ML19343D185
| ML19343D185 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 03/12/1981 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-1820, NUDOCS 8104090844 | |
| Download: ML19343D185 (16) | |
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ISSUE DATE: 3/12/81 45//4/Fl MINUTES OF THE ACRS SUBCOMMITTEE MEETING ON FORT ST. VRAIN LONGMONT, COLORADO JANUARY 27, 1981 The ACRS Subcommittee on the Fort St. Vrain Nuclear Generating Station met in open session on January 27, 1981 in Loncm nt, Colorado, to review operating experience, the degree of success in eliminating the core power fluctuations, core performance (both fuel and structural), plan for testing and operations above 70% of rated power, and plans for future operations, modifications, and refueling.
A tour of the plant was also made by members of the Subcommittee.
Notice of this meeting was published in the Federal Register on January 15, 1981 (Attachment A).
A copy of the detailed schedule of presentation is attached (Attachment B). Written questions from a member of the public were received but his request to aks them orally was denied as being untimely. The Subcom-mittee suggested that the NRC Staff and the Licensee provide written answers to these questions.
No written reports were issued or approved by the Subcom-mittee at this meeting.
A list of attendees at the meeting is attached (Attachment C). A list of documents provided to the Subcommittee during this meeting is also attached (Attachment D).
EXECUTIVE SESSION ( Open to Public)
Dr. Siess, Subcommittee Chairman, opened the meeting at 8:30 a.m. with a statement regarding the conduct of the meeting in accordance with the pro-visions of the Federal Advisory Comittee Act and the Government in the Sunshine Act.
Mr. J. C. McKinley was the Designated Federal Employee for this meeting.
8104090$
. FORT ST. VRAIN.
MEETING WITH THE NRC STAFF AND PUBLIC SERVICE COMPANY OF COLORADO (PSC)
Mr. Miller (NRC) noted that the NRC expects to resolve by mid-February the two issues (moisture monitor response time and the time available to make the decision to depressurize in the event of a total loss of force circula-tion accident) preventing authorization for operation above 70% of rated power.
Mr. Warembourg (PSC) reviewed the operating history of the plant since July 1976. The plant capacity factors, based on the 70% limit of 200 MWe were:
1977 13.7%
1978 43.3%
1979 48.5%
1980 43.1%
He estimated that 70% of the plant downtime resulted from problems on the secondary side of the plant. He pointed out that Fort St. Vrain has more than four times as much instrumentation on the secondary side as a comparably sized fossil fueled plant. He discussed a number of plant operating problems and the actions taken to correct them. One significant problem on the primary side is a leak of clean interspace helium into the cold reheat steam line.
The specific location of the leak is not known but is suspected to be through a threaded connection in Loop 2.. This leakage is clearly evident in the con-denser off-gas system and the purified helium makeup. A Technical Specifica-l tion modification was requested and granted to relax allowable leak. rate from 400 to 700 pounds per day. Currently the rate is about 300 pounds per day.
It is planned to investigate this leak further during the September 1981 shutdown.
O
FORT ST. VRAIN
- Mr. Asmussen (General Atomic) described the core temperature fluctuation problem and its postulated causes and corrective action. The core regional restraint devices were Installed in late 1979 and tests were conducted in 1980. The cyclic nature of the fluctuations was eliminated but a redistri-bution phenomenon continues to be observed.
The redistribution appears to be predictable and well-behaved and should not precluce operation above 701, of rated power.
It is postulated that the redistribution results from pressure induced contraction (closing of spaces between fuel blocks) of the core.
Mr. Oscar Lee (PSC) described the recent order from the Colorado Public Utilities Com$1ssion which require,s PSC to deposit about $870,000 per month in an escrow account to be refunded to the ratepayers if Fort St. Vrain fails to achieve 50% capacity f actor based on a capacity of 200 MWe. This effec-tively removes Fort St. Vrain from the PSC rate base until such time as it can demonstrate a 50% capacity factor.
Mr. Warembourg (PSC) outlined PSC's plans for near term operation of Fort St Vrain. The intent is to complete the core temperature fluctuation tests above 70% of rated power before shutting down to refuel on Aprt13,1981.
