ML20210D900
| ML20210D900 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 09/15/1986 |
| From: | Eddleman W, Julie Hughes, Katz S, Runckle J COALITION FOR ALTERNATIVES TO SHEARON HARRIS, CONSERVATION COUNCIL OF NORTH CAROLINA, EDDLEMAN, W. |
| To: | NRC ATOMIC SAFETY & LICENSING APPEAL PANEL (ASLAP) |
| Shared Package | |
| ML20210D908 | List: |
| References | |
| CON-#386-755 OL, NUDOCS 8609220038 | |
| Download: ML20210D900 (64) | |
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C0tnEILD UiNkC 116 SEP 18 #1:03 h0CNii$uY$NICf.
BRANC$i UNITED STATES OF AMERICA NUCLEAR REGULATORY C0W41SSION BEFORE THE ATOMIC SAFETY AND LICENSING APPEAL BOARD In the Matter of
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CAROLINA POWER AND LIGHT COMPANY AND NORTH CAROLINA Docket no. 50-400 OL EASTERN MUNICIPAL POWER AGENCY (Shearon Harris Nuclear Power Plant, Unit 1)
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MOTION TO REOPEN THE RECORD PURSUANT TO 10 CFR 2.734 BY C0ALITION FOR ALTERNATIVES TO SHEARON HARRIS, WELLS EDDLEMAN AND CONSERVATION COUNCIL OF NORTH CAROLINA September 15, 1986 JOSEPH T. HUGHES, JR., CASH STEVEN P. KATZ, CASH WELLS EDDLEMAN, PR0 SE JOHN D. RUNCKLE, C.C3.C.
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Motion to Reopen I,
Preservice Inspection Contention Now comes'the Coalition for Alternatives to Shearon Harris (CASH),
Wells Eddleman, pro jte, and the Conservation Council of Nortfi Carolina, moving the Commission to reopen the record in docket 50-400, Shearon Harris Nuclear Power Plant, pursuant to 10 CFR 2.734.
On the basis of the following argument the movants assert that the Commission is unable to determine that reasonable assurance that as built, the facility can and will be operated without endangering public health and i
safety as required by 10 CFR 50.57 (2)(3)(1).
l The Comission should answer two questions in determining whether such reasonable assurance exists:
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whether all ascertained construction errors have been cured; and, 2.
whether there is so pervasive a breakdown in Quality Assurance procedures as to raise legitimate doubts about overall safety )
i Union Electric Company (Calloway Plant Unit 1 of the facility.
ALAB-740,18 NRC 343,346 (1983).
The movants will demonstrate, (1) that there are compelling factual argu-ments'in support of this motion, (2) that there is uncertainty as to whether all ascertained construction errors have been cured,18 NRC 343, and that there has been a breakdown of the Inservice Inspection Process at SHNPP as to raise legitimate doubts about the overall safety of the plant; and finally, that the movants have satisfied the requirements of 10 CFR 2.734.
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Motion to Reopen I'I.
Inadequacy of Applicant's Preservice Inspection Program On January 1,1986. Ms. Parry Miriello, a former CF&L worker at Shearcq Harris and Brunswick nuclear reactors wrote to the presiding judge, James Kelley, Chairman of the ASLB panel in Docket 50400 OL alleging falsification of radiation exposure records and questionable practices relating to health physics and requested that her identity remain confidential.
See Appendix F.
The Chairman _, however, ruled, pursuant to 10 CFR 2.780 (b) that the allegations were to be treated as ex parte coe.'nications and disclosen the information to all parties in the case, including the Applicants. Although the KRC Office of Investigations (OI) has had documented evidence of Ms. Miriello's contentions since September 1985, the 0! has yet to do a personal interview with the alleger. Moreover, the NRC OI has yet to issue a report of its i
investigation, which goes to the heart of the questior, of the Applicant's competence and integrity in operating the proposed Shearon Harris plant.
