Letter Sequence Other |
|---|
|
Results
Other: 05000267/LER-1986-020, :on 860711,determined That FSAR Analyses for Safe Shutdown Cooling Following 90-minute Loss of Forced Cooling May Be Invalid.Caused by Design Omission.Three Options Presently Being Investigated, 05000267/LER-1986-026, :on 860917,FSAR Analysis for Safe Shutdown Cooling W/Firewater Invalid.Caused by Incomplete Analysis/ Inadequate Review.Review & Reanalysis Will Be Performed on Various Accidents Described in FSAR, ML19306G340, ML20137H372, ML20197B076, ML20204G924, ML20205T170, ML20206B329, ML20206B459, ML20206F887, ML20207K386, ML20207K441, ML20207K446, ML20207K506, ML20207K512, ML20207P779, ML20207P991, ML20207P993, ML20209E329, ML20209F187, ML20209G043, ML20210A740, ML20210A748, ML20210A757, ML20210T436, ML20210T655, ML20210T686, ML20211D992, ML20211E058, ML20211E084, ML20211E110, ML20211G583, ML20211N368, ML20214Q988, ML20214Q998, ML20214S836, ML20215H964, ML20215H973, ML20215J855, ML20215J871, ML20234C109, ML20235E520, ML20235F508, ML20245C018
|
MONTHYEARML20137H3721985-11-26026 November 1985 Memorandum & Order Granting Extension of 851130 Deadline for Environ Qualification of Electrical Equipment to 860531 & Approving Proposal to Allow Operation w/35% Reactor Power Limit During Interim.Served on 851127 Project stage: Other ML20211E0841986-02-20020 February 1986 Issue a to Fort St Vrain:Delayed Firewater Cooldown;Effect of Liner Cooling on Orifice Valve Temps Project stage: Other ML20209F1871986-03-18018 March 1986 Fort St Vrain Steam Generator Temps During Interruption of Forced Cooling from 105% Power Project stage: Other 05000267/LER-1986-020, :on 860711,determined That FSAR Analyses for Safe Shutdown Cooling Following 90-minute Loss of Forced Cooling May Be Invalid.Caused by Design Omission.Three Options Presently Being Investigated1986-08-10010 August 1986
- on 860711,determined That FSAR Analyses for Safe Shutdown Cooling Following 90-minute Loss of Forced Cooling May Be Invalid.Caused by Design Omission.Three Options Presently Being Investigated
Project stage: Other ML20211E0581986-09-30030 September 1986 Effect of Delayed Firewater Cooldown W/Loss of Liner Cooling on Pcrv Temps Project stage: Other 05000267/LER-1986-026, :on 860917,FSAR Analysis for Safe Shutdown Cooling W/Firewater Invalid.Caused by Incomplete Analysis/ Inadequate Review.Review & Reanalysis Will Be Performed on Various Accidents Described in FSAR1986-10-17017 October 1986
- on 860917,FSAR Analysis for Safe Shutdown Cooling W/Firewater Invalid.Caused by Incomplete Analysis/ Inadequate Review.Review & Reanalysis Will Be Performed on Various Accidents Described in FSAR
Project stage: Other ML20211G5831986-10-22022 October 1986 Anticipates Completion of Steam Generator Analysis & App R Modeling Reanalysis Work by Feb 1987,per 860918 Telcon W/Nrc Re Steam Generator Cool Down Studies for App R Project stage: Other ML20197B0761986-10-22022 October 1986 Informs That Util Will Update & Submit Rept on Chernobyl Accident by 861126.Update Will Ctr on Graphite Related Concerns,Including Analysis of Worst Case Explosive Gas Mixtures & Comparison of Reactor Kinetics Behavior Project stage: Other ML20207K5121986-11-13013 November 1986 Fort St Vrain Calculations for Circulator Temp-Related Operating Limits Project stage: Other ML20207K5011986-12-0404 December 1986 Effect of Firewater Cooldown Using Economizer-Evaporator- Superheater (EES) Bundle on Steam Generator Structural Integrity. Draft Rept of Steam Generator Ability to Withstand post-App R Firewater Cooldown Transient Encl Project stage: Draft Other ML20207K4461986-12-12012 December 1986 Issue a to Effect of Firewater Cooldown Using Reheater on Steam Generator Structural Integrity Project stage: Other ML20211N3681986-12-12012 December 1986 Forwards Restart Interaction Schedule,Per 861205 Request