ML18139A220
| ML18139A220 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/14/1980 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-1711, NUDOCS 8005140076 | |
| Download: ML18139A220 (22) | |
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NUCLEAR POWER STATION UNITS 1 and 2
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'0. The ACRS Subcorrmittee on Surry Nuclear Power Station, Units 1 and 2, met in Room 1046, 1717 H Street, N. W., Washington, DC on January 2j, 1980 to review the pro-posed results of the Surry Steam Generator Replacement Program. The notice of the meeting appeared in the Federal Register on December 23, 1979 (Attachment A).
A copy of the detailed Presentation Schedule is attached (Attachment B). A list of attendees at the Subcorrrnittee meeting is attached (Attachment C). A list of documents provided to the Subcorrrnittee for this meeting is provided (Attachment D).
There were no public statements either oral or written. The entire meeting was open to members of the.public. ACRS members present at the meeting were H.
Etherington, D. Moeller, P. SheWlllOn, and M. Bender.
1.0 SUBCOMMITTEE CHAIRMAN IS OPENING REMARKS (OPEN SESSION)
H. Etherington, Subco1TUT1ittee Chairman, introduced the members of the Subcorrrnittee and discussed the purpose of the meeting.
He pointed out that the meeting was being conducted in accordance witn the provisions of the Federal Advisory Corrrnittee Act and the Government in the Sunshine Act and that Mr. Gary Quittschreiber was the Designated Federal Employee for the meeting.
He noted that no written or oral statements from members of the public had been received concerning the meeting.
2.0 EXECUTIVE SESSION (OPEN SESSION)
A brief executive session was held.
Each of the Subcomnittee members pointed out specific itenis which.they planned to explore by questions to representatives of Virginia Electric Power Company (VEPCO) and the Nuclear Regulatory Corrmission (NRC)
Staff during the meeting.
3.0 INTRODUCTORY REMARKS
- 3.1 VEPCO - Status of Replacement Program J. Benton. VEPCO, noted that they hal essentially completed the SGRP as planned in Unit 2 which began on February 3, 1979. Personnel radiation exposure was within five percent of the estimate made prior to the start of Unit 2 SGRP.
Benton noted that the program took 37 weeks, instead of thf 26 which were anticipated.
The additional time was partly the result of taking their time once they realized the SGRP was.not the limiting activity. Benton indicated that eight to nine months was a reasonable time frame for the Unit 1 SGRP.
Surry 1&2 January 23, 1980 3.2 NRG Staff - General Evaluation of Program D. Neighbors, NRC Staff, noted that they issued a license amendment and environ-mental impact appraisal on January 19, 1979 to allow work on Unit 2 to begin.
Neighbors indicated that the NRC felt VEPCO did a very good job in planning the SGRP~
He said the SGRP procedures were well written by VEPCO in advance and that they did a good job in controlling and following the procedures throughout the program.
In response to questioning from D. Moeller concerning.lessons learned, R. Emch, NRC Staff, noted that there would be a follow-up study on the Surry SGRP similar to.the one BNL had performed prior t"o the peginning of work. The follow-up study will factor in the actual experiences for estim~ting man-rem exposure.
3.3 Videotape A 40 minute videotape of the Surry Unit 2 SGRP was shown to the Subcontnittee.
The videotape, as well as raw footage, has been made available to other utilities planning to replace steam generators. Members of the Subco11111ittee corrrnented on the usefulness of the videotape.
4.0 SIGNIFICANT UNANTICIPATED PROBLEMS WHICH OCCURRED J. Benton said they did not have any major significant problems during Unit 2 SGRP; however, he did mention numerous "unanticipated events and problems, 11 both technical and administrative, which they plan to remedy on the Unit 1 SGRP.
Attachments 1 through 5 list the problems encountered during the Unit 2 SGRP and how these problems will be solved on Unit 1.
5.0 REPORT ON ESTIMATED VERSUS ACTUAL MANREM EXPOSURE, SOLID WASTE GENERATION, GASEOUS WASTE GENERATION, ANO LIQUID WASTE GENERATION J. Benton discussed the estimated versus actual labor, exposure, and rad-waste value comparisons for the Unit. 2 SGRP.
The following summary provides a general indication of the comparison (See Attachments 6 and 7 for details):
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Sur(y 1&2 Labor Man-rem Exposure Liquid Effluent Volume Liquid Effluent Activity Noble Gas Effluents Gaseous Iodine Effluents Gaseous Particulate Effluents Solid Waste Volume Solid Waste Activity
- Resulted from defuel ing operations, ESTIMATED 233,588 manhours 2,066 man-rem 2.3x106 gallons 0.344 curies Ne.gl i gi bl e 4~53xlo-3 curies 3.12x10-3 curies 26,236 ft3 18.9 curies January 23, 1980 ACTUAL 871,643 manhours 2,140 man-rem 3.0xl06 gallons 0.497 curies 101.3 curies*
6.88xlo-6 curies l.32x10-3 curies 57,820 ft3 63.6 curies J. Benton noted that the actual labor expenditures reported exceed by a signifi-cant margin the estimates made during the project planning phase.