As a worker exposed to radiation of the Applicant's nuclear reactors, the facts which have been brought forward by Ms. Miriello create serious
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close questions which would implicate the effectiveness of the Applicant's Preservice Inspection Program for its Harris reactor. Morecever, the asser-t tions which Ms. Miriello makes, if substantiated by the Office of Investigation i
report which has yet to be completed, would result in a finding by the Commission that the Applicant's request for an operating license "may be revoked suspended or n.odified, in whole or part, for any material false statement of fact required of the Applicant." (10 CFR 50.100)
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Miriello, a former employee of CP&L, alleged in September of 1985 that l
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<focuments were falsified by the applicant. The OI has yet to complete this t
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investigation. Among other allegations which have not been resolved, Miriello has, been unable to obtain her complete record from the Appl'icant and thus has been precluded from seeking, positions within that field. Aside fronathe m
interest in freedom to pursue gainful employment, the Applicant may be in i
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violation of 10 CFR 50.100 (material false statements of fact),10 CFR 0.735039(c) !
(disclosure of confidential informa) ion by the Applicant), and a substantial t
possibility that the Applicant may not Mave an adequate inservichinspection prograre. All these issues may in combination or in part, amount to a substantial fundamental flaw in the final decision of the Licensing Board's decision in that this evidence was never considered as a contention in 50-400 OL.
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The Inservice liispection Prograta at SHNPP is supposed to be a programmed se s system of planned, repetitive tests, inspections, and examinations carried out i\\
prior to in.itial operations and at regular intervals throughout the service life of the plant.
Preservice tests and examinations establish a baseline against which to compare the results of subpequent inspections. Pipe welds on safety-related' systems are examined by ultrasonic NDE testin'g to establish baseline data. According '.c the affidavit;of Thomas Brombach, CP&L Project Specialist /
Inservice Ins'+.tio, August 6,1986, "ISI during plant ?ife can help identify t
conditions in safety-related systems and components which could lead to failures..."
Although CP&L does not rely' on the preservice baseline inspections to
' assure the quality of constrdction, it is clear that this data is critical to monitoring the ongoing integrity of safety-related piping systems throughout the Harris Plant.
Correct initial baseline data is an essential element for giving reasonable assurance to the oublic that the Harris reactor can be operated 4
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and maintained in a safe manner with an effective program for monitoring the integrity of safety-related piping systems.
As an' eng'ineer with the Nuclear Energy Services (NES) Preservice Inspection Program, Ms. Miriello was responsible for reviewing data generated by the NES preservice inspection program "for completeness, legibility and accuracy of certain information," according to Thomas Brombach, who oversaw NES activities at the Harris Plant for CP&L.
As Ms. Miriello notes in her affidavit of July 28, 1986, which is appended to the motion to reopen, on a number of occasions she has made good faith efforts to bring improprieties to the attention of CP&L management. She notes her previous questioning of missed steam generator tubes during an eddy current inspection in November,1984; the cutting out and reworking of 10 to 20 welds, where no new inservice inspections were done on the new welds during July / August 1984; and the discrepencies noted in an inservice inspection report of a weld identified as 1-ISI-RC-23 during January,1985.
Ms. Miriello has provided the NRC with documentary evidence of improper inservice ultrasonic inspections of the large reactor coolant line welds as part of the Applicant's quality assurance program.
Attachments #1 and #2, which are both five pages long, show a discrepancy on the fourth page for the coolant line welds for numbers #9 and #12.
As Ms. Miriello notes in her letter to Judge Kelley of January 1,1986, ~
"two level III Nuclear Energy Services NDE inspectors argued over these ultra-sonic results. They had conflicting opinions." When the new page four was revised as shown in Attachment #2, " note that the mention of a weld or repair weld was eliminated from page 4 of the original Mel Perry (NES corporate inspector) turned in."
"Also removed was the listings of indications in this
weld, referring specifically to indications #9 and #12."
