Letter Sequence Request |
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Results
Other: A01061, Forwards Info Re Design Basis Transient & Accident Conditions Providing Basis for Auxiliary Feedwater Sys Flow Requirements,In Response to NRC 791022 Request.Based on Analyses,Auxiliary Feedwater Sys Complies W/Section 1.4, B10116, Advises of Discrepancy Between Delays Cited in Util 800520 Analysis Re Use of Two Electrically Driven Auxiliary Feedwater Pumps in Automatic Initiation Scheme.Multiple Conservatisms Justify Validity of Analysis, ML19210E670, ML19211A900, ML19211C160, ML19253C587, ML19257C081, ML19257C288, ML19257D549, ML19260B517, ML19305A972, ML19305D956, ML19309B223, ML19322E381, ML19338C766, ML20125D098
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MONTHYEARML19256E2921979-10-22022 October 1979 Fowards Generic Request for Addl Info & Requirements for Auxiliary Feedwater Sys Project stage: RAI ML19210E6701979-11-28028 November 1979 Responds to NRC 791018,22 & 1121 Requests Re short- & long- Term Recommendations for Auxiliary Feedwater Sys Requirements Project stage: Other ML19253C5871979-11-30030 November 1979 Forwards Calculations Re Automatic Initiation of Auxiliary Feedwater & Supporting Statement That Longer Time Is Available for Haddem Neck Steam Generator Dryout than for Millstone-2 Project stage: Other ML19260B5111979-12-0606 December 1979 Forwards Proposed Automatic Initiation Scheme for Auxiliary Feedwater Sys, in Response to NRC Request for Specific Design Details & Demonstration of Compliance W/Hr Denton Project stage: Request ML19253C9351979-12-0606 December 1979 Forwards Rept Re Proposed Automatic Initiation of Auxiliary Feedwater Sys in Response to NRC Request for Sepcific Design Details & for Demonstration of Compliance W/Nrc to All Operating Nuclear Power Plants Project stage: Request ML19211A9001979-12-17017 December 1979 Forwards Design Drawings Re Automatic Initiation of Auxiliary Feedwater,In Response to NRC Request.W/O Encl. List of Drawings Encl Project stage: Other ML17208B0701979-12-18018 December 1979 Provides Info on Compliance W/Tmi Lessons Learned Task Force short-term Item Re Auxiliary Feedwater Sys Flow Indication, in Response to NRC 791211 Request.Util Installing Single Control Grade Flow Indication Channel Per Feedline Project stage: Other ML19211C1601979-12-21021 December 1979 Requests Tech Specs for Auxiliary Feedwater Sys Mods & Revision of Normal & Emergency Operating Procedures. Sample Tech Spec Pages Encl Project stage: Other ML20125D0981979-12-27027 December 1979 Responds to to Hendrie Re Concerns About Requirement for Automatically Initiated Auxiliary Feedwater Sys at Facilities.Requests Analysis of Effect of Failure to Isolate Feedwater Flow to Affected Steam Generator Project stage: Other ML19260B5171979-12-31031 December 1979 Proposed Automatic Initiation Scheme for Auxiliary Feedwater Sys Project stage: Other ML19257C0811980-01-0303 January 1980 Forwards Summary of Bulletins & Orders Task Force 791218-19 Audit of Small Break LOCA Emergency Procedure & Operator Retraining.List of Exit Interview Attendees & List of Instrument Power Supplies Encl Project stage: Other ML19257C2881980-01-17017 January 1980 Submits Results of Review of Operating Records of 48-h Endurance Test on Auxiliary Feedwater Pumps,In Response to short-term Recommendations of NRC 791011 & 22 Ltrs.Intent of Recommendation Fulfilled Project stage: Other ML19257D5491980-01-25025 January 1980 Forwards Info Re Automatic Initiation of Auxiliary Feedwater.No Conclusion Reached Re Acceptability of Implementation Project stage: Other ML19273D1251980-02-14014 February 1980 Forwards Licensee Accident Analysis Re Main Steam Line Break Inside Containment.Requests Safety Evaluation.Licensee Plans to Submit Auxiliary Feedwater Sys auto-initiation Sys Which Delays Auxiliary Feedwater Flow for Three Minutes Project stage: Approval ML19322E3811980-03-0505 March 1980 Responds to IE Bulletin 80-04 Re Analysis of PWR Main Steam Line Break W/Continued Feedwater Addition.Details of Control Grade Automatic Initiation of Auxiliary Feedwater Scheme Are Being Finalized.Necessity of Installation Is Questionable Project stage: Other ML19305A9721980-03-10010 March 1980 Advises That Util Response to NRC 791022 Request Re Auxiliary