ML17264B179
| ML17264B179 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 02/08/1996 |
| From: | Dan Dorman NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9602130448 | |
| Download: ML17264B179 (26) | |
Text
February 8, 1996 LICENSEE:
Vermont Yankee Nuclear Power Corporation FACILITY:
Vermont Yankee Nuclear Power Station
SUBJECT:
SUMMARY
OF JANUARY 25,
- 1996, MEETING WITH REPRESENTATIVES OF VERMONT YANKEE NUCLEAR POWER CORPORATION On January 25, 1996, pursuant to notice, the NRC staff met with representatives of Vermont Yankee Nuclear Power Corporation (the licensee) at Brattleboro, Vermont, to discuss the status of licensing issues related to the Vermont Yankee Nuclear Power Station (VYNPS).
A list of attendees is provided as Attachment l.
A handout of issues discussed at the meeting was prepared by the licensee and is provided as Attachment 2.
Attachment 3 contains a brief history and schedule for the licensee's plan to convert the Technical Specifications (TS) for VYNPS to the improved standard TS.
In addition, the licensee discussed its philosophy behind its recent reorganization of the engineering department.
The licensee also briefly discussed actions it has taken and is taking to verify the adequacy of its LOCA analyses in light of concerns identified regarding the analyses for Maine Yankee.
1 Sincerely, I
Original signed by:
. Daniel H. Dorman, Project Manager Project Directorate I-1
'ivision of Reactor Projects I/II
";.Office of Nuclear Reactor Regulation
,r Docket<No., 50-244, Attachments::
1.,'.. Li.st of Attendees "',z
, 2.
NRR,Meeting-l/25/96 Improved TechSpecs, cc w/encls:
See',next'page
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UNITED STATES NUCLEAR REGULATORY COMMISStON WASHINGTON, D.C. 20555-0001 February 8,
1996 LICENSEE:
Vermont Yankee Nuclear Power, Corporation FACILITY:
Vermont Yankee Nuclear Power Station
SUBJECT:
SUMMARY
OF JANUARY 25,
- 1996, MEETING WITH REPRESENTATIVES OF VERMONT YANKEE NUCLEAR POWER CORPORATION On January,25, 1996, pursuant to notice, the NRC staff met with representatives of Vermont Yankee Nuclear Power Corporation (the licensee) at Brattleboro, Vermont, to discuss the status of licensing issues related to the Vermont Yankee Nuclear Power Station (VYNPS).
A list of attendees is provided as Attachment 1.
A handout of issues discussed at the meeting was prepared by the licensee and is provided as Attachment 2.
Attachment 3 contains a brief history and schedule for the licensee's plan to convert the Technical Specifications (TS) for VYNPS to the improved standard TS.
In addition, the licensee discussed its philosophy behind its recent reorganization of the engineering department.
The licensee also briefly discussed actions it has taken and is taking to verify the adequacy of its LOCA analyses in light of concerns identified'regarding the analyses for Maine Yankee.
Sincerely, Docket No. 50-244 Daniel H. Dorman, Project Manager Project Director ate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachments:
1.
List of Attendees 2.
NRR Meeting-1/25/96 3.
Improved Tech Specs cc w/encls:
See next page
'I
D. Reid Vermont Yankee Nuclear Power Corporation CC:
Vermont Yankee Nuclear Power Station Hr. J.
P. Pelletier, Vice President Yankee Atomic Electric Corporation 580 Hain Street
- Bolton, HA 01740-1398 Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 R.
K. Gad, III Ropes
& Gray One International Place
- Boston, MA 02110-2624 Hr. Richard P.
- Sedano, Commissioner Vermont Department of Public Service 120 State Street, 3rd Floor Montpelier, VT 05602 Public Service Board State of Vermont 120 State Street Montpelier, VT 05602
- Chairman, Board of Selectmen Town of Vernon P.O.. Box 116
- Vernon, VT 05354-0116 Mr. Jay Thayer, Vice President Vermont Yankee Nuclear Power Corporation Ferry Road Brattleboro, VT 05301 Mr. Robert J;. Wanczyk, *Plant Manager Vermont Yankee..Nuclear Power Statio~
P.O.
Box 157. Governor Hunt Road
- Vernon, VT 05354
,( P G.
Dana Bisbee, Esq.