According to Ms. Miriello's investigations, these design flaws, depending
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on the size, in the Shearon Harris core coolant line may be violations of the ASME Boiler and Pressure Vessel Code,Section XI, Article IW'B3000, " Acceptance Standards for Flaw Indications" as quoted from the 1980 edition of the Shearon Harris Preservice Inspection Manual.
According to the information which Ms. Miriello has observed and obtained, approximately 10% of the welds in the inservice inspection program at the 4
Shearon Harris plant are defective and improperly documented based on the number of data sheets which were altered.
Moreover, one third or about 1000 of the inservice inspection records are questionable as to being actual inspections (records)ofweldspresentlyintheplant. These inservice inspection records were altered and ~ changed without following the proper NRC procedure for record revisions on pipe welds.
On July 15, 1986, US NRC Region II issued 2 violations to CP&L based on inspections of the Harris reactor during December 2-6, 1985. Since this informa-tion was not made public until the above date, it was not possible to enter it into the record in the ASLB proceedings on licensing the Harris plant.
The movants contend that the violations alleged in the July 15, 1986 inspec-4 tion report call into question the accuracy and reliability of the CP&L/NES Pre-service Inspection Program.
Moreoever, there is a sufficient nexus between the allegations of improprieties in the preservice inspections of safety-related pipe welds by Ms. Miriello, the confirmation of the improprieties by the violations in the July 15, 1986 inspection report and the requirement that reasonable assurance
.must be given that the reactor has been properly constructed and can be safely operated.
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- The gravity of the safety concerns which have been confirmed by Ms. Miriello's 1
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'whistleblowing activities and the most recent violations issued against CP&L j
point to the need for a more thorough examination of the Applicant's management capability in ' supervising the contractor who is responsible for operating its Preservice Inspection Program.
The movants contend that thdre is sufficient nexus between the information which may surface in the pending NRC Office of Investigations Reviews and Reports and the need for Applicant and the licensee to provide a reasonable assurance that the Harris reactor can be operated safely.
In analyzing the admissability of a contention based on the evidence which is appended to this motion of reopen, the movants must meet the stringent tests of 10 CFR 2.734, as well as the criteria for late-filed contentions as found in 10 CFR 2.714(a)(1-v).
The contention alleging a fatal f. law in the Preservice Inspection Program for the Applicant's Shearon Harris nuclear reactor is based on the admission of the following pieces of evidence:
' January 1,1986 letter to Judge Kelley from Patty Miriello, which has never been entered into the record nor been the basis of a preservice inspection contention;
' July 15,1986 notice of violation (Report No. 50-400/85-48)toCP&L from US NRC Region II alleging violations in the Harris plant Preservice Inspection Program;
' July 28, 1986 affidavit of Ms. Patty Miriello concerning the quality assurance program at CP&L's Harris reactor and allegations of safety violations in the Applicant's Preservice Inspection Program.
To reopen a closed record, the movants must meet the following criteria:
the motion must be timely; it must address a serious safety concern and demon-strate that a different result could be reached with evidence; and it must be accompanied with supporting documents or affidavits 1 In addition, with contentions which were not previously in controversy, the movant must satisfy the.requirments for nontimely contentions in 2.714(a)(1-v).
In analyzing a contention based on the inadequacy of the Applicant's
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i Preservice Inspection Program, the movants contend that the factors weighing
.in support of reopening the record greatly outweigh ~ the arguments against moving to reopen.
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Timeliness Timely is defined as whether the contention to be presented could have been raised at an earlier stage. As the Commission noted, 6 AEC 520,523 (1973)
"a matter nay be of such gravity that the motion to reopen should be granted notwithstanding that it might have been presented earlier," Vermont Yankee.
With the allegations of deficiencies in the Applicant's Preservice Inspection Program, good faith efforts have been made by Ms. Miriello and the joint intervenors to bring the deficiencies to the attention of NRC investigators /
enforcement personnel, as well as to the ASLB.
