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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H8701999-10-15015 October 1999 Responds to Recipient Informing NRC of from W Simoneau to Rhode Island Atomic Energy Commmission & Proposed Minutes from Rhode Island Commission Meeting of 990923 ML20205L0991999-04-0707 April 1999 Forwards Insp Rept 50-193/99-201 on 990322-26.No Violations Noted.Insp Included Review of Activities Authorized for Facility ML20155G4431998-10-14014 October 1998 Confirms 981014 Telcon That T Tehan Will Take Two Year re- Qualification Exam at Same Time SRO License Will Be Changed from Inactive to Active Status ML20154J3051998-10-13013 October 1998 Forwards Insp Rept 50-193/98-202 on 980921-25.No Violations Noted.Various Aspects of Safety Program Inspected Including Selective Exams of Procedures & Representative Records & Interviews with Personnel ML20203E0421998-02-13013 February 1998 Forwards Insp Rept 50-193/98-201 on 980113-15.No Noncompliance or Safety Concerns Were Identified ML20199E8141997-11-12012 November 1997 Forwards Amend 25 to License R-95 & Safety Evaluation.Amend Corrects Omission from Previous TS Amend ML20211J0081997-10-0202 October 1997 Forwards Corrected Copy of Page 29 of Amend 24 of TS Re Change Made by Amend 20 ML20217E2851997-09-23023 September 1997 Forwards Amend 24 to License R-95 & Se.Amend Clarifies TS Requirements & Corrects Typographical Errors ML20198F0111997-08-0505 August 1997 Informs That Responsibility for Non-Power Reactor Insp Program Has Been Transferred from Regional Ofc to Nrr. Addresses Listed ML20140H7241997-06-17017 June 1997 Forwards Amend 23 to License R-95 & Se.Amend Removes Reactor Coolant Inlet Temp as TS Requirement in SL & Lsss,Section 2.1.1 & 2.2.1,respectively ML20140F8331997-06-11011 June 1997 Forwards Results of 970528 Operator Initial Exam at Rhode Island Aec.W/O Encl ML20148J8071997-06-11011 June 1997 Forwards Operator Licensing Initial Exam Rept 50-193/OL-97-01 During Wk of 970526 ML20196G8941997-05-30030 May 1997 Informs of Error in ,Concerning Changes to Riaec License.Ts Page 63 Correct ML20140E7681997-04-23023 April 1997 Forwards Insp Rept 50-193/97-01 on 970311-14.No Violations Noted ML20135E1481997-03-0404 March 1997 Requests Matl Listed in Encl 1, Ref Matl for Reactor/Senior Reactor Operator Licensing Exams, at Least 60 Days Prior to 970526.Procedures for Administration & Review of Written Exams Requested ML20132E2351996-12-18018 December 1996 Forwards Amend 22 to License R-95 & Safety Evaluation.Amend Provides for Extension of Annual TS Surveillances for Safety Blade Testing & Reactivity Calculations ML20135E3531996-12-0505 December 1996 Requests One Time Extension to Allow Safety Blade Testing & Reactivity Calculations as Outlined Per Encl.One Month Extension Requested to Allow Testing to Be Done in Jan 1997 ML20134K4811996-11-13013 November 1996 Informs That B Smith,SOP-10724-1,has Retired & No Longer Needs to Maintain License ML20117A8001996-08-20020 August 1996 Forwards Info Which Constitutes Second Annual Rept Required by Rev One to TS ML20096D4081996-01-12012 January 1996 Provides Answers to Concerning Rev of Rhode Island Nuclear Science Ctr TS to Combine Radiation Safety Committee & Reactor Utilization Committee Into Single Committee Called Nuclear & Radiation Safety Committee ML20083M5121995-05-12012 May 1995 Forwards Second Rev to ECCS for Facility.Rev Incorporates Comments from Design Review Conducted by Anl ML20082S0001995-04-18018 April 