Deputy Attorney General 33 Capitol Street
- Concord, NH 03301-6937 Resident Inspector Vermont Yankee Nuclear Power Station U.S. Nuclear Regulatory Commission P.O.
Box 176
- Vernon, VT 05354 Chief, Safety Unit
, Office of the Attorney General One Ashburton Place, 19th Floor
- Boston, MA 02108 Hr. David Rodham, Director ATTN: James Huckerheide Massachusetts Civil Defense Agency 400 Worcester Rd.
P.O.
Box 1496 Framingham, MA 01701-0317 Mr. Raymond N. HcCandless Vermont Division of Occupational and Radiological Health Administration Building Montpelier, VT 05602 CI Hr. J. J. Duffy Licensing Engineer Vermont Yankee Nuclear Power Corporation 580 Main Street
- Bolton, HA 01740-1398
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~LIAT OF ATT ATE EE
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>C~NS E REPRESENTATIVES FOR V
0 T YANKEE NUCLEAR POWER STATION RATTLEBORO VERNON JANUAR 5
996 Dan Dorman Jay Thayer Bob Sojka Jim Duffy Dave HcElwee Bill,Sherman I TIO NRC/NRR/Project Directorate I-I Vermont Yankee Vermont Yankee Vermont Yankee Vermont Yankee State of Vermont
~ITAL Project Hanager VP Engineering Ops.
Support Mgr.
Licensing Engineer
'iaison Engineer Nuclear Engineer
NIMMeeting-1/25/96 Plant Operating Summary Projected Year End Capacity Factor - 86.7% (VYBest Ever)
New Lost Time Accident Record - Over 600 Days Without A Lost Time Accident October Was our best ever single'month for Mwe (as a result ofthe new turbine)
Scram of 12/8/95 Allowed several operational issues to be resolved (Generator balance, AOG H2 Monitors, FDW Nozzle calibration, FDW level control adjustments)
Engineering Reorganization-12/14/95-Integrated, Speed ofResponse, System Engineers, 1996 Refueling Outage-29 1/2 days, 45 FDW Heaters,.Torus Inspection, FOST, SW, RPV Shroud, MOV's, Appendix R Fixes, FDW Check Valve replacement Condensate Demineralizer Panel Alarm Fire of 1/10/96 AOG Allegation VYLOCAAnalysis Solomon Stability Monitor4 Alpha Computer Scram Solenoid Pilot Valves 1995 Refueling Outage Vermont Yankee replaced all SSPV's with 15 year Viton parts Startup, May, 1995 all rods successfully scrammed (5/o=.317, T.S.=.358)
November, 1995, 50% rods scrammed 30 MS slower for 5% insertion (3.3.C.1-0.358 ms)
November 27, 1995 three sets ofSSPV's delivered to ASCO/GE for testing Modified end caps needed to allow Viton Diaphragms to Hex adequately Vermont Yankee, Limerick, Oyster Creek, Cooper have Standard (early)End Caps Tendency for Standard End Caps to exhibit degraded time response over time Sticking ofthe Viton diaphragm to its internal seat observed (viton formula problem) 118 SSPV identified as the limitingcomponent December 8, 1995 Vermont Yankee measured 5% insertion time 0.356 118 exhaust end caps and diaphragms replaced using revision G end caps (now.328) 15 rods scrammed on 1/9/96, 4 ms average change (15 rod average.332 vs.328)
Preparing a draft Tech Spec Change to.500 ms GE Apparent Cause memo Appendix R July, 1995 -Present - Vermont Yankee identified several App. R concerns, LER 95-20 "Hot Shorts" (IN92-18), SRV Cable Repair, RCIC Initiation, RCIC HELB Fuse Replacement
Four independent, multi-discipline task force teams (Eval, Design, SA, Root Cause)
Root Cause-Lack ofUnderstanding, Weak SSCA, Poor Documenataion, Lack of Ownership, Not a Living Document September, 1995 Appendix R Project Team-resolve open items, rewrite 1985 Safe Shutdown Capability Analysis (SSCA), design changes, refine program 10 individuals. 600 of2500 drawings reviewed Continuous Dialog with NRC-IR dated 12/22/95, 3 Violations, 2 URI's, Enforcement Conference January 11, 1996 Compensatory Fire Watches, Operations Standing Order, Engineering Reorganization Detection, Suppression, FBL, Equipment Redundancy, Surveillance, Control of Combustibles provide additional barriers Full compliance to be achieved by the end ofthe 1996 Refueling Outage Anticipate the following exemptions to be submitted in 1996; LNP only for Control Room fires Taking credit for Vernon Hydro Changing safe shutdown path for RB3 to ADS & CS Updating fuse replacement Design Changes: Remote Vernon Tie Transfer, SRV cabling, Pre-installed Fuses (eliminate all other systems except RHR, SRV Hot Short)
Misc.-SE as FBL, Switchgear Room Smoke Detectors Torus Temperature Vermont Yankee was one ofthe first BWR's to increase allowable torus temperature in the mid 1980's (Amendment 88). Subsequently, the BWROG has done additional generic work, but work that Vermont Yankee did not participate in.