It currently appears that service water limitations will prevent testing above 70% during the summer months and so the intent is to start these tests in March and complete them in April.
In September, another shutdown is planned to do the loop split and other plant modifications.
The test plan (yet to be submitted to the NRC) would be to establish a core pressure drop of about 3.2 psig and a power level of 70%.
Power would be
{
FORT ST. VRAIN,
increased about 3% at a rate of about 1/2% per minute; if no fluctuations were observed the power would be dropped back by 3% and then increased 3% at a rate of 3% per minute.
If stable operation is again achieved, the process would be repeated from this higher power level. When power levels of 80, 90, and 100%
are achieved, additional tests would be performed to check parameters other than core stability.
The load shedding test from 100% would be performed only after stability is assured.
The startup test data and fluctuation test data could be analyzed during the April 1981 refueling shutdown and then plans made for operation for core cycle 3.
Mr. Alberstein (General Atomic) reviewed the performance of the core. One of the fuel elements removed during the first refueling was destructively examined at General Atomic (GA).
The coated particles were found to be virtually undamaged at that level of burnup.
Based on the observations at the first refueling it was concluded that there was no structural damage of any kin'd to the core components.
Following the reload, the measured and calculated reactor physics parameters were in close agreement. The region power (peaking) factor is a function of coolant temperature rise and coolant flow rate. Flow rate is an inferred value based on flow control valve position.
Variations in the regional peaking f actor can come from three possible sources; the physics calculation, the measurement of temperature, or the inferred flow rate.
Bypass flow associated with the fluctuations and temperature redistribution also affects the regional peaking f actors.
It currently appears that the major contributor to the discrepancy between the calculated and measured regional peaking factor is the uncertainty in the cgolant flow value.
0 FORT ST. VRAIN.
The circulating activity in the primary coolant is well below the levels predicted by GA in calculations made four or five years ago.
Extrapolating current activity levels to full power produces an estimate of 600 curies in the primary circuit (less than half the predicted amount and less than 1/5 the design value). About ninety percent of this activity consists of Xenon and Krypton.
Mr. Lopez (GA) reviewed the graphite oxidation program being carried out at GA in Fort St. Vrain.
At the first refueling of Fort St. Vrain, some PGX graphite samples were placed in the core; at the next refueling some of those samples will be removed and exarined.
Currently, based on past plant operating experience, GA estimates that the core support blocks have about 30 more years of useful life, assuming plant operating conditions do not improve.
It is expected that improvements can be made in the amount of oxidants in the primary system.
GA is also engaged in an experimental program for the Department of Energy on graphite oxidation.
Mr. Mathie (PSC) summarized the report by GA on the examination of the gas circulator removed at the first refueling (GAC-15847). The circulator was l
decontaminated, examined, found to be in good condition, refurbished, and made available for further service. This circulator was recently used to replace a circulator that developed a leak in the bellows of its static seal.
l
FORT ST. VRAIN.
PSC has replaced individual circulators four or five times. The last replace-ment was done by PSC personnel and was done in about five weeks as compared with previous replacements using contractor personnel which required about eight weeks to accomplish.
Currently, GA is refurbishing the circulator that c
was recently removed.
Mr. Swart addressed the problem of moisture ingress into the primary system and the actions being taken to correct the problem. Moisture ingress comes primarily from the circulator bearing seal system. This is a complex auxil-iary system that can be upset in a number of ways. Control and calibration of this system is continually being improved. Testing that would upset the system has been modified.
Design changes are being completed and modifica-tions are to be made during the September 1981 shutdown. The Safety Analysis for these changes has not yet been submitted to the NRC but should be in the near future.
Mr. Holmes (PSC) reviewed the performance of the water-cooled liner of the prestressed concrete reactor vessel (PCRV). Thus far, no cooling channels have had to be plugged.
Early in plant operation, a number of locations in the PCRV were identified as possibly not being adequately cooled, subsequent actions corrected the problems and it now appears that 100% of rated power can be achieved without exceeding the liner cooling capabilities.