1995 Advises That Shipment Id R95-030995B Made Successful Transit from Point of Origin to Destination on Schedule ML20082R9971995-04-0505 April 1995 Advises That 10CFR73 Shipment Id R95-030995A Successfully Transported from Point of Origin to Destination on Schedule ML20081J0781995-03-20020 March 1995 Forwards Rev of TS to Combine Radiation Safety Committee Reactor Utilization Committee Into Single Committee Called Nuclear & Radiation Safety Committee ML20078R3571994-12-16016 December 1994 Notifies of stand-down of Shipment W/Id Numbers R95-111894A, R95-111894B & Rescheduling of Shipment.Nrc to Be Notified of New Shipment Dates & New Id Numbers to Be Assigned ML20078R5861994-12-14014 December 1994 Proposes Rev of TS to Require Sampling of Secondary Coolant Sys for Radioactivity (TS 4.3.b) on Weekly Basis & Deletion of Requirement for Secondary Radiation Detector,Per Discussion W/Nrc.Revised TS Page 42 Encl ML20080B1411994-11-17017 November 1994 Advises That for Purposes of Completion of Notification Requirements Under 10CFR73.72,original Enrichment of Sf Assemblies Was 93%,appropriate Governors Notified According to NRC Requirements & Armed Escorts Will Be Provided ML20078B6241994-10-0707 October 1994 Forwards Ri Nuclear Science Ctr Proposed 3 MW or Higher ECCS Plan ML19346J0111994-08-24024 August 1994 Informs That Annual Rept for 1993-1994 Would Be Administrative Burden than Technical Value.Full Rept Will Be Submitted for 1994-1995 ML20072M6941994-08-24024 August 1994 Forwards Change to Physical Security Plan,Per 10CFR50.54(p)(2).Encl Withheld ML20072S2751994-08-24024 August 1994 Proposed That Section 3.7.1 of TS Be Changed as Listed, Concerning Rev of TS to More Clearly Define Allowed Reactor Operation W/O Particulate or Gaseous Stack Effluent Monitor in Svc ML20071G1801994-07-0505 July 1994 Notifies That Ef Spring Retired as Employee of Riaec & No Longer Has Need to Maintain Operators License at Facility Effective 940628.Spring RO License OP-2365-11 Should Be Expired,Per 10CFR50.74(b) ML20069H4681994-06-0101 June 1994 Forwards Rhode Island Nuclear Science Ctr Proposed 3 MW or Higher Emergency Core Cooling Sys Plan ML20069J6041994-05-17017 May 1994 Responds to NRC Ltr Re Violations Noted in Insp Rept 50-193/94-01.Corrective Actions:Revision of Procedures & Radiation Safety Guide Has Started Which Would Be Completed by 940731 Rather than 940701 Due to Delays ML20029D9091994-04-29029 April 1994 Ack Receipt of 940413 Response to Insp Rept 50-193/94-01 ML20070N7331994-04-13013 April 1994 Informs That 10CFR20 Training Requirements Fulfilled Re New Requirements Issued on 940223 Per Insp Rept 50-193/94-01 ML20063K7901994-02-18018 February 1994 Forwards Preliminary Rept on Ri Nuclear Science Ctr Conversion from HEU to LEU Fuel ML20063G0961994-01-31031 January 1994 Forwards Rev 1 to Tech Specs,Including Revs Resulting from Review Process to Date ML20058K3591993-12-0808 December 1993 Forwards Insp Rept 50-193/93-04 on 931116-18.No Violations Noted ML20058G8291993-12-0303 December 1993 Submits Change to Ri Atomic Energy Commission Physical Security Plan.Change Withheld ML20058A6551993-11-17017 November 1993 Forwards Revised Copy of Proposed TSs for License R-95, Incorporating Questions Received from NRC to Date ML20057C2411993-09-17017 September 1993 Forwards Insp Rept 50-193/93-03 on 930810-18.No Violations Noted ML20056H3101993-09-0202 September 1993 Forwards Revised Emergency Plan,Reflecting Comments from Recent NRC Region I Review of Plan.Copy