Unfortunately, both the Chair-4 man of the Harris ASLB (Docket 50-400) and the NRC OI have refused to take appropriate and responsive actions making it all but impossible for the inter-i i
I venors to develop evidence upon which to develop late-filed contentions. The July 15, 1986 violations present compelling evidence that there are factual grounds i-for closer scrutiny of this previously unexamined area in the hearing record.
As noted in 6 AEC 367, "the fact that NRC staff may have previously known of matters' being raised has no bearing on the validity of an intervenor's motion to reopen." In this cire impropieties by the ASLB in dismissing grave safety concerns as ej( parte communications and inaction by NRC investigatory staff should not be a legitimate excuse for preventing continued efforts to bring grave safety concerns in front of the full Commission, even at this
' late date.
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As was noted in 6 AEC 358,365 (1973), "if the problem raised presents a sufficiently grave threat to public safety, a board should reopen the record' j
to consider it even if it is not newly discovered and could have been raised in timely fashion." The movants contend that Ms. Miriello's letter on New-Year's Day 1986 is a perfect example of grave safety concerns which were not properly raised, but continue to present a compelling need to be aired, dealt with and corrected by the Applicants and the NRC.
2.
Significant Safety Issue The movants contend that the gravity of the allegations concerning i
fundamental defects in the conduct of preservice inspections on safety-related welds at the Harris plant weighs heavily in favor of erring on the side of safety, when the Comission is considering the importance of baseline data which will become the yardstick for continually measuring the margin of safety in critical reactor components, piping and cooling systems.
When there is clear evidence that testing was conducted using improper standards, that test data was improperly collected and recorded by inspectors and that the Applicant has no method for independently verifying the accuracy of preservice inspection test data, there is a grave safety question which must be scrutinized, investigated and answered before the Harris reactor is loaded with nuclear fuel.
3.
Materially Different Result The movants contend that if the ASLB were presented with the evidence l
which is supporting this motion to reopen, they would have reached a materially different result during licensing proceedings for the applicant's Harris reactor.
As.the. Board noted in its Callaway Plant decision 18 NRC 343,346 (1983).
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'"the defects must be of such a severity that they would prevent the finding of reasonable assurance that the plant can be operated safely without endanger-ing the public."
If the ASLB had inquired into the status of the Applicint's Preservice Inspection Program, they would have discovered the violations, deficiencies and fatal flaws in competence, management and reliability that are just now coming to light.
In order to give reasonable assurance to the public, the movants contend that there is a compelling need for the Commission to give close scrutiny to the evidence which has thus far been made public, as well as the evidence that will be available particularly,_undesignated documents under investigation pursuant to conversation with Nina Toms regarding CASH FOIA concerning documentation of welding and falsification.
The movants expect that based on the evidence there will be a need for the Applicant to redo certain preservice inspections which have been found to be defective and also without proper documentation to assure safe operation in the years to come.
As required by 10 CFR 2.734, where a motion to reopen relates to contentions not previously in controversy among the parties the movants must satisfy the requirements of 10 CFR 2.714 (a)(1)(1-v).
Good Cause for failure to file on time - This standard requires that the issues could not have been raised earlier.
The movants note that: where lateness is satisfactorily explained, a much smaller demonstration on the other four factors is necessary.
Florida Power and Light, 6 NRC 8, affirmed by Commission 6 NRC 939 (1979). The movants further note that, "the fact that the NRC Staff may have previously known of matters being raised have no bearing upon the validity of a.;... motion to reopen." 6 AEC 367.
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1 With respect to the timeliness issue we incorporate by reference the argument under 'l.
Timeliness', and assert the following argument.
Subsequent to the close of the record various reports concerning health and-safety have become available. The documents appended to this motion are timely filed because of the cumulative nature of the inferences which arise therein.
At a certain point in time, evidence of repeated violations of NRC regulations, gives rise to the necessity of reopening the record.
Here, Ms. Miriello's affidavits were available over a period of time.