Project stage: Other ML20207K5061986-12-22022 December 1986 Issue a to Effect of Intentional Depressurization on Cooldown from 39% Power Using One Reheater Module (1-1/2 H Delay) Project stage: Other ML20207K4411986-12-23023 December 1986 Issue a to Economizer-Evaporator-Superheater (EES) Cooldown from 39% & 78% Power Using Condensate or Firewater (1.5 H Delay) Project stage: Other ML20207K3861986-12-30030 December 1986 Forwards Analyses Supporting Power Operation Up to 39% Power Based on Safe Shutdown Cooling Following 90 Min Interruption of Forced Circulation.Conclusions of Repts Listed.Corrective Actions for LERs 86-020 & 86-026 Also Listed Project stage: Other ML20207P7791987-01-0707 January 1987 Forwards Current Integrated Schedule for Restart & Power Ascension Activities.Schedule Incorporates Consolidated Schedular Info on Both Interaction Activities.Updates Will Be Provided Twice Per Month.W/One Oversize Graph Project stage: Other ML20207P9931987-01-13013 January 1987 SAR for Tech Spec Limiting Condition for Operation 4.3.1 Change Permitting Safe Shutdown Cooling W/Evaporator- Economizer-Superheater Project stage: Other ML20207P9871987-01-15015 January 1987 Forwards Application for Amend to License DPR-34,changing Tech Specs to Require Both evaporator-economizer Superheater Sections & Both Reheater Sections to Be Available During Operation at Power.Fee Paid Project stage: Request ML20207P9911987-01-15015 January 1987 Proposed Tech Specs,Requiring Both evaporator-economizer Superheater Sections & Both Reheater Sections to Be Available During Operation at Power as Min Number of HXs Project stage: Other ML20207P9891987-01-15015 January 1987 Application for Amend to License DPR-34,requiring Both evaporator-economizer Superheater Sections & Both Reheater Sections to Be Available During Operation at Power as Min Number of Operable HXs Project stage: Request ML20211E1101987-01-26026 January 1987 Rev a to Engineering Evaluation of Procedure to Recover from Actuation of Steam Line Rupture Detection/Isolation Sys for Power Levels Through P2 Project stage: Other ML20210A7571987-01-30030 January 1987 Fort St Vrain 1987 Power Ascension Plan Project stage: Other ML20210A7481987-01-30030 January 1987 Requests Concurrence to Start Up & Operate Facility Through Graduated Rise to Power Up to 100% of Rated Power,Subj to Listed Constraints. Fort St Vrain 1987 Power Ascension Plan Encl Project stage: Other IR 05000267/19870021987-01-30030 January 1987 Partially Withheld Insp Rept 50-267/87-02 on 870106-09 (Ref 10CFR73.21).No Violations or Deviations Noted.Major Areas Inspected:Matl Control & Accounting Project stage: Request ML20210A7401987-02-0202 February 1987 Forwards Updated Nrc/Public Svc Co of Colorado Restart Interaction Schedule, Reflecting Current Target Dates & Recently Completed Items Project stage: Other ML20209G0431987-02-0202 February 1987 Forwards Current Integrated Schedule for Plant Restart & Power Ascension Activities.W/One Oversize Encl Project stage: Other ML20210N8831987-02-0303 February 1987 Forwards Request for Addl Info on 861230 & 870115 Submittals Re Analysis of Firewater Cooldown from 82% of Full Power Project stage: RAI ML20210P0191987-02-0505 February 1987 Summary of 870113 Meeting W/Util Re Completion of Equipment Qualification Program & Program & Approvals Required for Plant Restart Project stage: Meeting ML20210T6861987-02-0505 February 1987 Rev a to Engineering Evaluation of Reanalysis of FSAR Accidents/Transients Relying on EES Cooling. W/Four Oversize Drawings Project stage: Other ML20211D9921987-02-0505 February 1987 Issue a to Economizer-Evaporator-Superheater Cooldowns for Equipment Qualification & App R Events W/Vent Lines (1.5 H Delay) Project stage: Other ML20210T6551987-02-0606 February 1987 Provides Results of Confirmatory Analyses for FSAR Accidents Which