Some requalification of the control rod drive mechanisms may be required, but test results near 100% of rated power are needed before a qualfication temperature can be established.
1
FORT ST. VRAIN.
The Subcommittee and PSC discussed various other operational problems including snubber performance, instrument set point drift, and surveillance test induced transients.
No dramatic near term improvements are expected. Mr. Swart noted that nuclear power plants are designed to shut themselves down, not to keep themselves running.
Mr. Warembourg expressed PSC's concern over the potential economic and opera-tional impact of placing Fort St. Vrain under IAEA safeguards requirements.
The application of 10 CFR 25 and 10 CFR 95 to Fort St. Vrain will also have some significant impacts on economics and operations. These requirements also have some interesting impacts on e'mergency planning, including the handling of classified material at offsite emergency centers.
Another troublesome area is the application of the TMI requirements to Fort Fort St. Vrain is a relaIively small generating station of 330 MWe St. Vrain.
capacity.
It doesn't take too many additional requirements of $500,000 to
$2 million each to make the plant uneconomical to operate.
Amongst these requirements is one recuiring simulator training by October 1981.
This could have a $12 million impact on the plant since these are no HTGR simulators and one would have to be designed and built specifically for Fort St. Vrain.
There was general agreement that simulators aid in training but transients in HTGR4 happen so slowly that operators have time to think and act.
Another troublesome NRC requirement is that all Senior Operators have college degrees. Mr. Warembourg e. <pects this to result in a greater turnover of operating
FORT ST.-VRAIN.
personnel.
He would prefer to have the current experienced operators to some college degreed operator that studied LWR technology.
After a great deal of discussion with the NRC Staff, PSC was finally able to convince the Staff that, because of the long response time of an HTGR, the Shift Technical Adviser, did not have to be on site 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day but could be on call and available in 60 minutes.
It was pointed out that this was accomplished through the Standardization and Special Projects Branch of NRR which doesn't normally handle the TMI-related requirements.
Mr. Warembourg indicated that NRC Emergency Preparedness group is currently e
the most troublesome.
Although Fo'rt St. Vrain can show that, for what would be a Class 9 accident in a water reactor, the 30-day dose at the exclusion area boundary would be only 800 mrem, it is being required to have the same early-warning alert system as a water reactor.
Fort St. Vrain has been given*
some relief on the size of its emergency planning zone (EPZ) in that it has been reduced from 10 to 5 miles in radius.
Part of the problem is that no one in the NRC Emergency Preparedness group has HTGR expertise and the member-l ship on the group is constantly changing.
As a result of the TMI accident, PSC reviewed its emergency plan and found that it needed significant improvement, and PSC was well on its way when the NRC requirements came out. PSC has worked closely with the state in' the de-velopment of a coordinated emergency plan.
The Colorado state plan has been i
I submitted to FEMA but approval has not yet been received. The state plan was issued on January 27, 1981 for interim use pending approval.
l i
I.
FORT ST. VRAIN.
PSC submitted an emergency plan for Fort St. Vrain to the NRC in March 1980, comments were received in July 1980, and a revised plan submitted August 1980.
Although it is known that differences exist between PSC and the NRC, no official comments have been received on the revised plan. The deadline of January 2,1981 established in NUREG-0737 has passed and April 1,1981 is fast approaching for an approved plan.
Mr. Miller (NRR) has been unable to get comments out of the Emergency Preparedness group.
In good f aith, PSC proceeded to design and build a Technical Support Center based on guidance contained in NUREG-0578.
Draft NUREG-0696 set new criteria that the half-completed center cannot meet. Draft NUREG-0696 requires com-pliance with Regulatory Guide 1.97 which is not applicable to HTGRs.
NUREG-0610 sets radiological action levels based on water reactor technology.
At a meeting on December 10, 1980, PSC offered comments on the applicability of NUREG-0610 to Fort St. Vrain. The NRC responded with oral instructions to comply with NUREG-0610.