Feedwater Sys Flow Design Info Is Scheduled for Submittal on or About 800616 Project stage: Other ML19309B2231980-03-31031 March 1980 Proposed Revisions to Tech Specs 3.7.1.2 & 4.7.1.2,adding Surveillance Requirement for Auxiliary Feedwater Flow Test After Cold Shutdown Exceeding One Month Project stage: Other ML19309B1741980-03-31031 March 1980 Application to Amend License DPR-65,in Response to Concerns Expressed in NRC .Revisions Add Surveillance Requirement for Auxiliary Feedwater Flow Test After Cold Shutdown Exceeding One Month.Affidavit Encl Project stage: Request ML19305D9561980-04-11011 April 1980 Discusses Problems W/Implementation of Lessons Learned Task Force Recommendation Re Automatic Initiation of Auxiliary Feedwaters Sys.Requests NRC Concurrence W/Plan for Implementing Requirement During 1980 Refueling Outage Project stage: Other ML19275E7241980-05-0909 May 1980 Forwards Supplemental Safety Evaluation Supporting Licensee 800125 Response.Peak Containment Pressure Will Remain Below Design Pressure Even W/Addition of Auxiliary Feedwater at Run Out Flow Project stage: Approval ML19275E7271980-05-0909 May 1980 Suppl to Safety Evaluation Supporting Licensee 800125 Response.Peak Containment Pressure Will Remain Below Design Pressure Even W/Addition of Auxiliary Feedwater at run-out Flow Project stage: Approval A00803, Application to Amend License DPR-65,submitted as Proposed Revision to Tech Specs,In Response to NRC . Summarizes Status of Implementation of Automatic Initiation of Auxiliary Feedwater.One Pump Sufficient1980-05-20020 May 1980 Application to Amend License DPR-65,submitted as Proposed Revision to Tech Specs,In Response to NRC . Summarizes Status of Implementation of Automatic Initiation of Auxiliary Feedwater.One Pump Sufficient Project stage: Request ML19323F2551980-05-20020 May 1980 Tech Spec Change Request for Tables 3.3-3,3.3-4,3.3-5 & 4.3-2,for Engineered Safety Features Actuation Sys Instrumentation,Trip Values,Response Times & Surveillance Requirements Project stage: Request A01060, Responds to IE Bulletin 80-06, Engineered Safety Feature (ESF) Reset Controls. Three Facilities Will Have Completed Mods Per IE Bulletin 80-06 by 810101.List of Equipment & Status of Criteria Encl1980-06-13013 June 1980 Responds to IE Bulletin 80-06, Engineered Safety Feature (ESF) Reset Controls. Three Facilities Will Have Completed Mods Per IE Bulletin 80-06 by 810101.List of Equipment & Status of Criteria Encl Project stage: Other A01061, Forwards Info Re Design Basis Transient & Accident Conditions Providing Basis for Auxiliary Feedwater Sys Flow Requirements,In Response to NRC 791022 Request.Based on Analyses,Auxiliary Feedwater Sys Complies W/Section 1.41980-06-16016 June 1980 Forwards Info Re Design Basis Transient & Accident Conditions Providing Basis for Auxiliary Feedwater Sys Flow Requirements,In Response to NRC 791022 Request.Based on Analyses,Auxiliary Feedwater Sys Complies W/Section 1.4 Project stage: Other ML19338C7661980-08-29029 August 1980 Proposed Revisions to Tech Specs Required to Support Plant Operation During Cycle 4 Reload Project stage: Other B10061, Application for Amend to License DPR-65,incorporating Proposed Revisions to Tech Specs Required to Support Plant Operation During Cycle 4 Reload1980-08-29029 August 1980 Application for Amend to License DPR-65,incorporating Proposed Revisions to Tech Specs Required to Support Plant Operation During Cycle 4 Reload Project stage: Request ML19338D1421980-09-0202 September 1980 Requests Class III Fee for Review of 800520 Application for Proposed Tech Spec Changes Re Automatic Initiation of Auxiliary Feedwater Sys.Application Involves Consideration of Single Safety Issue Project stage: Approval B10116, Advises of Discrepancy Between Delays Cited in Util 800520 Analysis Re Use of Two Electrically Driven Auxiliary Feedwater Pumps in Automatic Initiation Scheme.Multiple Conservatisms Justify Validity of Analysis1980-10-31031 October 1980 Advises of Discrepancy Between Delays Cited in Util 800520 Analysis Re Use of Two Electrically Driven Auxiliary Feedwater Pumps in Automatic Initiation Scheme.Multiple Conservatisms Justify Validity of Analysis Project stage: Other B10127, Advises of Error in Sgn 111 Code Used for Feedline Break Analysis Submitted 800616 