Adiscrepancy was noted during the 1994 SWOPI between TS 3.7.A.l.a (100 degree torus temp during power operation) and FSAR Figure 14.6-7 (indicates an initialtorus temperature of90 degrees). The discrepancy was evaluated by engineering assessment, also done in 1994, which showed no significant impact on plant design bases, but recommended formal update ofa number ofanalyses.
Several ofthose analyses have been updated.
Work done by the BWROG over the last 10 years, new work done by the Severe Accident Management group, and the ECCS strainer plugging issue have identified new issues which were not addressed by the Mid 1980 Vermont Yankee work.
Since Vermont Yankee did not participate in the BWROG torus temperature task, we now must negotiate with GE and Teledyne and either buy in to the BWROG work or redo the containment clearing loads ourselves.
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What we believe is the likelyoutcome, willbe an in-house 50.59 evaluation, followed by a FSAR Revision in the February, 1996 time frame. It is possible that instrument inaccuracies may come into play and eventually limitthe Vermont Yankee torus temperature to 95 degrees.
In the interim, Vermont Yankee has administratively limited the torus temperature to 90 degrees via Standing order 19.
Bulletin 95-02 (Debris Plugging)
Vermont Yankee's response dated November 16, 1995 documented the following; Previously (1988) upgraded our strainer design which significantly improved surface area.
Have used RHR during normal testing and an actual 1991 transient.
'horoughly cleaned the torus during the last outage.
Have FME controls and closeout procedures.
Have extensive video footage and photographs ofall torus areas.
Scheduled another torus cleaning during the 1996 refueling outage.
Torus water clarity at Vermont Yankee allows the strainers to be viewed each refueling.
Inspections have consistently been done by a senior Operations Supervisor Inspections are done Rom directly above the strainers, using underwater lights.
Vermont Yankee has recently (12/7/95) performed an STP to confirm strainer performance. This was a very significant effort and confirmed operability As a result ofthis test, Vermont Yankee submited a suinmary report on 12/18/95.
Bulletin 96-01 (Logic Testing)
Received on 1/19/96. Response due in 60 days.
GL 95-07 (Pressure Locking and-Thermal Binding)
Vermont Yankee submitted a submitted a 60 day response to GL 95-07 on October 16, 1995.
We are have screened all power operated safety related valves (HPCI 20, RCIC 20, RHR 25A/B, RHR 26A, HPCI 14). There are no safety related air operated or hydraulically operated gate valves at Vermont Yankee, therefore, this issue is limited to the MOV's in the GL 89-10 scope. There are 85 MOV's in the GL 889-10 Program.
Six MOVgate valves were modified during the 1995 refueling outage (CS 11A/B, CS 12A/B, HPCI-19, RCIC-21)
We attended the November 2, 1995 NRC Public Workshop and continue to participate with the BWROG and maintain a dialog with the NRC on these issues.
Our next submittal willbe in February, 1996.
GL 89 MOV'S 50 MOV's willbe modified during the 1996 Outage (EDCR-95-407) 6 motor/actuator replacements-V10-17, 27A/B, V23-19,20,21 Diagnostic Test Sensors (3 Smartstems, 16 Quik Stems, 4 2 Yoke Strain Gauges) V10-25A, 39A, 39B, and V2-53A,/B, V10-17,25B, 27A/B, 34A/B, V23-14,19.