Utilize Either EES or Reheater Section of Steam Generator for DHR Project stage: Other ML20210T4361987-02-11011 February 1987 Requests Publication of Fr Notice of Consideration of Issuance of Amend to License DPR-34 & Proposed NSHC Determination & Opportunity for Hearing on 870115 Request Re Operation of evaporator-economizer-superheater Sections Project stage: Other ML20211E9791987-02-12012 February 1987 Forwards Proposed Agenda & Slides for 870226 Meeting W/ Commission & Staff to Secure Commission Approval for Full Power Operation of Facility Project stage: Meeting ML20211D8901987-02-17017 February 1987 Forwards Response to NRC 870203 Request for Addl Info Re Firewater Cooldown from 82% of Full Power,Per Util 861230 & s Project stage: Request ML20207Q7941987-03-0303 March 1987 Forwards Second Request for Addl Info Re Util Analysis of Firewater Cooldown from 82% of Full Power Operation,Based on Review of 861230,870115 & 0217 Submittals Project stage: Approval ML20204G9241987-03-20020 March 1987 Forwards Restart & Power Ascension Schedule,Incorporating Consolidated Schedular Info on NRC-util Interaction Activities.Brief Narrative Description of Scope of Each Line Item Activity Also Encl.W/One Oversize Encl Project stage: Other ML20205B3441987-03-20020 March 1987 Forwards Response to NRC 870303 Second Request for Addl Info Re Firewater Cooldown from 82% of Full Power (Safe Shutdown Cooling) Project stage: Request ML20205M8901987-03-30030 March 1987 Forwards Third Request for Addl Info Re Util 861230,870115 & 0217 Submittals Concerning Analysis of Firewater Cooldown from 82% of Full Power.Major Concerns Re Effects of Transient Loading Due to Seismic Motion or Flow Project stage: RAI ML20205T1701987-04-0101 April 1987 Forwards Oversize Current Integrated Schedule for Facility Restart & Power Ascension Activities Required for Equipment Qualification Completion Certification,Startup/Plant Criticality & Power Ascension to 82%.Related Info Encl Project stage: Other ML20206B6031987-04-0101 April 1987 Forwards Comments Re Implication of Chernobyl Reactor Accident.Design Differences Between Fort St Vrain & Chernobyl Preclude Accident Similar to Chernobyl from Occurring at Fort St Vrain Project stage: Approval ML20206B4591987-04-0303 April 1987 Forwards Summary of Equipment Qualification (EQ) Insp Conducted by NRR & IE on 870126-30.EQ Program Approved. Detailed Results of Insp Will Be Provided Project stage: Other ML20206B3291987-04-0707 April 1987 Submits Daily Highlight.Public Svc Co of Colorado Authorized to Restart & Operate Facility HTGR at Level of Up to 35% Full Power.Facility Out of Operation Since 860531,when Shut Down for Equipment Qualification Mods Project stage: Other ML20206F8871987-04-10010 April 1987 Submits Requested Addl Info for Analysis of Firewater Cooldown for 82% Power Operation,Per Project stage: Other ML20209E3291987-04-27027 April 1987 Provides Written Authorization to Operate Reactor at Up to 35% Full Power,Per Section IV of 870406 Confirmatory Order Modifying License DPR-34 Project stage: Other ML20215H9641987-04-30030 April 1987 Forwards Updated Ga Technologies Procedure 909410, Buckle Users Manual, Per 870330 Request.Manual Updated to Include Revs to Computer Code Required by High Temps & Short Times Assumed for Steam Generator Tube Stress Analysis Project stage: Other ML20215H9731987-04-30030 April 1987 Revised Buckle Users Manual:Creep Collapse of Thin-Walled Circular Cylindrical Shells Subj to Radial Pressure & Thermal Gradients Project stage: Other ML20215J8711987-05-0404 May 1987 Rev a to Evaluation of Test Data for Confirmation of Fire Water Flow Rate to Circulator Water Turbine During EES Cooldown for Safe Shutdown Cooling Project stage: Other ML20215J8551987-05-0404 May 1987 Forwards Rev a to EE-EQ-0057, Evaluation of Test Data for Confirmation of Fire Water Flow Rate to Circulator Water Turbine During EES Cooldown for Safe Shutdown Cooling Project stage: Other ML20214S8361987-05-27027 May 1987 Requests Insp & Audit Per 10CFR50,App B of Licensee Activities Supporting Request for 82% Power Operation. Requests That Insp Be Conducted & Completed within 180 Days Project stage: Other ML20214Q9881987-05-29029 May 1987 Forwards Rept GA909438,Issue Nc, Verification Rept for Buckle Computer Program. Edition of Buckle Code Covered by User Manual Validated & Independently Verified by Rept Project stage: Other 1987-02-11