of Old Plan Also Encl ML20056H2801993-08-24024 August 1993 Requests Addl Info to Continue Review of Application for Amend of OL R-95,per 921222 Submittal ML20045H4281993-06-30030 June 1993 Provides Info That Has Become Available Since Revised 10CFR20 Became Effective on 910620 & Forwards Two Press Releases Re Issuance & Implementation of Revised Part 20 ML20056C1451993-03-18018 March 1993 Forwards Insp Rept 50-193/93-02 on 930223-25.No Violations Noted.Written Procedures for Some Health Physics Operations Not Formalized ML20128G6661993-02-0404 February 1993 Forwards Safeguards Insp Rept 50-193/93-01 on 930119-22.No Safety Concerns or Violations Noted ML20044F1841993-01-28028 January 1993 Forwards Reactor & Senior Reactor Operator License Certificates for Jj Cunningham & Tn Tehan,Respectively,Per Commission Request.W/O Encls ML20128E7271993-01-28028 January 1993 Advises That 921130 & 930107 Revs 4 & 5,respectively,to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20127H2611993-01-13013 January 1993 Forwards Revised Pages to Sar,Rev 1,addressing Issues Discussed in 930131 Telcon Re Amended Facility License,Leu Reactor Startup Plan,Reactor Core & Control Elements,Safety Sys Settings & Beryllium Lifetime 1999-04-07
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20155G4431998-10-14014 October 1998 Confirms 981014 Telcon That T Tehan Will Take Two Year re- Qualification Exam at Same Time SRO License Will Be Changed from Inactive to Active Status ML20211J0081997-10-0202 October 1997 Forwards Corrected Copy of Page 29 of Amend 24 of TS Re Change Made by Amend 20 ML20196G8941997-05-30030 May 1997 Informs of Error in ,Concerning Changes to Riaec License.Ts Page 63 Correct ML20135E3531996-12-0505 December 1996 Requests One Time Extension to Allow Safety Blade Testing & Reactivity Calculations as Outlined Per Encl.One Month Extension Requested to Allow Testing to Be Done in Jan 1997 ML20134K4811996-11-13013 November 1996 Informs That B Smith,SOP-10724-1,has Retired & No Longer Needs to Maintain License ML20117A8001996-08-20020 August 1996 Forwards Info Which Constitutes Second Annual Rept Required by Rev One to TS ML20096D4081996-01-12012 January 1996 Provides Answers to Concerning Rev of Rhode Island Nuclear Science Ctr TS to Combine Radiation Safety Committee & Reactor Utilization Committee Into Single Committee Called Nuclear & Radiation Safety Committee ML20083M5121995-05-12012 May 1995 Forwards Second Rev to ECCS for Facility.Rev Incorporates Comments from Design Review Conducted by Anl ML20082S0001995-04-18018 April 1995 Advises That Shipment Id R95-030995B Made Successful Transit from Point of Origin to Destination on Schedule ML20082R9971995-04-0505 April 1995 Advises That 10CFR73 Shipment Id R95-030995A Successfully Transported from Point of Origin to Destination on Schedule ML20081J0781995-03-20020 March 1995 Forwards Rev of TS to Combine Radiation Safety Committee Reactor Utilization Committee Into Single Committee Called Nuclear & Radiation Safety Committee ML20078R3571994-12-16016 December 1994 Notifies of stand-down of Shipment W/Id Numbers R95-111894A, R95-111894B & Rescheduling of Shipment.Nrc to Be Notified of New Shipment Dates & New Id Numbers to Be Assigned ML20078R5861994-12-14014 December 1994 Proposes Rev of TS to Require Sampling of Secondary Coolant Sys for Radioactivity (TS 4.3.b) on Weekly Basis & Deletion of Requirement for Secondary Radiation Detector,Per Discussion W/Nrc.Revised TS Page 42 Encl