He indicated that this was largely duet~ the fact that peripheral and support activities associated with specific tasks were included in the assessment of actual expendi-tures. The estimates developed prior to commencement of work were intended for planning purposes and did not accurately anticipate the additional activities.
J. Benton summarized the ALAAA techniques used and the manrem exposure savings as a result of these techniques. Attachments 8 and 9 provide a table of the techniques, exposure incurred, and the exposure savings *. Attachment 10 provides a table summarizing the Unit 2 SGRP tasks which had ?ignificant personnel expo-sure in excess of the estimated values. Benton said there were other tasks on which they missed their estimates but they were only small exposures. Overall, they overestimated about as much as they underestimated so that the overall exposure estimates were close to the actual exposures.
6.0 CHANGES BEING MADE IN EQUIPMENT AND PROCEDURES TO PREVENT A REPEAT Ot DEGRA-DATION PROBLEMS WITH THE NEW STEAM GENERATORS J. Benton discussed the changes being made in the equipment and procedures to prevent a repeat of the problems they had with the original generators in Units 1 and 2 which required replacement. Benton discussed the numerous changes listed on Attachments 11 through 13 made by VEPCO to assure long term integrity of the new steam generators. Improvements have been made in the steam generators to prevent and inhibit corrosion, improve performance, and improve maintainability and reliability. Benton noted that the replacement generators were purchased
Surry 1&2 January 23, 1980 several years ago and the changes were the best technology at that time and they s~ill feel that the new design is adequate.
In response to questions from P. Shewrnon concerning training and management which got them into the problem to begin with, Benton indicated that the steam generators originally had phosphate control and carbon steel support plates.
The problems were not unique to Surry; although, they did have some condenser leakeage which aggravated the problem.
He felt the problems they have had wi.11 ensure in the future that chemistry control is a very important factor.
Benton noted that VEPCO is not a member of the EPRI Steam Generator Owners Group.
He said they did not feel that it was worth the money to Join this, partic~larly, since they are the first to do much of the work. It was noted that even though they are not formal members that they are still contributing their experience to the Group. J. Benton described the station chemist support, training, and I
responsibilities *. M. Bender suggested that VEPCO might use some outside consultants in this area to provide some outside expert opinion on possible impr*ovements.
7.0 CONCLUDING STATEMENTS D. Neighbors said the NRC has no further requirements with regard to the SGRP prior to Unit 1 startup.
H. Etherington informed the Applicant and the NRC Staff that a presentation to the ACRS on the Unit 2 SGRP would be scheduled for the February ACRS meeting.
It was suggested that the videotape be shown at the ACRS meeting if at all possible.
The meeting was adjourned at 11:00 am.
For additional details, a complete transcript of the meeting is available in the NRC Public Document Room, 1717 H St., NW, Washington, DC 20555, the Swem Library, College of William anq Mary, Williamsburg, VA 23185 and International Verbatim Reporters, Inc. 499 South Capitol Street, SW, Suite 107, Washington, DC 20002.
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Federal Register / V No. 250 / Friday, December 28. 1979 meeting on the Surry Station) until conclusion oCbusinesa. Thursday, January
- Z4, 8:30 a.m. until the concluaion of
- busine111.
The Subcommittee will review the status of unresolved generic safety items involving pressure vessels, steam generators, and other pressure boundary components in its cognizant aiea of review.
. Further Information regarding topics to be discussed. whether the meeting has been cancelled or rescheduled, the Chairman's ruling on requests for the opportunity to present oral statements and the time allotted therefor can be obtained by a prepaid telephone call to the cognizant Designated Federal Employee, Mr. Elpidio G. Igne
{telephone 202/634-3314) between 8:15 a.m. and 5:00 p.m., EST.
Dated: December m, 19711.
John C. Hayla, Advisory Cmrunittee Management Officer.
(FR Dae.~ Plied u-:7~ 8:411 am}
IIIU.Nl CODE~
Advisory Committee on Reactor V Safeguards Subcommittee on tt,e Surry Nuclear Station; Meeting The ACRS Subcommittee on the Surry Nuclear Station will hold a meeting on January 23. 1980 in Room 1046, 1717 H St., NW, Washington. DC 20555 to continue its review of the Surry Station steam generator replacement program.
Notice of this meeting was published December 20, 1979.
In accordance with the procedures outlined in the Federal Register on October 1.1979, (44*FR 56408), oral or written statements may be presented by members of the public, recordings will be permitted only during those portiom of the meeting when a transcript is being kept, and questions may be asked only by members of the Subcommittee, its consultants, and Staff. Persons desiring to* make oral statements should notify the Designated Federal Employee as far in advance as practicable so that appropriate arrangements can be made to allow the necessary time during the meeting for such statements.
The agenda for subject meeting shall be as follows:
Wednesday, January 23, 1980; 8:30 a.m.