[Table View] |
Comments on Documents Authorizing Increase of Plant Operating Power to 82%.Editorial Changes Recommended to SERs Re SSE & Tornadoes,Reheater & Metallurgical Facts & Firewater in EES| ML19306G340 |
| Person / Time |
|---|
| Site: |
Fort Saint Vrain  |
|---|
| Issue date: |
06/28/1987 |
|---|
| From: |
Scinto J NRC |
|---|
| To: |
Heitner K NRC |
|---|
| References |
|---|
| TAC-63576, NUDOCS 8711120109 |
| Download: ML19306G340 (1) |
|
Text
_
Note ' t o Ken -Heitner 6/28/87
@g(ckground m
i
'b-From Joe Scinto
(.
.1 Re: FtSt Vrain 82% Package I have a couple of comments on this.
I
- 1) How was 'the limitation on operation above 35% imposed?
By.
Order? by. Confirmatory Action Letter?
l I can't tell whether this letter is the right way to authorize the increase to 82% and to impose 82%'as a-new limit.
This needs
-l
' to be r eviewed by Mr. Schinki's division.-
]
- 2) The first SER - on SSE an'd Tornados - appears to be based priniarily on the Oak Ridge TER.
Somewhere the-STAFF needs to 1
adopt the Oak Ridge work.
(something like "the NRC staff has reviewed the Oak Ridge TER and agrees with. 0ak Ridge's evaluations and conclusions, except as discussed ~below..")-
0 At the bottom of p.2 and top of p.3 there is a discussion of certain (unclear) contingencies (7) in the Oak: Ridge TER.
It's hard to tell what they are, what they relate to,whether we are agreeing with them or disagreeing with them and why?
What does the last sentence of the para at the top of p.2'say?
It's some sort of paraphrase of App.
R.
Is there any conclusion-associated with this statement?
P.3 You need to do more to explain how you draw an probability conclusion about water hammer etc. "from these oualitative statements".
1
- 2) The SER on the reheater contains.a bunch of metallurgical facts
-- but there is almost no connection between all this info and a conclusion that the plant can operate saf ely.
- 3) The SER on firewater in the EES says the objective of the applicants analysis was to show that the primary pressure boundary will remain intact; but all this SER deals with is creep collapse without explanation of why it'is so limited.
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-APR 37 iggy In Reply Refer To:
Docket: 50-267 Public Service Company of Coicrado ATTN: Robert O. Williams, Jr.
t Vice President, Nuclear Operctions
]
P. O. Box 840 Denver, Colorado 80201-0840
Dear Mr. Williams:
-y i
In accordance with the provision of Section IV of the Confirmatory Order Modifying License issued for the Fcrt St. Vrain Nuclear Generating Station on-April 6,1987, I am herewith ~providing written authorization for the Fort St. Vrain reactor to operate in excess of 10 percent of full power.
Nothing in this release shall be construed to modify or' change tim aforement'.oned order, as this is the release specified in that order.
In effect you are now released to aperate up to 35 percent of full power,.
Since y,
^ :
^
Robert D. Martin w
Regional Administrator cc:
Manager, Nuclear Productio.1
- N Fort St. Vrain Nuclear Stat 16805 WCR 191 Platteville, Colorado 80651 e
P. Tomlinson, Manager. Quality Assurance Division (same' address)
T. Murley, Director Nuclear Reactor Regulation Colorado Radiation Control Drogram DfNector 9 E
Colorado Public Utilities L iojon r.