(From late May 1986 through late August 1986). The Notice of Violation of July 15, 1986, became available in mid-August. There is also evidence, abet unavail--
able to the public, that the 10 is conducting investigations of CP&L.
On August 6,1986 the Division of Rules and Records (F0IA Office NRC) received a request filed under the Freedom of Information Act.
During a conversation with Nina Toms on September 9,1986, it was confirmed that a number of documents requested were the subject of investigation by the 01 (CASH had requested docu-mentation of issues raised by Ms. Miriello in affidavits in support of CASH's July 2,198610 CFR 2.206 Show Cause Petition.)
l The argument concerning inservice inspection could not have been raised earlier. CP&L's Notice of Violation was' unavailable to CASH until mid-August.
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The cumulative effect of Ms. Miriello's affidavits makes clear the timely nature of this motion.
(Particularly where Miriello's allegations are the substance of ongoing NRC investigations and are unavailable to the movants.)
The movants consider factors (ii) and (iv) together, as these factors are accorded relatively less weight than the other three factors in 10 CFR 2.714 (a)(1).
SEEt South Carolina Electric and Gas (Virgil C. Summer Nuclear Station Unit 1) l
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13 NRC 881,895 (1981).
Because the evidence contained in the Motion to Reopen S
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l has not been made part of the licensing hearing, has not been the subject of adjudication in an open and public hearing, and because this evidence squarely implicates the ' Applicant's inservice inspection there are no other means for the movants to seek relief other than to reopen the record. '
'The fourth factor, the extent to which the petitioners' interests will be represented by existing parties, would relate only to CASH, as Wells Eddleman, pro g, and Co'nservation Council are parties to the appellate proceeding on this docket.
CASH is seeking Comission review of its Petition to Intervene a'nd has participated in NRC proceedings by filing various pleading and motions.
The third factor, the extent to which movants can assist in developing a sound record, is accorded significant weight when balancing the factors. SEE:
Shorham, 18 NRC at 399,400.
The precise issues to be raised concern: the inadequa-cies of the Applicant's inservice inspection program, tests, and examinations of various safety related systems; documentation and record keeping discrepancies; the reliability of baseline inspections; and other issues. These areas of examination, and their adequate resolution are vital to assure the health and safety of citizens.
ihat the petitioners demonstrate "special expertise" is demonstrated by Eddleman's and Conservation Council's long fought intervention during the licensing hearing and appeals process.
CASH has demonstrated "special expertise" by filing various pleadings,show cause petitions and F0IA requests, and continued good faith effort to comply with NRC procedural requirements.
The fifth and final factor is the extent to which a movant's participation will broaden the issues or delay the proceedings. As the matters raised in this motion run to issues not contested in the licensing hearing but are directly related to health and safety systems and components of SHNPP.
this motion is
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DOLKETEE-uss!<c W SEP 18 All:03 CFFICE CF :Lw. an y
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BIAdck UNITED STATES OF AMERICA NUCLEAR REGULATORY C0!iMISSION BEFORE THE ATOMIC SAFETY AND LICENSING APPEAL BOARD In the Matter of
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CAROLINA POWER AND LIGHT
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COMPANY AND NORTH CAROLINA Docket No.
50-400 OL EASTERN MUNICIPAL POWER AGENCY
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(Shearon Harris Nuclear
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Power Plant, Unit 1)
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CERTIFICATE OF SERVICE This is to certify that on this date copies were mailed by deposit in the U.S. Mail, first class, postage prepaid, or hand-delivered to persons listed on the attached Service List.
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September 15, 1986
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l' UNITED STATES OF AMERICA
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NUCLEAR REGULATORY COMMISSION l-I In the Matter of
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CAROLINA POWER & LIGHT COMPANY
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and NORTH CAROLINA EASTERN
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Docket No. 50-400 OL 4
MUNICIPAL POWER AGENCY
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i f (Shearon Harris Nuclear Power
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Plant)
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,b Chairman Lando W.