Until the Conclusion of Business The Subcommittee may meet In Executive Session. with any of its consultants who may be present, to explore and exchange their preliminary opinions regarding matters which should be considered during the meeting.
At the conclusion of the Executive Session, the Subcommittee will hear presentations by and hold discussions
- with representatives of the NRC Staff.
the Virginia Power and Electric Company, and their consultants, and other interested persons.
In addition. it may be necessary for the Subcommittee to hold one or more closed sessions for the purpose of exploring matters involving proprietary information. I have determined. in accordance with Subsection 10( d] of the Federal Advisory Committee Act (Pub.
L 92-463], that, should such sessions be required. it is necessary to close these
- sessions to protect proprietary information. See 5 U.S.C. 552b(c)(4).
Further Information regarding topics to be discussed, whether the meeting has been cancelled or rescheduled, the Chairman's ruling on requests for the opportunity to present oral statements and the time allotted therefor can be obtained by a prepaid telephone call to the cognizant Designated Federal Employee, Mr. Gary Quittschreiber (telphone 202/634-3267) between 8:15 a.m. and 5:00 p.m., EST.
Background information concerning items to be discussed at this meeting can be found in documents on file and available for public inspection at the NRC Public Document Room. 1717 H Street, NW, Washington. DC 20555 and at the Swem Library, College of William and Mary, Williamsburg, VA 23185.
Dated: December 20, 1979.
John C. Hoyle, Adviaory Committee M'1l1agement Officer.
(FR Dae.~ FIied LW:7-:&; !t411 am)
A.IJNG CODl 7IIO-OMI Advisory Committee on Reactor Safeguards Subcommittee on Licensee Event Reports (LERs);
Meeting The ACRS Subcommittee on Licensee Event Reports (LERs) will hold an open meeting on January 23, 1980, in Room 1167; 1717 H St., NW.. Washington, DC 20555. Notice of this meeting was published December 20, 1979.
The agenda for subject meeting shall be as follows:
Wednesday, January 23, 1980; 11:30 a.m.
Until Conclusion of Business The Subcommittee will discuss the evaluation of I.ER information with representatives of NRC's newly formed Office of Analysis and Evaluation of Operational Data.
Further information regarding tppica
- to be discussed. whether the meeting has been cancelled or rescheduled. the Chairman's ruling on requests for the opportunity to present oral statements and the time allotted therefor can be obt
'a prepaid telephone call to the cognizant Designated Federal Employee, Dr. Andrew L Bates (telephone 202/634-3267) between ~5 a.m. and 5:00 p.m., EST.
Dated: December m, 1979.
John C. Hoyle.
Advisory Committee Management Officer.
(FR Dae:.,._
Flied 12-Z7-79: M5 u,J i,IUJMQ COD£ ?HCM1-II Advisory Committee on Reactor Safeguards Nuclear Regulatory Commission; Meeting In accordance with the purposes of Sections 29 and 182b, of the Atomic Energy Act (42 U.S.C. 2039, 2232b.), the Advisory Committee on Reactor Safeguards will hold a meeting on January 10-12, 1980, in Room 1046, 1717 H Street, NW., Washington, DC. Notice of this meeting was published in the
- Federal Register on December 20, 1979.
The agenda for the subject meeting will be as follows:
Thursday, January 10, 1980 8:30 A.M.-12:30 P.M.: Executive Session (Open}-The Committee will hear and discuss the report of the ACRS Chairman regarding miscellaneous matters relating to ACRS activities.
The Committee will discuss proposed.,
ACRS comments and recommendations to the U.S. Congress regarding the NRC Safety Research Program.
Portions of this session will be closed as necessary to discuss information the premature disclosure of which would frustrate the ACRS ability to perform its.
statutory function.
1:30 P,M.-6:30 PM.: Meeting with NRC Staff (Open}-The Committee will hear and discuss reports from representatives of the NRC Staff regarding proposed NRC action plans to implement recommendations of the President's Commission and other studies of the Three Mile Island. Unit 2 accident
- Portions of this session will be closed as necessary to discuss Proprietary Information applicable to these items.
5:30 P M.~:30 PM.: Executive Session (Open}-The Committee will discuss proposed methods to strengthen the role.
of the ACRS in accordance with the recommendations of the President's Commission on the accident at Three Mile ls]and.
Friday, January U, 1980 8:30 AM.-10:30 A.M.: Meeting with NRG Staff (Open}-The Committee will hear reports and will discuss proposed plans for NRC Implementation of the
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PRESENTAT10N SCHEDULE e
SURRY UNIT 2 STEAM GENERATOR REPLACEMENT PROGRAM JANUARY 23, 1979 1717 H Street, NW, Rm 1046 WASHINGTON, DC MEETING WITH VIRGINIA ELECTRIC POWER COMPANY AND NRC STAFF 1.0 *subcommittee Chairman's Opening Remarks 2-.0 Introductory Remarks 2.1 VEPCO - Status of Replacement Program 2.2 NRC Staff - General Evaluation of Program 3.0 Technical Presentations by VEPCO with NRC Staff 3.1
. 3. 2 Overview of Steam Gene1ator Rel\\lacement Program Operations (V;deow.r.e..J Significant Unanticipated Problems Which Occurred if Any.