in Response to NRC 791022 Request for Addl Info Re Auxiliary Feedwater Sys Flow Requirements. Forwards Reanalysis Using Sgn 111 Code1980-11-20020 November 1980 Advises of Error in Sgn 111 Code Used for Feedline Break Analysis Submitted 800616 in Response to NRC 791022 Request for Addl Info Re Auxiliary Feedwater Sys Flow Requirements. Forwards Reanalysis Using Sgn 111 Code Project stage: Request A00921, Forwards Addl Response to IE Bulletin 80-06, Engineered Safety Feature Reset Controls. Reset Logic Associated W/Certain Components Did Not Require Mods.Items & Justification for Deletions Described1981-02-13013 February 1981 Forwards Addl Response to IE Bulletin 80-06, Engineered Safety Feature Reset Controls. Reset Logic Associated W/Certain Components Did Not Require Mods.Items & Justification for Deletions Described Project stage: Other A01488, Responds to NRC Requesting Auxiliary Feedwater Pump Endurance Test & Compliance W/Requirement to Automate Steam Driven Auxiliary Feedwater Pump.Test Confirmed Pump Vibrations Did Not Exceed Allowable Limits1981-02-19019 February 1981 Responds to NRC Requesting Auxiliary Feedwater Pump Endurance Test & Compliance W/Requirement to Automate Steam Driven Auxiliary Feedwater Pump.Test Confirmed Pump Vibrations Did Not Exceed Allowable Limits Project stage: Other ML19347D4851981-03-19019 March 1981 Discusses Review of Util Providing Info Re 48-h Auxiliary Feedwater Pump Endurance Test & Compliance W/Nrc Requirement to Automate Start of steam-driven Pump.Item Re Pump Test Resolved Project stage: Approval ML19343D0051981-03-20020 March 1981 Suppls 810213 Response to IE Bulletin 80-06, Engineered Safety Feature (ESF) Reset Controls. Low Pressure Safety Injection Pumps P-42A & B Are Secured Upon Receipt of Sump Recirculation Actuation Signal Project stage: Other ML20005A8731981-06-26026 June 1981 Informs That Control Board Mounting Hardware for Auxiliary Feedwater Flow Indicators Will Not Arrive Prior to Required 810701 Inservice Date,Per NUREG-0737,Item II.E.1.2.Vendor Failed to Order Equipment.Foxboro Co Encl Project stage: Other ML20054E1841982-04-16016 April 1982 Forwards Responses to Generic Ltr 82-05 Re post-TMI Requirements Implementation.Continued Safe Operation Assured W/Existing Implementation Status Project stage: Other 1980-03-10
[Table View] |
Text
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(_)
DOCKET NO. 50-336 ATTACIBIENT 2 MILLSTONE NUCLEAR POWER STATION, UNIT No. 2 AUTOMATIC INITIATION OF AUXILIARY FEEDWATER PROPOSED REVISIONS TO TECIINICAL SPECIFICATIONS i
)
MAY, 1980 80 052807p g
TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION h
MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE M
MODES _
ACTION _
FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE _
7.
CONTAINMENT PURGE d
VALVES ISOLATION a.
Manual CIAS (Trip Buttons) 2 1
2 1,2,3,4 6
b.
Mariual SIAS (Trip Buttons) 2 1
2 1,2,3,4 6
c.
Automatic CIAS Actuation Logic 2
1 2
1,2,3 6
R d.
Containment Radiation -
High Y
Gaseous Monitor 1d 1d 1
1, 2, 3, 4, 6 8 Particulate Monitor 1d 1d 1
1,2,3,4,6 8 8.
LOSS OF POWER a.
4.16ky Emergency Bus 4/ Bus 2/Bos 3/ Bus 1, 2, 3 7
Undervoltage (Under-vb1tage relays) - level one b.
4.16kw Erergency Bus Undervoltage (Under-voltage relays) - level 4/ Bus 2/ Bus 3/ Bus 1, 2, 3 7
two 9.
AUXILIARY FEEDWATER a.
Manual 2
1 2
1,2,3 9
1,2,3 9
b.
Steam Generator Lbvel - Low 2(f) 1(f).
2
TABLE 3.3-3 (Continued)
TABLE NOTATION (a) Trip function may bs bypassed when pressurizer pressure is
< 1750 psia; bypass shall be automatically removed when pressurizer pressure is y,1750 psia.
(b) An SIAS signal is first necessary to enable CSAS logic.
(c) Trip function may be bypassed below 600 psia; bypass shall be automatically removed at or above 600 psia.
(d) Each char.nel has two sensors, high radiation level on either sensor will initiate containment purge valve isolation.
(e) Trip may be bypassed during testing pursuant to Special Test Excep-tion 3.10.3.
(f) Each channel has four (4) sensors, low steam generator water level
~
on any two (2) sensors will inithte a channel trip.
~
ACTION STATEI1ENTS ACTION 6 With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
ACTION 7 With the number of OPERABLE channels one less than the Total Number of Channels and with the pressurizer pressure:
a.