PSC has appealed directly to the Commission regarding the requirements for simulator training and the early warning system.
l NUREG-0654 also presents problems in that it requires PSC to have 26 people on site in 30 minutes to respond to an emergency while the Shift Technical I
Adviser doesn't have to be there in less than an hour.
l
^
FORT ST. VRAIN.
Mr. Warembourg noted that the cooperation with the state and local agencies in the development and testing of emergency plans has been excellent. With the termination of funding through FEMA, state and local authorities will be having problems paying for drills and exercises.
He also noted that cooperation with NRC/I&E has been good and that two I&E resident inspectors have been assigned to Fort St. Vrain.
PSC has some
- serious concerns regarding NRC inspectors' access to PSC personnel files and the potential violation of the Right to Privacy laws.
Mr. Warembourg went over the plans for the next refueling and core inspection.
Mr. Williams (NRR) outlined what he considered to be research needs to support Fort St. Vrain. Dr. Siess noted that, in preparation of its report on the NRC's research budget, the ACRS had been told that there was no need for research in FY 1982. Mr. Williams and Mr. Foulds disagreed with that position and Dr. Siess agreed to review the [ natter.
4 The Subcommittee took note of the questions submitted by a member of the l
public (John Loges) and suggested that the NRC Staff and the Licensee prepare a written response.
The Subcommittee also took note of the apparent lack of understanding by some It segments of the NRC Staff of the basic differences between HTGRs and LWRs.
was suggested that the ACRS might consider sending a letter to the Executive Director for Operations noting this apparent lack of understanding.
i l
11 -
FORT ST. VRAIN No further meetings are scheduled but the Subcommittee will continue to follow the developments at Fort St. Vrain.
The meeting was adjourned at 5:20 p.m.
Following the adjournment, the Subcom-mittee members toured the Fort St. Vrain plant.
NOTE:
For additional details, a complete transcript of the meeting is avail-able in the NRC Public Document Room, 1717 H St., NW, Washington, DC 20555 or from Alderson Reporters, 300 7th St., SW, Washington, DC, (202) 554-2345.
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Fehl Register / W1. 48. Ns. to / %ursd y, I:nuary 15, 1981 / N;tices 1
36&1 Datdi knu:ry 12.1981.
3mployee, Mr.1;hn C. McKinley ha a been canceUed or rescheduled. the with (telephone 202/634-3287) betw:en Ct15 Chaftman's ruling cn requists for the Cali!
John C Hryle.
a.m. and 5:00 p.m., EST.
opportunity ta present oral statements St ff Adrisory Committee Mancrement Wicer.
and the time allotted therefor can be intet Deted: January u, teet, obtained by a prepaid telephone call to F6 gra % ss.ias rs.4 t.sm e4s =1 5
$ bi aiwiso coes rie H us John C Hoyle, the cognizant Designated Federal Advisory Cocunitter Management Offo.
y g g,.g (,,g cer.
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202/634-3767) between 8:15 an and Cha Adv!:ory Committee on Reactor 520 p.m., EST.
opp-Saf;guertis, Subcommittee on Fort St.
I have determined. in accordance with and Vrdn; Meeting Subsection 10(d)of theFederal obts The ACRS Subcommittee on Fort St.
Advisory Committee on Reactor Advisory Committee Act, that it may be the Vrain will hold a meeting on January 27 Safeguards, Subcommittee on Safety o em na tlus 1981 at the Fort St. Vrain Visitors Philosophy Technology and Criteria; nyc[ssary o d
Center,16805 Road 19%, Platteville, CO Meeting is Exemption (9)(B) to the Sunshine Act, a.m (nnr Longmont, CO). The Subcommittee
,The ACRS Subcommittee on Safety 5 U.S.C. 552b(c)(9)(B).
p will review operatmg experience, degree Philosophy. Technology and Criteria Dated. january 12,12.
job of success in eliminating the core power will hold a meeting at ISO pm on
}oba C Hoyle.
Adi fluctuations, plans for testing and January 28,1981 at the Best Westem Advisory Committee Management Offscer pi optration above 70% of rated power, Airport Park Hotel,600 Avenue of 851 core performance (fuel and structural),
Champions,Inglewood. CA 90301.The A De-ia* N ***t **s =l salmo coes ww cnd plans for future operations, Subcommittee will discuss requirements
~~
modifications, refueling and shift for new (beyond Near-Tenn manmng requirements. Notice of this Construction Permit) reactor plants.