57, V70-19A/B, 20, VG-22A/B 8h V13-27, 132 Quick Disconnect Connectors-V2-53A/B, V10-17, 25A/B, 34A, V13-16, 20, 19, 20, 21, 57, VG-22 Wiring and Oveload Protection Per MOVESG 8h Appendix R Hot Shorts Expected Cost-$ 430,000 MOVcoloseout leter submitted on 12/29/95 Tech Spec Proposed Changes Some ofthe following proposed changes could be CBLA's. We hope to discuss the cost accounting methods for qualifying as CBLA's.
Diesel Fuel Oil (PC 178)
Vermont Yankee has recently installed a new oil storage tank for our house heating boilers, and no longer needs to continuously add new fuel oil to the emergency diesel Fuel Oil Storage Tank. As a result, we have been able to purchase high quality fuel oilwith a pour point of-27 degrees.
We have also installed a temperature monitoring system for the tank contents, and continuously monitor fuel oil temperature. There is a Tube-Lock tent type structure which completely surrounds the FOST and can be heated in the event oil temperature drops to within ten degrees of the pour point. Operator guidance exists for the operators in the form ofa Standing Order which ensures operability.
As a result, there is no challenge to operability, and we intend to integrate this change into our conversion to Improved Tech Specs.
Administrative Change (PC 180)
This change reQects a great deal ofwork by NRR and VY, and we would like to see it through to completion. The final draft has completed plant review and was presented to PORC on January 24, 1996.
Stack Gas monitor (PC 181)
As a result of a problem experienced earlier with the stack gas high range monitor, we intend to propose a change to Note 7 ofTable 3.2.6 which currently reads "If the control room indication cannot be restored within 30 days, the reactor shall be in hot shutdown within six hours and in cold shutdown within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />"'he Proposed new wording willread "From and after the date that this parameter is unavailable by Control Room indication, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> ensure that local sampling capacity is available. Ifthe Control Room indication is not restored within 7 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.7 within the subsequent 14 days, outlining the action taken, the cause ofthe inoperability, and the plans and schedule for restoring the system to operable status."
First Notch Insertion Time We are currently preparing a proposed change to the first notch (notch 46) insertion time to change this reauirement &om.358 to.500 ms in the event our testing demonstrates this is necessary.
Appendix S, Option B NRC has amended Appendix J with an option B to provide a performance based test interval option for utilities with a good Type A performance history and an experience base for Type B & C Testing. Requires evaluation ofperformance history ofcontainment, penetrations, isolation valves and risk.
We hope to be able to take advantage of Option B and submit a change to Appendix J sufBciently early in 1996 to be implemented during the fall Refueling Outage.
Secondary Containment We willpropose a change to Section 3.7.C making it consistent with ITS. This change willalso add surveillance requirements to better ensure secondary containment integrity is maintained when required and to provide guidance when secondary containment integrity is lost.
KCCS During Shutdown &Refueling Currently the Vermont Yankee Tech Specs provide three levels ofECCS availability; all systems, no systems and 3.5.H.4 which states:
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When the reactor is in the refueling condition both LPCI subsystems, or both Core Spray systems or one diesel generator may be inoperable.
The proposed change would require two Core Spray subsystems, or two LPCI subsystems or one CS and one LPCI subsystem during refueling.
Shutdown Margin This proposed change revises the c'urrent requirements for control rod and control rod drive maintenance by incorporating ITS language for the shutdown margin specifications to allow calculation for determination ofthe highest worth rod.
Control Rod Over-Travel Surveillance The Vermont Yankee Tech Specs currently require testing the control rod over-travel indication followingmaintenance when the rod has been uncoupled. This creates a problem because it is difHcultto withdraw an uncoupled rod without inadvertently recoupling it due to the insert signal that is momentarily generated.
We willpropose a change that makes this area consistent with ITS.
SRV Setpoint Tolerance &95% Restriction We willchange the setpoint tolerance from+/- 1% to +/- 3% via a Bases change We plan to submit a change to remove the 95% restriction with 1 SRV inoperable SW Subsystem We willeither submit a change to clarify a SW Subsystem, roll this into the ITS Conversion, publish an interpretation, or'some combination ofthese alternatives Conversion to Improved Tech Specs As formally stated in our recent letter, Vermont Yankee has committed to convert our current tech specs to the NUREG 1433, Rev.1 version ofImproved Tech Specs.
The process is expected to take approximately two years, with implementation followingthe 1998 early spring Refueling Outage. Conversion is the right thing for Vermont Yankee.