PRESENTATION TIME 5 min 5 min
- 1. hour 10 min 3.3 Report on Estimated versus Actual Manrem 20 min Exposure, Solid Waste Generation, Gaseous Waste Generation, and Liquid Waste Generation 3.4 Changes Being Made in Equipment and Procedures 20 min to Prevent a Repeat of Degradation Problems with New Steam Generators 4.0 Caucus Conclusions/Remarks ADJOURNMENT Note:
(1) A maximum of 10 minutes will be allowed for receiving oral statements from members of the public if requested.
(2) The speakers should limit their prepared presentations to the time allowed.
An allowance, amounting to 50% of presentation time, has been made for questioning by the Subcommittee.
F
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APPROX TIME 8:30 am 8:35 am 8:45 am 8:55 am 10:00 am 10:15 am 10:45 am 11:15 am 11 :20 am
ACRS MEMBERS H. Etherington, Chairman D. Moeller-_
P. Shewmon M. Bender ACRS STAFF e
ATTENDEES LIST G. Quittschreiber, Designated Federal Employee ACRS CONSULTANT R: Dillon OTHERS NAME Richard Emch Robert LaGrange B. D. Li aw M. Grotenhuis C. Z. Serpan, Jr.
S. C. Goldberg A. Schwencer J. o.- Neighbors Richard Garnsey J. Peter Paine Stanley J. Green James Lang A. L. Parrish III Albert E. Curtiss III Ozen Batum Bill Miller Tom Stenzel Sheilah Kast Bill Bennett Paul Silliman Garry D *. Frieling John A. Mundis Walter H. Way Joseph M. Fackelmann A. L. Sudduth Gerald Slifer M. W. Gettler C. W. Rhodes
- P *. P. Nottingham R. M. Smith
- s. P. Sarver Edward J. Rivas R. A. Rosenberg AFFILIATION NRC/DOR/EB NRC/DOR/EB NRC/DOR EB NRC/DOR/ORB-1 NRC/RES NRC/ELD NRC/DOR/ORB-1 NRC/DOR/ORB-1 CERL-CEGB-England Electric Power Research Institute Electric Power Research Institute Electric Power Research Institute VEPCO - SGRP Project Mgr Rochester Gas & Electric (SGO Group)
Souther Electric Services, Inc.
Richmond Times Dispatch VEPCO Washington Star Con Edison Con Edison Wisconsin Electric Electric Power Research Institute Carolina Power & Light Co.
N. E.Utilities Duke Power, Charlotte, NC Public Service Electric & Gas Co VEPCO VEPCO VEPCO VEPCO VEPCO VEPCO Stone & Webster Alfctd~~
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e Page 2 Attendees List E. F. Harwell Martin Crutsinger Fred Millar C. GrochmaT James M. Burger L. Lewis George J. Schnable Joanne Dunn John Benton R. McKay TVA AP e
Potomac Alliance Stone & Webster Empire State Electric Energy Research Corp -
Duke Power Public Service Electric & Gas Co.
McGraw-Hill VEPCO VEPCO r.-1* --**-**. **-*-------.. ----- - ----* *---*-*-----.. - --- ------... --------*-
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e DOCUMENTS PROVIDED TO THE SUBCOMMITTEE FOR THIS MEETING
- 1.
View graphs shown at the meeting are provided as Attachments 1 -13. A complete set of all handouts are provided in the meeting transcript and in the ACRS office file for this meeting.
- 2. Progress Report No. 5 on the Surry Unit 1 and 2 Steam Generator Repair Program, forwarded by letter from C. M. Stallings to H. Denton, dated January 7, 1980.
ATTACHMENT D
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I PURPOSE:
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SUMMARY
OF UNANTICIPATED E'ltBTS STEAM GENERATOR REPLACEMENT PROGRAM SURRY POWER STATION - UNIT NO, 2 To SUMMARIZE UNANTICIPATED EVENTS AND PROBLEMS EXPERIENCED DURING THE LiNIT No. Z SGRP AND TO DISCUSS THEIR APPLICABILITY TO UNIT No, 1.
, No MAJOR OR SIGNIFICANT UNANTICIPATED EVENTS OR PROBLEMS OCCURRED DURING THE SGRP; HOWEVER, THERE WERE A NUMBER OF MINOR PROBLEMS AS SUMMARIZED BELOW,
, PROBLEMS CAN BE CATEGORIZED AS TECHNICAL OR.NON-TECHNICAL PROBLEMSa
- TECHNICAL PROBLEMS - PROBLEMS ASSOCIATED WITH HARDWARE, ENGINEERING PACKAGES, OR INSTALLATION PROCEDURES,
- NaN-TECHNICAL PROBLEMS - PROBLEMS ASSOCIATED WITH THE ADMIN-STRATION OF THE WORK OR THE LABOR FORCE, TECHNICAL PROBLEMS
- 1.