AMewy Comminw on Heectw mesting was published December 22 In accordance with the procedures Safeguards, Subcommittee on San outlined in the Federal Register on Onoke ma 2 and 3;MeeW W
1980.
In accordance with the procedures October 7,1980 (45 m 66535), oral or T=
outlined in the Federal Register on written statements may be presented by
%e ACRS Sobcommittee on San Oct:ber 7,1980, (45 FR 66535), oral or members of the public, recordings will Onofre Units 2 and 3 will hold a meeting v.
written statements may be presented by be permitted only during those portions on January 31,1981 at the Best Western members of the public, recordmss will of the meeting when a transcript is being Airport Park Hotel,600 Ave of be permitted only during those portions kept, and questions may be asked only Champions, Ingelwood, CA 90001.%e Em cf the meeting when a transcript is being by members of the Subcommittee. its Subcommittee will meet with kept, and questions may be asked only consultants, and staff. Persons desiring representatives of the Southern by members of the Subcommittee,its to make oral statements should notify California Edison Company and the consultants, and Staff. Persons desiring the Designated Federal Employee as far NRC Staff to review the seismology and tri 85 to make oral statements should notify in advance as practicable so that geology related items for San Onofre the Designated Federal Employee as far appropriate anangements can be made Units 2 and 3 for an Operating lleense.
in advance as practicable so that to allow the necessary time during the In accordance with the procedures appropriate arrangements can be made meeting for such statements.
outlined in the Federal Registee on to ellow the necessary time during the The entire meeting will be open to
. October 7,1980, (45 a of 635), oral or C
meeting for such statements.
public attendance except for Asoe written statements may be presented by F
1 ne entire meeting will be open to sessions during which the Suocommittee members of the public. recordings will
[
I public attendance.
finds it necessary to discuss be permitted only during those portions The agenda for subject meeting shall predecisionalinformation. One or more of the meeting when a transcript is being be as follows:
closed sessions may be necessary to kept, and questions may be asked only g
Tuesday, January 27,1981 discuss such information. (SUNSHINE by members of the Subcommittee,its 8:30 a.nt untilde conclusion of ACT EXEMPTION (9)(B)).To the extent consultants, and Staff. Persons desiring business practicable, these closed sessions will to make oral statements should notify Durmg the initial portion of the be held so as to mtntmire inconvenience the Designated Federal Employee as far meeting, the Subcommittee, along with to members of the public in attendance.
in advance as practicable so that cny of its consultants who may be ne agenda for subject meeting shall appropriate arrangements can be made present, will exchange preliminary be as followr.
to' allow the necessary time during abe views regsrding matters to be Wednesday, fonuary 2B,1981 meeting for such statements.
considered dunng the balance of the 2.00p.m. until de conclusion of business The entire meeting will be open to During the initial portion of the public attendance.
meeting.
%e Subcommittee will then hear meeting, the Subcommittee, along with
%e agenda for subject meeting shall presentations by and hold discussions any of its censultants who may be be as follows:
with representatives of the NRC Staff.
present, will exchange preliminary Saturday,Ja uary31,198J their consultants, and other interested views regardag matters to be a:30 a.m. until the conclusion of business persons regarding this review.
considered dunng the balance of the During the Initial portion of the meeting, the Subcommittee, along with l
Further information reFarding topics meeting.
i to be discussed, whether the meeting The Subcommittee will then hear any of its consultants who may be l
has been cancelled or rescheduled. the presentations by and hold discussions present, will exchange preliminary Chairman's ruling on requeste for the with representatives of the NRC Staff.
views regard 5g matters to be opportunity to present oral statements their consultants, and other interested considered during the balance of the i
end the time allotted therefor can be persons regarding this review.
meeting.