ML20080B1411994-11-17017 November 1994 Advises That for Purposes of Completion of Notification Requirements Under 10CFR73.72,original Enrichment of Sf Assemblies Was 93%,appropriate Governors Notified According to NRC Requirements & Armed Escorts Will Be Provided ML20078B6241994-10-0707 October 1994 Forwards Ri Nuclear Science Ctr Proposed 3 MW or Higher ECCS Plan ML20072S2751994-08-24024 August 1994 Proposed That Section 3.7.1 of TS Be Changed as Listed, Concerning Rev of TS to More Clearly Define Allowed Reactor Operation W/O Particulate or Gaseous Stack Effluent Monitor in Svc ML19346J0111994-08-24024 August 1994 Informs That Annual Rept for 1993-1994 Would Be Administrative Burden than Technical Value.Full Rept Will Be Submitted for 1994-1995 ML20072M6941994-08-24024 August 1994 Forwards Change to Physical Security Plan,Per 10CFR50.54(p)(2).Encl Withheld ML20071G1801994-07-0505 July 1994 Notifies That Ef Spring Retired as Employee of Riaec & No Longer Has Need to Maintain Operators License at Facility Effective 940628.Spring RO License OP-2365-11 Should Be Expired,Per 10CFR50.74(b) ML20069H4681994-06-0101 June 1994 Forwards Rhode Island Nuclear Science Ctr Proposed 3 MW or Higher Emergency Core Cooling Sys Plan ML20069J6041994-05-17017 May 1994 Responds to NRC Ltr Re Violations Noted in Insp Rept 50-193/94-01.Corrective Actions:Revision of Procedures & Radiation Safety Guide Has Started Which Would Be Completed by 940731 Rather than 940701 Due to Delays ML20070N7331994-04-13013 April 1994 Informs That 10CFR20 Training Requirements Fulfilled Re New Requirements Issued on 940223 Per Insp Rept 50-193/94-01 ML20063K7901994-02-18018 February 1994 Forwards Preliminary Rept on Ri Nuclear Science Ctr Conversion from HEU to LEU Fuel ML20063G0961994-01-31031 January 1994 Forwards Rev 1 to Tech Specs,Including Revs Resulting from Review Process to Date ML20058G8291993-12-0303 December 1993 Submits Change to Ri Atomic Energy Commission Physical Security Plan.Change Withheld ML20058A6551993-11-17017 November 1993 Forwards Revised Copy of Proposed TSs for License R-95, Incorporating Questions Received from NRC to Date ML20056H3101993-09-0202 September 1993 Forwards Revised Emergency Plan,Reflecting Comments from Recent NRC Region I Review of Plan.Copy of Old Plan Also Encl ML20127H2611993-01-13013 January 1993 Forwards Revised Pages to Sar,Rev 1,addressing Issues Discussed in 930131 Telcon Re Amended Facility License,Leu Reactor Startup Plan,Reactor Core & Control Elements,Safety Sys Settings & Beryllium Lifetime ML20126F4461992-12-22022 December 1992 Forwards Rev 1 to SAR for Low Enriched Fuel Conversion of Ri Nuclear Science Ctr Research Reactor, Incorporating Questions Forwarded by NRC 920914 & 1102 Ltrs & Original & Revised Tech Specs,Per ANSI N378-1974 ML20116L3711992-11-0202 November 1992 Advises That Listed Multiple Choice Question B 016 from 921027 Initial/Requalification Exam Had Two Possible Answers.All Other Questions/Answers Resolved Satisfactorily at Exit Meeting ML20099A6181992-07-23023 July 1992 Forwards Rev 1 to SAR for Low Enriched Fuel of Rhode Island Nuclear Science Ctr Research Reactor, Per Telcon W/M Mendonca.Rev Updates Analysis of LOCA to Reflect Beamport Operational & Design Considerations ML20101U1911992-07-17017 July 1992 Forwards SAR for Low Enriched Fuel Conversion of Rhode Island Nuclear Science Ctr Research Reactor ML20091Q3981992-01-23023 January 1992 Forwards Executed Amendment to Indemnity Agreement E-25 & 14 ML19337F4991992-01-22022 