It's expensive and challenging, but willresolve the ambiguities, missing action statements, and take a giant step toward design basis configuration.
At the present time, we have selected Rich Pagodin as Project Manager, who willreport to Bob Sojka for this task. Other stafF willbe assigned early next year, following development ofthe Project Plan and contractor selection.
During the next 12 months, we have budgeted and expect to spend over one million dollars on the Tech Spec Conversion Project.
We have been and expect to continue to work with the other BWR 4's on this efFort. On 2/1/96 8h 2/2/96 we willbe meeting with GE, GP and EXCEL to discuss their assistance in developing the Vermont Yankee ITS.
Today, we hope to explore an appropriate process should the conversion effort uncover potential FSAR or TS compliance issues, 24 month cycles, power uprate, containment delta p.
C
C3 Improved Tech Specs CI History ofImproved Tech Specs
+ Interim Policy Statement on Tech Spec Improvements, February 1987 o Five NUREG Versions Approved by NRC, September 1992
+ Revision 1 of NUREG's issued, July 1995 a 50% Converted by 1997 O Benefits ofImproved Tech Specs a Operational Safety is Improved a Recognition and Understanding of Safety Significance is Improved
+ Administrative Burdens are Reduced a Quantity ofSurveillance Testing is Substantially Reduced
+ Conversion Becomes a Self Assessment CI Operational Safety is Improved e Complexity of Tech Specs is Reduced
+ Reformatted to a User-Friendly Format a Surveillance Testing is Reduced a Challenges to Personnel &Equipment are Reduced o Ambiguities &Cascades are Eliminated
+ Licensing Bases are Confirmed Q Potential Cost Savings o UtilityConversion Alliance o Quality, Program Improvements a Similar Documents [Specifications, Technical Requirements Manual, Training Materials, SFDP, Generics]
a Submittal &Review Improvements a Common GE Studies Q Recognition &Understanding ofSafety Significance is Improved
+ Precise Wording &Significantly Expanded Bases a Long Standing Operability, Surveillance &ActionStatement Issues are Resolved
+ Obscure Requirements &Completion Times are Clarified a 50.59 Safety Analyses are Simplified C3 Administrative Burden Reduced a Considerable Reduction in TS Changes
a Many Requirements Relocated
+ Fewer LER's, NOV's, ETS/DW's
+ Favorable Regulatory Environment a Fewer Surveillance's
+ Greater Schedule Flexibility
+ Giant Step Toward PLEX Cl Impediments to ITS Conversion
+ Cost Estimated to be $1,800,000 a 20 Month Schedule o Design Bases Reconstitution
+ Power Uprate Decision
+ BWROG Products a 18 Vs 24 Month Cycle Decision
4 H
1
Vermont Yankee Tech Spec Conversion Task Name Tech S Conversion Detail Plan Select Team Leader Pre e Pro ect Plan Resolve BWROG Issues Draff Bid S Select Pro ect Team Evaluate Bidders Finalize Sco Define Processes Contract Contractor Pre are ITS Submittals DraftS litRe rt Establish TRM Pre re Packa es Draft Procedure Revs Submittals Com lete Review ITS Develo Bases Tech Reviews PORC Reviews NSARC Reviews Reviews Com lete NRC Review Review ITS Submittal Review Other Submittals Resolve Issues NRC A roval Final Procedures Train Staff Train 0 rators Train Mana ers Im lement 96 Refuel Outa e
98 Refuel Outage Printed: 10/DecI95 Pago 1
Duration 28.16 m 4.47 m 1.00 m 2.00 m 1.00 m 1.00 m 2.00 m 1.00 m 1.00 m 1.00 m 0.00 d 14.00 m 1.00 m 14.00 m 10.00 m 0.00 m 14.00 m 14.00 m 12.34 m 12.24 m 11.14 m 0.00 d 9.00 m 9.00 m 6.00 m 0.00 d 2.00 m 9.62 m 8.46 m 8.46 m 0.00 d 1.00 m 1.00 m 1996 1995 1998 1997 Q4 Q1 Q2 Q3 Q4 Q1 Q2 Q3 Q4 Q1
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Tan A. Chaffee E. Jordan A. Thadani R. Conte, RI ACRS W.
Dean I.I Miraglia
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PUBLIC PDI-I Reading D. Dorman J. Linville, RI
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