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obtained by a prepaid telephone call to Further information regarding topfes ne Subcommittee will then hear the cognizant Designated Federal to be discussed, whether the meeting presentions by and hold discussions ATTACHFENT A r
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ACRS FORT ST. VRAIN NUCLEAR GENERATING STATION SUBC0911TTEE MEETING JANUARY 27, 1981 TENTATIVE SCHEDULE APPR0XIMATE TIME 8:30 a Subcomittee Chairman's Opening Remarks 8:45 a NRC Staff presentation on status of review for pemitting operation in excess of 70% of rated power.
9:15 a Presentation by Pub'fic Service Company of Colorado 9:15 a - 10:00 a 1.
Review of operating experience and significant operational problems.
10:00 a - 11:45 a 2.
Analysis and control of core power fluctuations.
11:45 a - 12:00 n 3.
Plans for testing and operation above 70% of rated power.
12:00 n - 12:30 p LUNCH 12:30 p - 1:00 p a.
Core perfomance thus far (to include fission product release, circulating activity, graphite structural perfomance, primary circuit con-tamination,etc.).
~
1:00 p - 3:00 p 5.
Topics of specific interest:
a.
Decontamination, examination, and refurbishing of primary gas circulator removed at first refueling (15 mins.)
b.
Control of moisture ingress (10 mins.)
Separation of primary heliun loops (30 mins.)
c.
- d.
Improvenents in heliun purification capability (15 mins.)
PCRV liner perfomance (15 mins.)
l e.
f.
Chronic problems appearing in Liccasee Even*.
Reports (hydraulic snubbers, dirty electrical contacts, set points drift, etc.)
(15 mins.)
Itens of concern to Public Service Company (15 mins.)
9 i
- May be dropped if time gets short.
ATTACHMENT B
APPR0XIMATE TIME 3:00 p - 3:15 p 6.
Shift manning and operator training.
3:15 p - 3:30 p 7.
Applicability of TMI-2 experience to Fort St. Vrain.
3:30 p - 3:45 p 8.
Plans for future operations, refueling, and plant modifications.
3:45 p - 4:00 p 9.
Experience with various regulatory agencies (federal, state, and local) relating to plant operations.
4:00 p - 4:15 p
- 10.
Other items Public Service Company believes to be significant.
4:15 p Discussion with NRC/NRR research coordination staff regarding further research needs.
4:30 p Discussion with NRC/NRR staff regarding further regulatory requirements and actions.
5:00 p Subcommittee Chainnan's summary and adjournment.
NOTES:
1.
Box lunches will be available for purchase by the attendee! and will be eaten at an appropriate break in the vicinity of niion to 1:00 p.m.
2.
Following the meeting, a tour of the plant will be arranged for those ACRS members that are interested.
- May be dropped if time gets short.
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ATTACHMENT D DOCUMENTS PROVIDED TO THE SUBCOMMITTEE
- o Public Service Company of Colorado (PSC) viewgraphs on " Review of Operating Experience and Significant Pr'e-51 ems."
(~38 pages) 1.
General Atomic Company (GA) viewgraphs on " Fluctuations Review 2.
and Status."
(~55pages)
"Questiens Subcommitted by John Loges, Colorado Public Interest 3.
Research Group."
(one page)
PSC viewgraphs on " Plans for Testing Above 70%."
(~ 6 pages) 4.
GA viewgraphs on " Review of Core Performance."
(~14pages) 5.
GA viewgraphs on " Core Support Blocks -- i'-isture and 0xidation 6.
Effects."
(~7 pages)
PSC viewaraohs on "PCRV Linier." (~13 pages) 7.
Helium PSC viewgraphs on Helium Racovery System and Buffer 8.
System (s7 page:}
PSC viewgraphs on "Other Items of Concern to PSC."
(~3pages) 9.
(-14 pages)
PSC viewgraphs on " Applicability of TMI Criteria and Status."
10.
PSC viewgraphs on " Plans for Future Operation."
(~8 pages) 11.
(~5 pages)
PSC viewgraphs on " Experience with Various Regulatory Age 1cies."
12.
Nuclear Regulatory Commission (NRC) Staff viewgraphs on " Technical i
13.
Support for Fort St. Vrain."
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