PROBLEM:
As-BUILT DIMENSIONS WERE NOT COMPLETE OR INACCURATE, INCLUDING PIPING ISOMETRICS, SOLUTION: PRIOR ro COMMENCING UNIT No. 1 OUTAGE, CRITICAL AS-BUILT DIMENSIONS WILL BE TAKEN AND PIPING ISOMETRICS FOR FIELD RUN PIPE WILL BE PREPARED,
- 2.. PROBLEM:
STEAM GENERATOR SUPPORT FEET HOLES WERE FOUND TO BE OUT OF SPECIFICATION DURING INSTALLATION OF CAP SCREWS JUST PRIOR TO STEAM GENERATOR INSTALLA-
- TION, THIS REQUIRED SOME REWORK OF SOME OF THE BOLT HOLES, SOLUTION: TEST FIT CAP SCREWS IN SUPPORT FEET HOLES PRIOR TO INSTALLATION, II]
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3, PROBLEM:
SOLUTION:
I INSPECTION.oF THE DOWEL ~s IN THE LOWER SUPPORT ASSEMBLY TOOK SIGNIFICANT EFFORT AND PROBLEMS WERE EXPERIENCED IN THEIR REMOVAL AS THEY ARE NOT DESIGNED FOR ROUTINE DISASSEMBLY, INSPECTION WAS REQUESTED BY THE NRC STAFF BECAUSE OF CONCERN WITH THE MATERIAL OF CONSTRUCTION, No SIGNIFICANT DEFECTS WERE IDENTIFIED IN THE PINS SAMPLEDi THEREFORE) THERE SHOULD BE NO NEED TO INSPECT PINS ON UNIT NO, 1,
- 4.
- PROBLEM:
DELAYS WERE INCURRED DURING THE INSTALLATION OF THE SIX(£) JIB CRANES ON*THE CRANE WALL BECAUSE OF PROBLEMS OF LOCATING REINFORCEMENT BAR IN
- CONCRETE, SOLUTION: EVALUATE REDUCING THE NUMBER OF JIB CRANES TO BE INSTALLEDj EVALUATE OTHER TECHNIQUES FOR LOCATING REBARj INSTALL JIB CRANES PRIOR TO LiNIT No, 1
- OUTAGE,
- 5.
PROBLEM:. TANKS USED FOR ELECTROPOLISHING WERE TOO SMALL, SOLUTION: PROVIDE LARGER TANKS,
- 6.
PROBLEM:
REPAIRS HAD TO BE MADE TO POLAR CRANE RAILS AND CONTACT SHOES PRIOR TO ITS USE TO LIFT STEAM GENERATORS I.
SOLUTION: THE UNIT No. 1 CRANE HAS BEEN INSPECTED FOR THESE.
TYPES OF PROBLEMS AND REPAIRS HAVE BEEN MADE WHERE NECESSARY.
- 7.
PROBLEM:
THE USE OF GLOVE BOXES WERE NOT ALWAYS AN EFFECTIVE EXPOSURE REDUCTION TECHNIQUEi HOWEVER) A LICENSE CONDITION REQUIRED THAT THEY BE USED,
- 8.
SOLUTION: DETERMINE THE NECESSITY FOR USING GLOVE BOXES ON A CASE-BY-CASE BASIS INSTEAD OF MAKING IT A LEGAL REQUIREMENT,* VEPCO HAS REQUESTED A CHANGE TO THE LICENSE AND THE NRC WILL-APPROVE THE CHANGE PRIOR TO THE UNIT No. 1 OUTAGE, PROBLEM:
SOLUTION:
MECHANICAL PROBLEMS WERE EXPERIENCED WITH THE CRANE (BIG RED) THAT WAS USED TO LIFT SG FROM PLATFORM TO TRANSPORT VEHICLE, INVESTIGATING THE USE OF ANOTHE~ TYPE C~ANE, ill s=--=** ----~---~*-::__~--~~-.. :... : -~-~:...,-~--~~-~.*=--=--=-=-~--=-~=~:.---=~==--==~--=----~~~~=-=~.:~~~-~---*:--*~---.
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- 9.
PROBLEM:
SOLUTION:
e
. e THE REUSE OF THE REACTOR COOLANT PIPING REQUIRED THAT A SIGNIFICANT AMOUNT Of lIME AND EFFORT BE EXPANDED FOR REFURBISHMENT AND HANDLING (DECON, WELD BUILD UP, WELD PREP, ETC,)
EVALUATE THE COST EFFECTIVENESS OF PURCHASING NEW REACTOR COOLANT PIPE, INCLUDING POTENTIAL PERSONNEL EXPOSURE BENEFITS,
- 10.
PROBLEM:
MACHINING OF THE REACTOR COOLANT PIPE STUBS REMAINING INSIDE CONTAINMENT CAUSES SOME DELAYS, SOLUTION: EVALUATION IS BEING PERFORMED TO DETERMINE WHAT IMPROVEMENTS MAYBE POSSIBLE, E.G. MECHANICALLY CUT PIPE JNSTEAD OF PLASMA ARC OR USE DIFFERENT TECH-NIQUE FOR MACHINING PREP,
- 11.