January 1992 Forwards Rev to Physical Security Plan.Rev Withheld ML20091K9801992-01-22022 January 1992 Responds to NRC Re Violations Noted in Insp Rept of License R-95.Corrective Actions:Security Plan Rev Submitted for Review ML20086E4051991-11-18018 November 1991 Forwards Safety Analysis Rept for Low Enriched Fuel Conversion of Ri Nuclear Science Ctr Research Reactor ML20086D2051991-11-18018 November 1991 Forwards SAR for Low Enriched Fuel Conversion of Rhode Island Nuclear Science Ctr Research Reactor ML20067B2931991-01-23023 January 1991 Confirms 910116 Telcon Rept Re Complete Loss of Telephone Svcs,Including Both Voice & Burglar/Supervisory Alarm Sys. Caused by Telephone Lines Cut Through While Installing Phone Poles.Contact Verified Using two-way Radios ML20066C2801990-12-26026 December 1990 Advises That SAR Re Conversion of Reactor from High to Low Enriched U Fuel Will Be Submitted by 910401.Employee Retirement Incentive Programs Resulted in Retirement of Assistant Director for Reactor Operations ML20055H1281990-07-17017 July 1990 Submits Financial Info in Response to Decommissioning Rule (10CFR50.75) ML20012D5741990-03-22022 March 1990 Forwards Changes to Physical Security Plan.Encl Withheld ML20245J4271989-02-22022 February 1989 Requests Date for Submittal of SAR for Conversion of Reactor from Use of High Enriched U to Low Enriched U Fuel Extended from 890301 to 890901 ML20195H7901988-06-23023 June 1988 Requests That Date for Submission of Low Enriched U Conversion Application Be Extended to 890306.Extension Required to Do Remaining Work for Selection & Validation of Low Enriched Core for Facility ML20155B9011988-05-19019 May 1988 Responds to NRC Re Violations Noted in Insp Rept 50-193/88-01.Corrective Action:Full Compliance W/Tech Specs Achieved & Calculations Will Be Performed at Least Quarterly ML20151K5291988-04-12012 April 1988 Requests Concurrence in Subj Design Criteria So as Not to Interfere W/Operation of Reactor Facility Exhaust Stack ML20151U6351988-02-25025 February 1988 Provides Description of Servo Regulating Element Contained in Tech Specs,Per 880208 Telcon.During Review of Retyped Specs,Possible Discrepancy in Description Noted ML20237A3251987-12-0808 December 1987 Requests That Expected Date for Submitting Application to Convert from High to Low Enriched U Be Extended from 880104 to 880705,per 870323 Submittal of Proposed Schedule.Delay Due to Difficulties in Converting Re Use of Std Fuel Plate ML20236P9771987-11-0909 November 1987 Responds to NRC Re Amend 15 to License R-95.EPZ Will Not Be Modified During Const & After Completion of Ctr for Atmospheric Chemistry Studies Bldg.Provisions Made to Notify Workers During Const in Event of Emergency ML20236J3611987-08-0303 August 1987 Forwards Revised Emergency Plan for State of Ri Nuclear Science Ctr.Rev Corrects Spelling to Incorporate Name Change for Support Agency & Correct Refs ML20205C9111987-03-23023 March 1987 Submits Info to Meet Requirements of Highly Enriched U-low Enriched U (HEU-LEU) Conversion Rule.Schedule of Completion Dates Encl for After Conversion Approval 1998-10-14
[Table view] |
Text
TA,TE OF RHODE ISLAND AND PROVIDENCE PLANTATIONS RHODE ISLAND ATOMIC ENERGY COMMISSION j
Nudear Science Center 1
South Ferry Road j
Narragansett, R.I. 02882-1197 August 20, 1996 Docket No. 50-193 i
Mr. Marvin Mendonca, Senior Project Manager Non-Power Reactors,. Decommissioning and Environmental Project Directorate Division of Reactor Projects - III/IV/V U.
