.D.3.4 Project stage: Other ML20055C1341982-08-0303 August 1982 Advises That Main Steam Line Radiation & Containment Hydrogen Monitors Will Be Operational by 821001,per NUREG-0737 Items II.F.1.1 & II.F.1.6 Project stage: Other ML17255A9371983-04-21021 April 1983 Operating Reactor PORV Repts (F-37) TMI Action Plan Requirements,Westinghouse Owners Group,WCAP-9804, Technical Evaluation Rept Project stage: Other ML20024B9411983-07-0808 July 1983 Discusses Continued Problems in Making Control Room Ventilation Sys Operational Per TMI Action Plan Item III.D.3.4.Only One Area Radiation Monitor Necessary,Per TMI Action Plan Item III.A.1.2 Project stage: Other ML20140E5501985-01-0404 January 1985 Forwards Schedule for Submitting Addl Info & Justification of Nonconformance of Core Exit Thermocouples & Subcooling Margin Monitors,Per 840202 SER on Util Response to Generic Ltr 82-28 & NUREG-0737,Item II.F.2 Project stage: Other ML20126M4801985-06-13013 June 1985 Forwards Request for Addl Info Re Core Exit Thermocouple Sys,Subcooling Margin Monitors & Reactor Vessel Level Instrumentation Sys,In Order to Complete Review of 840312 & 850104 Submittals for TMI Item II.F.2.3 Project stage: RAI ML20129K1171985-07-19019 July 1985 Responds to 850613 Request for Addl Info Re NUREG-0737,Item II.F.2, Inadequate Core Cooling Instrumentation. Class 1E Platinum Resistance Temp Detectors Will Be Used to Measure Ref Junction Temp for Backup Displays Project stage: Request ML20133K9571985-08-0707 August 1985 Application for Amend to License NPF-1,consisting of License Change Application 125,incorporating Tech Specs for TMI-related Items Per NRC Model Tech Specs,NUREG-0737 & Generic Ltr 83-37 Project stage: Request ML20133K9421985-08-0707 August 1985 Forwards Application for Amend to License NPF-1,consisting of License Change Application 125,incorporating Tech Specs for TMI-related Items Per NRC Model Tech Specs.Certificate of Svc Also Encl.Fee Paid Project stage: Request ML20133K9731985-08-0707 August 1985 Proposed Tech Specs,Incorporating TMI-related Items Per NRC Model Tech Specs Project stage: Other ML20135A7781985-09-0303 September 1985 Forwards Reactor Vessel Level Instrumentation Sys Implementation Ltr Rept,In Response to NRC 850202 Safety Evaluation Project stage: Other ML20198C2571985-11-0505 November 1985 Forwards Addl Info Re Inadequate Core Cooling Instrumentation Installed or Proposed for Installation,In Response to NRC 850910 Onsite Evaluation.W/One Oversize Drawing Project stage: Other ML20137A9941985-11-21021 November 1985 Advises That Isolation Capability of Control Room Normal Ventilation Sys CB-2 Adequate.No Mods Required to Meet Intent of NUREG-0737,Action Item III.D.3.4, Control Room Habitability & GDC 19 Based on Listed Reasons Project stage: Other ML20136C6401985-12-20020 December 1985 Forwards Draft SER Re Tech Spec Changes & Draft Transmittal Ltr to Licensee.Proposed Amend to License NPF-1 Approved. SALP Input Also Encl Project stage: Draft Approval ML20137N9951986-01-31031 January 1986 Forwards Addl Info in Response to 850628 Generic Ltr 85-12, Implementation of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps. Trip Provided When Needed.Trip Excluded When Continued Pump Operation Desirable Project stage: Other ML20141P0581986-03-10010 March 1986 Forwards Amend 112 to License NPF-1 & Safety Evaluation. Amend Revises Tech Specs to Add Operability & Surveillance Requirements for Core Exit Thermocouples & Reactor Vessel Level Instrumentation Sys Project stage: Approval ML20154N8751986-03-12012 March 1986 Summary of Operating Reactor Events 860310 Meeting 86-07 W/Ornl Re Events Occurring Since 860303 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl Project stage: Request ML20155E7911986-04-0707 April 1986 Corrected Amends 112 & 114 to License NPF-1,re Thermal Power,Surveillance Requirements & Control & Dilution to Moderate Temp Coefficient Project stage: Other ML20155E7861986-04-0707 April 1986 Forwards Corrected Amends 112 & 114 to License NPF-1 Revising Pagination & Resolving Administrative Errors Project stage: Other 1982-04-28
[Table View] |
Text
. - ~ _ _ -.
-.a.--._-
-.2 j
o-POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION (Continued) b.
THERMAL POWER shall not be increased above 90% of RATED THERMAL POWER unless the indicated AFD is within the 15% target band and ACTION 2.a)l), above has been satisfied.
THERMAL POWER shall not be increased above 50% of RATEf) THERMAL c.
POWER unless the indicated AFD has not been outside of the 15%
target band for more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penalty deviation cumulative during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
}
SURVEILLANCE RE0VIREMENTS
~
4.2.1.1 The indicated AXIAL FLUX DIFFERENCE shall be determined to be within its limits during POWER OPERATION above 15% of RATED THERMAL POWER by:
Monitoring the indicated AFD for each OPERA 8LE excore channel, a.
at least once per 7 days when the AFD Monitor Alarm is OPERABLE, j
and h
b.