PROBLEM:
IN USING PLASMA ARC TO CUT REACTOR COOLANT PIPE, MOLTEN METAL COLLECTED IN CUT ON BOTTOM SIDE OF PIPE., MAKING IT DIFFICULT TO SEPARATE PIPE, SOLUTION: Cur WAS MADE IN LOWER HALF OF PIPE FIRST AND PACKED WITH "REFRACTORY" WHICH MOLTEN METAL DID NOT ADHERE TO I fil
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e NON-TECHNICAL PROBLEMS
- 1.
PROBLEM:
MANY WORK~RS WERE NOT-FAMILIAR WIT~ WORKING IN RADIOACTIVELY CONTAMINATED ENVIRONMENT.
SOLUTION: CONDUCTED RETRAINING PROGRAMS AFTER WORKERS HAD BEEN ON THE JOB FOR A SHORT TIME.
WORKERS WERE MORE RECEPTIVE AFTER THEY REALIZED TRAINING WAS FOR THEIR BENEFIT, USE PREVIOUS~Y TRAINED PERSONNEL FROM UNIT No. 2 ON UNIT No, l TO THE EXTENT POSSIBLE.
- 2.
PROBLEM:
HIGH TURNOVER OF CRAFT PERSONNEL.
SOLUTION: ENDEAVOR TO MINIMIZE TURNOVER.
- 3.
PROBLEM:
DURING EARLY PHASES OF THE OUTAGE, WORKERS WERE SOMETIMES IDLE IN THE CONTAINMENT.
- 4.
- 5.
SOLUTION:
REST AREAS WERE ESTABLISHED IN LOW RADIATION AREAS WITHIN THE CONTAINMENT AND WORKERS RETRAINED TO USE_AREAS.
IMPROVE WORK PLANNING TO ASSURE THAT ONLY WORKERS IN-CONTAINMENT ARE THOSE THAT HAVE NEED TO BE THERE.
BASED ON UNIT No, 2 EXPERIENCED, THE TOTAL NUMBER OF WORKERS CAN BE REDUCED, PROBLEM:
SOLUTION:
PROBLEM:
DURING INITIAL PHASES OF THE PROJECTJ DIFFICULTY WAS EXPERIENCED IN CORRELATING PERSONNEL RADIA-TION EXPOSURE TO A SPECiFIC WORK TASK, INITIALLY, THE PRIME CONTRACTOR FAILED TO PROVIDE THE INFORMATION REQUIRED, HOWEVER, A WORKABLE SYSTEM WAS ESTABLISHED AND IMPLEMENTED.
IHI S SYSTEM WILL BE USED ON UNIT NO. 1.
PROCESSING OF WORKERS INTO THE STATION WAS TIME CONSUMING BECAUSE OF SECURITY AND HEALTH PHYSICS REQUIREMENTS.
SOLUTION: SINCE THE SECURITY AND HEALTH PHYSICS ARE REGULATORY REQUIREMENTS, THEIR IMPACT MUST BE ACCEPTED.
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- 6.
PROBLEM:
IDENTIFICATION OF PEOPLE IN THE CONTAINMENT WAS DIFFICULT BECAUSE EVERYONE IS DRESSED IN THE SAME WHITE ANTI-CONTAMINATION CLOTHING.
SOLUTION: HEALTH PHYSICS TECHNICIANS ARE DRESSED IN BLUE ANTI-CONTAMINATION CLOTHING, ARM BANDS OR OTHER..
IDENTIFICATION WILL BE EVALUATED FOR USE IN IDENTI-FYING GROUPS OF PEOPLE OR CRAFTS,
- 7.
PROBLEM:
MARKING AND STORAGE OF MATERIALS TO BE REUSEDJ PRESENTED SOME DIFFICULTY BECAUSE OF THE INABILITY TO RETRIEVE THEM FOR REUSE, SOLUTION: ADDITIONAL EMPHASIS \\flll BE PLACED ON THE IDENTI-FICATION AND STORAGE PLAN.
- 8.
PROBLEM:
DURING THE EARLY PHASE OF THE PROJECT) DIFFICULTY WAS EXPERIENCED IN INSTALLING SHIELDING, SOLUTION: A "SHIELDING CONTRACTOR" REPLACED THE ORIGINAL CONTR~CTORt THE SHIELDING TECHNIQUE WAS ALSO CHANGED~
HIS SOLUTION WILL BE IMPLEMENTED ON UNIT No. 1.
- 9.