S. Nuclear Regulatory Commission (NRC)
Washington, DC 20555 s
Dear Mr. Mendonca:
This letter and enclosures constitute the second annual report that is required by revision one to the Technical Specifications. Enclosure 1 provides reactor operating statistics.. Enclosure 2 provides information on the 1 emergency shutdown. discusses maintenance operations. Enclosure 4 describes changes to the facility and enclosure 5 provides radiological controls information.
If there ' are any questions regarding this information, please call me at 401-789-9391.
1 Sincerely,
-Q ol Terry han Dir r
TT:cd Enclosures (5)
I Copy to:
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Dragoun, Region One i
9608260286 960820 PDR ADOCK 05000193 P
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Technical Specifications Section 6 8.4.a.
L i
i Reactor Energy Energy Critical Generated Generated Month (hours)
(MWh)
(mwd)
July-95 87.15 148.49-6.19 August-95 102.77 168.30 7.01 September-95 66.97-117.17 4.88 October-95 126.75 212.39 8.85 I
November-95 19.63 31.41 1.31 December-95 0.00 0.00 0.00 I
January-96 0.00 0.00 0.00
[
February-96 0.00 0.00 0.00 March-96 11.60 0.87 0.04 j
April-96 50.75 5.08 0.21 May-96 84.98 8.5d 0.35 June-96 63.38 6.34 0.26
[
l 1995-96 Totals:
613.98 698.55 29.11 Total Energy Output since Initial Criticality:
54,580.02 2,274.17 1
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INADVERTENT EMERGENCY SHUTDOWNS AND SCRAMS i
Date Run No.
Book / Pace Remarks Reason 8/31/95 6840 45/14 Dropped Blade 4 Drive misalignment l
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Section 6.8.4.c.
Maintenance Operations 1995-96 The reactor is normally operated daily (one shift) at its maximum licensed power level of 2MWt in support of the NAA i
and Neutron Scattering research conducted at the facility.
The reactor has been operating at a reduced power level of 100KWt while the reactor cooling systems are isolated and drained for an upgrade. Including the installation of two new primary pumps and the installation of an additional secondary cooling system.
Primarv/Secondarv Uoorade The new components will become a redundant system insuring forced convection cooling capability. System flow rates have been increased providing for better coolant safety margins.
j This. upgrade is in preparation for a fut.ure operating license change with a maximum power level limit of SMWe.
Emercency Core Coolina System The ECCS is 4.nstalled. It provides a redundant path to automatically maintain the pool water at near full level.
This system insures against a loss of coolant accident, i
Pool leak l
The reactor pool leak, being temperature dependent, has slowly decreased from 25 gallons per day to 8 gallons per day while the reactor has been operated at 100KWe for the past 8 months. The leak water is first noticed on the main reactor floor below the bottom of the thermal column housing, indicating the probable leak being a failure in the welded joint of the thermal column to pool liner. Inspections to pinpoint the location of the leak in the welded joint from the pool side is obstructed by the rabbit, beam port and i
thermal column protrusions into the pool. Fixing this leak is the top priority for funding requests under the Department of Energy Grant Program.
A grove was cut in the concrete floor at the thermal column to direct the water to a drain reducing the wetted floor area in front of the thermal column. The leak water then drains through a hole in the main floor to a 500 gallon tank located in the reactor basement area. From the tank the leak water is pumped through a 10 and 1 micron filter media to the suction of the reactor pool water demineralizer system and back to the pool.
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Radioactive liauid effluents l
i
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As part of a waste water management plan to reduce the amount of water being discharged from the facility, the pool leak 1
water is now filtered and pumped back into the primary water demineralizer system and returned to the pool.
j In addition, the pool water level was lowered approximately 2 inches (within Technical Specifications) to minimize the l
possibility of normal pool water temperature changes causing a pool water discharge to the retention tanks.