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Table 4.2-7 PERFORMANCE RANGE OF VARIABLE FOR EACH STEAM GENERATOR MODULE Full Load (100%)
One Quarter Load (25%)
O erating Condition P rformance Range Dimensions Minimum Nominal Maximum Minimum Nominal Maximum Helium Flow Ib/hr 278,490 284,170-289,850 81,800-83,500 85,200-0utlet Pressure gsia 686 686 686 589 589 589 Inlet Temperature F
1,357-1,427
.1,467 1,121 1,231 1,341 Outlet Temperature F
736 742 747 612 577 561
' 0.36
=0.36
=0.36 Pressure Drop psi
=3.47
=3.47
=3.47
=
Feedwater/ Main Steam Flow.
Ib/hr 170,000
.192,110 206,500 36,600 48,030 59,600 Outlet Pressure gsia 2,51 2 2,512 2 512_.
2,419 2,419 2,419.
Inlet Temperature F
403' 403~
",403-301 301
~301 Outlet Temperature F
1,005 1,005 1,005 1,000 1,000 1,000 Pressure Drop psi
=520
=590
=29
=45
=65 Reheat Steam F1ow _
lb/hr 187,150 187.150 187,150 45,400 45,400 45,400 Outlet Pressure-gsta 600 600 600 151 151 151 Inlet Temperature F
_ 673 673 673 567 567 -
567 Outlet Temperature F
967 1,002.
.1,022 926
'1,001 1,075 Pressure Drop' psi
=42
=42
=42
=11
=11
=11
- = 1 1iE a so t a%
_92_R.
85 3g
)> Tth
.,-.M 6
i er-s.
...re-n-,-.
w
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,w-,
e
+.-,..,-.-m i - r-w w= = = =
w--wa r.
-,e
m
~~
' ^ bA l D R
u Revision 4.
s, 9.22-5
~
i panelC, co;bol room control panel an;i cont automatic initiation of associated fire sunpression syst rol devices required for i
ems.
Two msoning types of detectors and thermal detectors. detectors are utilized:
l rise, continuous st. rip, or ' heat actuated device 1
bh rate of s.
1 In 'ths' eveH.
fire watches are ds aM ;shed u tet the detectors catoa l ' service, in accordance with Ted.htcal Spedificati i
n be returned to ons.
9.12.3.3.
Fire Suppression Soms Fire Water Systems. The provTdes a reliable water. $9W1y for suppressing fires fire protection water supply system reactor and turb'ne buiidings by supplying fire water t in' both the sprinkler systems, deluge system, fixed water spray o the wet pipe hose reels and yard systems, manual redundant 100% capacity fire water pumps are provide 1500 gpm at 125 pijg TDF Two and the standby _pumVdfe,!.
, each rated for sel engine drive.The main pump is electric m driver with irde Each pump has its own a separate"roca,per.deni power supplies and controls and is loca wall.
divided by a minimum 3-hour fire rated concrete The firs s ter pumpt-communicate directly with the main cr311ng tower basint.a
(
is supplied to the main cooling t Fire water via a circulating water makeup pump.ower basin from two storage pcads nake up rate exceeds the The normal cooling tower water systems.
The water inventory in eachrate at which water is used by t water approximately 13 pond is maintained at million gallons by watsr sources.
pur. ped from two river feet above grade level maintains a constadt h pproximately 132 storage as a. source of water making frequent starting of a
n the system.
The re 4ter pumps unnccessary for minor demand on the systca i
fire water pump Water for fire suppression is provided from the ffre to the station by means of a 10 sur rounding the station.
inch ' underground water pumos The fire water is then distributed to t main loop wet pipe sprinkler
- systems, systems, deluge ' systems, fixed the underground loop. manual hose stations and fire hydrants v wa ter - ~ spray Alarm monitored cMk ' valve's" are enh of the nine r es from control room personnel to the demand forfire water supply r ser provided in suppression systems are shown in Figure 9.12-2 fire water.
These water r
The wet pipe sprinkler systems utilize thermally a futibie: link spray nozzles ano are connected with fi i firi _. Wa t r supply system. such that water will be discha rge xed' piping to the ime.cSately from the nozzles opened by fire systen protects-the followiy.treas:
The wet pipe sprinkler the steam driven boiler feed I
a w'.
'J-.
d '. - -
..