PROBLEM:
THE AMOUNT OF SOLID RADIOACTIVE WASTE SIGNIFICANTLY EXCEEDED THE ESTIMATE, SOLUTION: IMPLEMENT A MORE COMPREHENSIVE WASTE REDUCTION
- PROGRAM,
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Volume (Gallons)
Activity (Curies)
Isotope TABLE 2 e
e EFFLUENT RELEASE AND SOLID WASTE COMPARISON
SUMMARY
STEAM GENERATOR REPLACEMENT PROJECT SURRY POWER STATION - UNIT NO. 2 LIQUID EFFLUENTS Total Estimated Releases,
2.3 X 106 0.344 Total Actual Releases 3.0 X 106 0.497 GASEOUS EFFLUENTS Estimated Release/Unit Actual Release During During Steam Generator Unit No. 2 Steam Repair Effort Generat.or Repair Effort (Ci)
(Ci)
. Noble Gases Negligible 101.3 Iodines 4.53 X 10-3 6.88 X 10-6 Particulates 3.12 X 10-3 1.32 X 10-3 SOLID WASTE Estimated Total Vo!ume (ft3) 26,236 Activity (Ci) 18.9 Total 1977 Liquid Releases 1.4 X 108 67.67 Average Six Month 1977 Release/Unit (Ci) 7400 0.-24 1.4 X 10-4 Actual guantities 57,820 63.6 JD
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Isotope No£1~~~~~
Xe-133 Xe-135 T<;>tal Iodines I-131 Total Particulates Co-60 Co-58 Cs-137 Cs-134 Cr-51 Mn-54 Total e
TABLE 3 e
EFFLUENT RELEASE ISOTOPIC DISTRIBUTIONS STEAM GENERATOR REPLACEMENT PROJECT SURRY* POWER STATION - UUIT NO. 2 GASEOUS EFFLUENTS Total Activity Released (Ci) 99.4 1.9 101.3
-6 6.88 X 10 6.88 X 10-6 7.00 X 10-4 3.00 X 10-4 2.19 X 1()-4 4.94 X 10-5 4.51 X 10-S 8.37 X 10-6 1.32 X 10-3 Percent of Total Activity 98 2
100 100 100 53 23 17 3
3 1
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Reactor Coolant I l Pipe Decontamination Miscellaneous Valve Refurbishment TABLE 4
SUMMARY
OF SPECIFIC ALARA TECHNIQUES STEAM GENERATOR REPLACEMENT PROJECT SURRY POWER STATION - UNIT NO. 2 Exposure Achieved "Cost" Incurred Dose Reduction (Manrem)
Factor 142 5-7 Negligible.
10 41 1000 5
10 Page 1 of 2 Calcuated Exposure Savings (Manrem) 2,616.
576 45,000 306
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l I l : 8 Technique Initial Containment Cleanup and Periodic Debris Removal Plasma-Arc Cutting Equipment Containment "Rest Area" Utilization Full Scale Mock-Up Training Refurbishment Work Performed Outside Containment TABLE 4
SUMMARY
OF SPECIFIC ALARA TECHNIQUES -
STEAM GENERATOR REPLACEMENT PROJECT SURRY POWER STATION - UNIT NO. 2 Significant Radiological Effects Observed Page 2 of 2
- Reduced potential for generation of airborne contamination.
~
- Minimized requirements for use of respiratory protection devices.
- No instances of significant internal or external contamination observed.
- Reduced exposure times required for performing reactor coolant pipe cuts.
- Provided workers in containment with designated rest areas where minimum
~xposure levels existed; thus avoiding unnecessary dose during idle periods.
- Reduced exposure times associated with certain major tasks, by increasing worker familiarity and job efficiency.
- Reduced worker exposures by permitting refurbishment of piping, valves and other components in lower radiation areas.
e Techniques and Practices with Overall Significance to the ALARA Program
-Health Physics Program
-Remote Handling Capabilities
-Personnel Radiation Protection Training Program
-Photograph and Video-Tape ~ocumentation
-"York Package" Task Planning
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i IASK INSTALLATION OF REACTOR COOLANT PIPING TABLE *1B TASKS INVOLVING SIGNIFICANT PERSONNEL EXPOSURE IN EXCESS OF ESTIMATED VALUES.
EXCESS MANREM 261.501 I
MAJOR FACTORS RESULTING IN EXCESS EXPOSURE (A)
ASSUMED AVERAGE RADIATION LEVEL WAS UNDER-ESTIMATED FOR PORTIONS OF THIS TASK,
'(B). PROBLEMS ENCOUNTERED IN MACHINING AND WELD..
PREP OF PIPE STUBS WITHIN CONTAINMENT RESULTED IN ADDITIONAL LABOR AND EXPOSURE, INSTALhATION OF BLOWDOWN 66,122 AND NISCELLANEOUS PIPING (A)
RADIATION LEVELS HIGHER THAN ANTICIPATED, CUTTING OFPREACTOR.
COOLANT IPING REMOVAL OF MISCELLANEOUS PIPING DISASSEMBLY OF STEAM 6ENERATOR SUPPORTS 64.958 57~537 33.181 (B)
VALVE REFURBISHMENT AND WELD-PREP REQUIRED ADDITIONAL LABOR AND EXPOSURE TO ACHIEVE PROPER FIT-UP, (A)
UNANTICIPATED PROBLEMS WERE ENCOUNTERED DURING PIPE CUTTING OPERATIONS,
. (B)
HANDLING OF REMOVED PIPE SECTIONS.AFTER CUTTING (I,E, MOVEMENT OF PIPE TO DECON AREA AND PREPARATION FOR DECON) WAS NOT INCLUDE.