< 1750 psia; imediately place the inoperable channel in the bypassed condition; restore the in-operable channel to OPERABLE status prior to increasing the pressurizer pressure above 1750 psia.
b.
> 1750 psia, operation may continue with the in-
.,operable channel in the bypassed condition, provided the following conditions are satisfied:
1.
All functional units receiving an input from the bypassed channel are also placed in the bypassed condition.
2.
The liinimum Channels OPERABLE requirement is met; however, one additional channel may be removed from service 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 surveillance testing per Specification 4.3.2.1 provided one of the inoperable channels is placed in the tripped condition.
illLLSTONE - UNIT 2 3/4 3-16
TABLE 3.3-3 (Continued)
With one or ms e channels inoperable, operation may v
i ACTION 8 continue provios the containment purge valves are main-l tained closed.
With the numbar of OPERABLE channels one less than the ACTION 9 Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or place the inoperable component in the tripped condition, or be J
i in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
J
- (
l i
t MILLSTONE - UNIT 2 3/4 3-17 t
1
TABLE 3.3-4 (Continued)_
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION Trip VALUES G
--e
'E All.0WABLE 7
FUNCTIONAL UNIT TRIP VALUE VALUrS__
E, 8.
LOSS OF POWER m
a.
4.16 kv Emergency Bus Undervoltage (Undervoltage relays) - level one
> 2912 volts
> 2912 volts b.
4.16 ky Emergency Bus Undervoltage
> 1700 volts with
> 3700 volts with (Undervoltage relays) - level two an 8.0 + 2.0 second in 8.0 + 2.0 second time deTay time deTay 9.
AUXILIARY FEEDWATER a.
Manual Not Applicable Not Applicable g
y b.
Steam Generator Level - Low
> 12%
> 10%
E$
i 9
^
TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION p.SPONSETIMEINSECONDS 3.
Containment Pressure-High a.
Safety Injection (ECCS) 1)
High Pressure Safety Injection 1 30.0*/5.0**
2)
Low Pressure Safety Injection 1 50.0*/5.0**
3)
Charging Pumps 1 40.0*/40.0**
4)
Containment Air Recirculation System 1 31.0*/31.0**
b.
Containment Isolation 1 7.5 c.
Enclosure Building Filtration System 1 E5.0*/50.0**
4.
Containtrent Pressure--High-High 35.6*III/35.6**(I) a.
Containment Spray 1
5.
Containment Radiction-High a.
Containment Purge Valves Isolation 1 ounting period -
C plus 7.5 6.
Steam Generator Pressure-Low a.
Main Steam Isolation 6
19 b.
Feedwater Isolation 1 60 7.
Refueling Water Storage Tank-Low a.
Containment Sump Recirculation 1 120 8.
Steam Generator Level-Low 60*/ 60** (2)
Auxiliary Feedwater System 1
TABLE NOTAT10fi
- Diesel generator starting and sequence loading delays included.
- Diesel generator starting and sequence loading delays not included.
Offsite power available.
(1) Header fill time not allowed.
(2) Excludes three-minute timed delay.
MILLSTONE -. UNIT 2 j
3/4 3-22 l
~
~
TABLE 4.3-2 (Continued)
ENGINEERED SAFETY FEATUPE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS b
CHANNEL MODES IN WHICH 5
CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE i
FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED C5 6.
CONTAINMENT SUMP RECIRCULATION (SRAS) a.
Manual SRAS (Trip Buttons)
N.A.
.M.A.
R N.A.
b.
Refueling Water Storage Tank - Low S
R M
- 1. 2, 3 c.
Automatic Actuation logic N.A.
N.A.
M(1) 1, 2, 3 7.
CONTAINMENT PURGE VALVES ISOLATION a.
ManualCIAS(Tr'oButtons)
N.A.
M.A.
R N.A.
b.
Manual SIAS (",p Buttons)
N.A.
N.A.
R M.A.
c.
Automatic CIAS Actuation R
Logic N.A.
N.A.
- M(1)
- 1. 2, 3 d.
Containment Radiation - High Y
Gaseous Monitor S
R M
ALL MODES Particulate Monitor S
R M
ALL MODES 8.
LOSS OF POWER a.4.16 ky Emergency Bus Undervoltage (Undervoltage relays) - level one S
R M-1.2,3
- b. 4.16 kv Emergency Bus Undervoltage(Undervoltage relays) - level two S
R M
1,2, 3 9.
AUXILIARY FEEDWATER a.
Manual Initiation N.A.
N.A.
R 1, 2, 3 l
b.
Steam Generator Level-Low S
R M
1, 2, 3 s
i
- Manual actuation switches shall be tested at least once per 18 months.
All other circuitry associated with manual safeguards actuatim shall receive a CHANNEL FUNCTIONAL TEST at least once per 31 days.