Zech, Jr.
Dr. Reginald L. Gotchy 1:
U.S. Nuclear Regulatory Commission Atomic Safety and Licensing Washington, D.C.
20555 Appeal Board U.S. Nuclear Regulatory Commission l[P Washington, D.C.
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li, Commissioner Thomas M. Roberts 1 1 U.S. Nuclear Regulatory Commission Mr. Howard A. Wilber Atomic Safety and Licensing jr Washington, D.C.
20555 Appeal Board if*
U.S. Nuclear Regulatory Commission
!F Commissioner James K. Asselstine U.S. Nuclear Regulatory Commission Washington, D.C.
20555 i
Washington, D.C.
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James L. Kelley, Esquire ib Commissioner Frederick M. Bernthal Atomic Safety and Licensing Board
!k U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Washington, D.C.
20555 Mr. Glenn O.
Bright jh Thomas S. Moore, Esquire Atomic Safety and Licensing Board Chairman U.S. Nuclear Regulatory Commission et, Atomic Safety and Licensing Washington, D.C.
20555
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Appeal Board in U.S. Nuclear Regulatory Commission
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20555 Dr. James H. Carpenter Atomic Safety and Licensing Board l t.
U.S. Nuclear Regulatory Commission lp Washington, D.C.
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i Charles A. Barth, Esquire Dr. Richard D. Wilson 729 Hunter Street Janica E. Moor,e, Esquire Of fice of the General Counsel Apex, North Carolina 27502 U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Mr. Wells Bddleman 812 Yancey Street Docketing and Service Section Durham, North Carolina 27701 office of the Secretary U.S. Nuclear Regulatory Commission Richard E. Jones, Esquire Washington, D.C.
20555 Vice President and Senior Counsel Carolina Power & Light Company Mr. Daniel F. Road, President P.O. Box 1551 Raleigh, North Carolina 27602 CHANGE P.O. Box 2151 Raleigh, North Carolina 27602 Dr. Linda W. Little Governor's Waste Management Board
- Bradley W. Jones, Esquire 513 Albemarle Building U.S. Nuclear Regulatory Commission 325 North Salisbury Street Raleigh, North Carolina 27611 Region II 101 Marrietta Street l
Atlanta, Georgia 30303 H. A. Cole, Jr., Esquire 1
Special Deputy Attorney General 200 New Bern Avenue Mr. Robert P. Gruber Executive Director Raleigh, North Carolina 27601 Public Staff - NCUC P.O. Box 991 Joseph Flynn, Esquire Raleigh, North Carolina 27602 Federal Emergency Management Agenci 500 C Street, S.W.,
John D. Runkle,. Esquire Washington, D.C.
20740 Conservation Council of l
North Carolina Steven Rochlis, Esquire 307 Granville Road Regional Counsel Chapel Hill, North Carolina 27514 Federal Emergency Management Agenc'.
i 1371 Peachtree Street, N.E.
M. Travis Payne, Esquire Atlanta, Georgia 30309 Edelstein and Payne P.O. Box 12607 l
Raleigh, North Carolina 27605 Coalition for Alternatives to Shearon Harris (CASH) 604 W. Chapel Hill Street Durham, North Carolina 27701 t
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i RECENEC."". IIs5I~" ~
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UNITED STATES NUCLEAR REGULATORY COMMisslON REGION ll o
101 MARIETTA STREET.N.W.
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ATLANTA, GEORGI A 30323 s..../
.f ul151986 Carolina' Power and Light Company ATTN:
Mr. E. E.'Utley Senior Executive Vice President Power Supply and Engineering and Construction P. O. Box 1551 Raleigh, NC 27602 Gentlemen:
/
SUBJECT:
- REPORT NO. 50-400/85-48 t
On December 2-6, 1985, NRC inspected activities authorized by NRC Constructio i
Permit No. CPPR-158 for your Harris facility.