)
Both underground retention tanks, (15,000 gals and 1,000 gals), are no longer in service. Both tanks are over 30 years old and have become degraded. It was decided to abandon them in place. The tanks were emptied. The manifolds have been removed and the piping capped off. Personnel access points have been sealed and locked. All radioactive liquids now drain into plactic tanks (900 gallon capacity) installed inside the facility basement.
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The following are descriptions of 10 CFR 50.59 evaluations conducted during the period covered by-this report in accordance with Technical Specifications, section 6. 8. 4. d.
The evaluations did not find any new types of failures that would result in effects not previously considered in the FSAR:
- 1. 5-15-95, Primary and Secondary systems upgrade.
This upgrade is in anticipation of a licensed reactor power level increase to 5 megawatts.
The upgrade consists of replacement of the original primary pump (1500 gpm) with one having higher flow capacity (2000 gpm), and adding an additional primary / secondary system with - the same capacities to provide the necessary cooling for operation at 5 megawatts. In the interim this change provides a redundant system for reactor operation at 2 megawatts.
- 2. 1-30-96, Replacement of the containment system air compressor.
The original air compressor failed and resulted in an air system reziew. Air pressure is used to operate (open and close) ~ the containment isolation valves (reactor building air supply and exhaust). These valves are used in conjunction with a ventilation blower to provide a negative pressure in the reactor building.
The replacement air compressor has - twice the air tank capacity and a higher air flow providing for increased reliability. All the air lines were replaced using larger size piping which improved the operating characteristics of the isolation valves.
The new equipment does not create an unresolved safety question.
- 3. 3-14-96, Adding a window to the inside reactor room entry door.
l The security type glass window provides both security
{
and safety enhancements for personnel using the reactor room doorway by being able to view condtions on the-opposite side of the door prior to opening it. This change does not interfere with containment. A glass break would have a similar effect as a gasket failure an j
therefore does not create an unresolved safety question.
- 4. 5-15-96, Install a leak recovery system.
A small pump.and filter system has been installed to recover the pool leak water (approx. 10 gallons per day) 4 e
A (continued) and pump it back to the primary water demineralizer system. The recovery system consists of a metering pump and two filters ( 10 micron and 1 micron) and a float switch.
The leak water, which is of lower conductivity than tap
- water, is collected in a
500 gallon tank.
Upon activation by a high water level switch the tank water is pumped through the two filters and into the suction line of the demineralizer system pump and then to the demineralizer resin tank prior to being sent back to the pool. A check valve is installed in the line to the demineralizer system to prevent a line break from causing a pool leak which would drain the pool to the anti-siphen lines as described in the FSAR.
9 O
1 l
1 RINSC ANNUAL REPORT ll:)
JULY 1, 1995 - JUNE 30, 1996 TECHNICAL SPECIFICATIONS SECTION 6.8.4 l
4e.
Environmental surveys performed outside the facility.
A quarterly TLD badge is deployed outside the northeast wall of the reactor building where large radioactive equipment is stored.
The doses are given below.
This is an area which is not frequented by the general public. Using an occupancy factor of 1% (0.01) the annual dose will be belov 50 mrem.
i OUARTER DQg 08/01/95-09/30/95 200 mrem 10/01/95-12/31/95 200 mrem 01/01/96-03/31/96 330 mrem 04/01/96-06/30/96 Not Received Yet 4f.
Annual radiation exposures in excess of 500 mrem.
There were no exposures above this limit.
49 Radioactive Effluents C.f L ? ': ? 5 1.
Gaseous ef fluent -concentrations are documented on the Monthly Information Sheets (Form NSC-78 enclosed).
The gaseous effluents, mainly Argon-41, are about 3-4% of the maximum permissible concentrations.
2.
Liquid effluents concentrations, released to the sewer, are documented on the sewer disposal record (Form NSC-32).
The concentrations were well below the monthly sewer limits.
A summary sheet is attached.
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