IN ORIGINAL ESTIMATE, ADDITIONAL LABOR AN EXPOSURE RESULTED, (A)
ADDITIONAL PIPING AND VALVE ASSEMBLIES WERE
- REMOVED, THIS INCREASED THE ORIGINAL SCOPE OF WORK TO BE PERFORMED, (A)
ADDITIONAL INSPECTION OF VASCOMAX DOWEL PINS WAS UNANTICIPATED AND RESULTED IN EXCESS LABOR AND EXPOSURE,.
. I CHANGES BEING MADE IN EQU ENI AND PROCEDURES TO PREVENT A REPEAT OF DEGRADATION PROBLEMS WITH NEW STEAM GENERATORS SURRY POWER STATION - UNIT NOS. 1 AND 2
, GOAL-. To ASSURE LONG TERM INTEGRITY OF NEW STEAM GENERATORS.
, IMPROVEMENTS HAVE BEEM MADE IN STEAM GENERATORS TO:
- PREVENT AND INHIBIT CORROSION IMPROVE PERFORMANCE IMPROVE MAINTAINABILITY AND RELIABILITY
, THE NEW STEAM GENERATORS HAVE THE FOLLOWING IMPROVEMENTS:
1, INCREASED RECIRCULATION RATIO 2,
NEW FLOW DISTRIBUTION BAFFLE 3,
IMPROVED BLOWDOWN SYSTEM 4,
FULL DEPTH EXPANSION OF TUBE IN THE TUBE SHEET 5,
THERMALLY TREATED INCONEL 600 TUBING TO INCREASE RESISTANCE TO CORROSION 6,
STRESS RELIEF OF FIRST EIGHT (8) ROWS OF TUBING 7°."
OFFSET FEEDWATER DISTRIBUTION 8,
TYPE 40S STAINLESS SUPPORT PLATES
- 9.
QuATREFOIL TUBE HOLE 10, RECESSED TUBE TO TUBESHEET WELD 11, MOISTURE SEPARATOR IMPROVEMENTS 12,. FLOW LIMITING DEVICE IN STEAM OUTLET NOZZLE 13, ADDITIONAL ACCESS PARTS 14, WET LAYUP SYSTEM 1Ii]
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e 15, PRIMARY SHELL DRAIN 16.*
- 17.
- 18.
- 19.
PRIMARY NOZZLE CLOSURE RINGS FEEDRING MODIFICATIONS - J - TUBES MARKING OF STEAM GENERATOR TUBES NEW REFLECTIVE TYPE INSULATION
- FULL FLOW DEMINERALIZERS HAVE BEEN INSTALLED TO REMOVE CONTAMINANTS FROM FEEDWATER THAT COULD CONCENTRATE IN SG.
- MIXED BED DEMINERALIZERS
- CHEMICAL REGENERATION SYSTEM
- ACID AND CAUSTIC STORAGE TANK
- AMMONIA-HYDRAZINE SYSTEM
- MoNITORING EQUIPMENT
- MAIN CONDENSER HAS BEEN REBUILT
- TITANIUM TUBING.
- ALUMINUM-BRONZE TUBE SHEET.
NEW SUPPORT PLATES
- NEW MONITORING EQUIPMENT
- MAKE-UP WATER TREATMENT SYSTEM MODIFICATIONS
- ADDITIONAL DEMINERALIZER
. ~ GENERAL REFURBISHMENT
- NEW CONTROL PANELS
- ADDED 3QQJ000 GALLON DISTILLED WATER STORAGE TANK
- RIVER WATER FILTRATION MAKEUP SYSTEM INSTALLED*
- NEUTRALIZATION SYSTEM AND SETTLING POND NEW MONITORING EQUIPMENT fl
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- STEAM GENERATOR BLOWDOWN PROCESSING SYSTEM
- COOLING SYSTEM INSTALLED TO RECOVER ENERGY
- DEMINERALIZERS USED TO REMOVE IMPURITIES
. - WATER RETURNED TO SECONDARY SYSTEM AND REUSED
- MONITORING INSTRUMENTATION OPERATING PROCEDURES
- PROCEDURES TO BE IMPLEMENTED TO CONTROL CHEMISTRY PARAMETERS
- ESTABLISH ACTION LIMITS FOR CONDENSER LEAKAGE AND OTHER PARAMETERS
- CORRECTIVE ACTIONJ INCREASE BLOWDOWN; REDUCE POWERJ SHUT DOWN UNIT
- CONCLUSIONS: - THE IMPROVEMENTS SUMMARIZED ABOVE SHOULD ASSURE THAT THE CONTINUED INTEGRITY OF THE STEAM GENERATORS AND PREVENT DEGRADATION OF THE TYPE THAT HAS BEEN EXPERI-
- ENCED, f--- -.. ----**.*--*-*-----***.