Monitoring and logging the indicated AXIAL FLUX DIFFERENCE for each OPERABLE excore channel at least once per 30 minutes when j
the AXIAL FLUX DIFFERENCE Monitor Alarm is inoperable.
The logged values of the indicated AXIAL FLUX DIFFERENCE shall be
\\
assumed to exist during the interval preceding each logging.
I 4.2.1.2 The indicated AFD shall be considered outside of its 15% target band when at least 2 of 4 or 2 of 3 OPERABLE excore channels are indicating the AFD to be outside the target band.
target band shall be accumulated on a time basis of: POWER OPERATION outside of the 15%
i One minute penalty deviation for each one minute of POWER a.
OPERATION outside of the target band at THERMAL POWER levels equal to or above 50% of RATED THERMAL POWER, and b.
One-half minute penalty deviation for each one minute of POWER OPERATION outside of the target band at THERMAL POWER levels i
below 50% of RATED THERMAL POWER.
TROJAN-UNIT 1 3/4 2-2 Amendment No. 770, 114 k
8604180126 860407 1
PDR ADOCK 05000344 P
PDR
j TABLE 4.3-7
(
ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL CHl.NNEL FUNCTIONAL LMSTRUMENT CHECK CALIBRATION TEST 1.
Reactor Coolant System M
R Subcooling Margin Monitor 2.
PCRV Position Indicator M
R 3.
PORY Block Valve Position M
R Indicator 4.
Safety Valve Posit'on M
R Indicator ( Acovit'. cal Flow) 1 5.
Auxiliary Feedwater Flow Rate M*
R q
6.
Pressurizer Water Level M
R i
7.
Containment Atmospheric M
R Pressure (-10 to 190 psig)
(
8.
Containment Water Level (Wide M
R Range) 9.
Containment Water Level M
R (Narrow Range)
- 10. Core Exit Theraccouples M
R**
i
- 11. Reactor Vessel Level Instru-M R
mentation System l
- Not applicable in Modes 1 and 2.
4
- Calibration shall consist of calibrating the thermocouple indicators.
3 TROJAN-UNIT 1 3/4 3-53 Amendment No. 58, 92, Idf.112 t
e 9
~-,
j 1
3/4.1 REACTIVITY CONTROL SYSTEMS
(
BASES 3/4.1.1 BORATION CONTROL 3/4.1.1.1 SHUTOOWN MARGIN A sufficient SHUTOOWN MARGIN ensures that 1) the reactor can be made subcritical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and 3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.
I SHUT 00WN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS Tavg. The most restrictive condition occurs at EOL, with Tavg at no load operating temperature, and is associated with postulated steam line break accident and resulting uncontrolled RCS cooldown.
In the analysis of this accident, a minimum SHUTOOWN MARGIN of 1.6% ak/k is initially required to control the reactivity transient. Accordingly, the SHUT 00WN MARGIN requirement is based upon this limiting condition and is consistent with FSAR accident analysis assumptions. With Tavg less than 200*F, the most restrictive reactivity transients resulting from the postulated Boron Oilution Accident are such that a 1.6% ak/k SHUT 00WN MARGIN is initially required.
(
3/4.1.1.3 BORON DILUTION A minimum flow rate of at least 3000 GPM provides adequate mixing, prevents stratification and ensures that reactivity changes will be gradual during boron concentration reductions in the Reactor Coolant System. A flow rate of at least 3000 GPM will circulate an equivalent Reactor Coolant System volume of 12,900 cubic feet in approximately 33 minutes. The reactivity change rate associated with boron reductions will therefore be within the capability for operator recognition and control.
3/4.1.1.4 MODERATOR TEMPERATURE COEFFICIENT (MTC)
The limitations on MTC are provided to ensure that the assumptions used in the accident and transient analyses remain valid through each fuel cycle. The surveillance requirement for measurement of the MTC at the beginning and towards the end of each fuel cycle is adequate l
to confirm the MTC value since this coefficient changes slowly due TROJAN-UNIT 1 83/41-1 Amendment No. 5#, 770, 114 4
r
- - ~. -.~.-..
-..-- -..-..~,.
j I
'st
[
i il I I I
ll ci
[
11 jj
(
gr.
n l
cil.
II
~
~
p, le l
[5 g !
Bg II i
s I
I!!!!!l ii
[i i
iri I g. ti..
- i l
g I l gl i. I,
ll j
3 1y Ber[s2l i
ll s i I
l;l 3.!
e s-
- I; ll f
,A
,A
,A g
n!!
I l
s i l iI.a.' iii I
li s
11 ll gn 38-ll i)
Ih!
'A
~~
y i
e
(
li il 2
~
ll 4
so g
[kf
- -l!
ll ll
[
e.
I o
c g
lla l
ll i
as i
II il cl e.
l w.ll.
el It-i u..e i
bl15 El i
i ll_
Il il i
l l-ll If II II l
I
- il ll
<W la g
,a n
Es.
j i g
-g I
E i
.:l l5 I
8 jj
+
il l
l l'l
[".
.I i i 3
lI li i
3-il s'
il TROJAN - UNIT 1 6-3 Amendment No. (2. 55, 66. M.
!!3. 114
-