At the conclusion of the insp i
tion, the findings were discussed with those members of your staff identifie in l
the enclosed inspection report.
Areas examined during the inspection are identified in the report.
Withinkhese -
areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observations of activities in progress.
The inspectors also conducted independent measurements, utilizing Region II ultrasonic equipment at your site, to verify your capability for performing ultrasonic examinations and analyzing examination results.
The inspection findings indicate that certain activities violated NRC require-ments.
The violations, references to pertinent requirements, and elements to be included in your response are presented in the enclosed Notice of Violation, i
Your attention is invited to unres61ved items identified in the inspection report.
These matters will be pursued during future inspections.
l The responses directed by this letter and the enclosures are not subject to the clearance procedures of the Office of Management and Budget issued under the Paperwork Reduction Act of 1980, PL 96-511.
l Should you have any questions concerning this letter, please contact us.
Sincerely, i
l a
, Chief id M. V relli D
R actor Pro'jects Branch 2 Division of Reactor Projects
Enclosures:
(See page 2) 1 l
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Enclosures:
1.
Report No. 50-400/85-48 j
cc w/encls:
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R. A. Watson, Vice President Harris Nuclear Project De L. Tibbetts Director of Regulatory Compliance J. L. Willis, Plant General Manager O
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.P ENCLOSURE 1 NOTICE OF VIOLATION Carolina Pcwer and Light Cowany Docket No. 50-400 Harris License No. CPPR-158 The following violations were identified during an inspection conducted on December 2-6, 1985 and a subsequent in-office review on Decent.er 12, 1985.
The Saverity Levels were assigned in accordance with the NRC Enforcement o licy (10 CFR Part 2, Appendix C).
o 1.
10 CFR 50.55a paragraph (g) subparagraph (2) ellows the licenses to use the American Society of Mechanical Engineer (ASME) Code Section XI,1980 Edition with addenda throu.]h the winter 1981.
Carolina Power and Light Company's Inservice Inspection Program de' linea ted in Procedure Number ISI-201 Revision 1, the ASME Code, 1980 Edition, with addendas through winter 1931.
Contrary to the above, Nuclear Energy Service, Inc'. (NES) inservice Inspection Procedures the ASME Code,1980 Edition with addendas through winter 1982.157-5 This is a Severity Level V violation (Supplement II).
2.
10 CFR 50, Appendix B, Criterion V, requires that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type apprcpriate to the circumstances and shall be accom-plished in accordance with these in:tructions procedures or drawingt.
NES Preservice and Inservice Data Control Procedure IST-101 Rev.1, Par 3-
. graph 5.2,E. requires that corrections to data reports are to be completed by a single line drawn through the incorrect entry, initialled, and dated by the respcnsible individual when the correction is made.
Contrary to the above, on December 2-6, 1985, examination data sheets were i
observed where the hES Nondestructive Examination (NDE) Lead Examiner, ilad written " rewrite" on initial examination data sheets that had been signed by an NCE examiner and given a control number.
In some instances technical entries of eva~1uations were changed on the rewritten data sheets.
i This is a Severity Level y vioTation (Supplement II).
Pursuant to 10'CFR 2.201, y6u are required to submit to this office within 30 days of the date of this Notice, a Mritten statement or explanation in reply, including:
(1) admission or denial of the alleged violations; (2) the reasons i
_ for the violations if admitted; (3) the ccrrective steps which have Deen taken and the. results achieved; (4) corrective steps which will be taken to avoid f0rther violations; and (5) the date when fuli compliance will be achieved.
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Carolina Power and Light Company 2
Docket No. 50-400 Herris License No. GPPblS8
' Security or safeguards information should be submitted as an enclosure tp facilitate withholding it from public diselosure as required by 10 CFR 2.790(d).
or 10 CFR.73.21.
JUL 151985 g, e,.
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Report No.!
50-400/85-48 Licensee: Carolina Power and Light Company P. O. Bcx 1551 Raleigh, NC 27602 Dockat No.:
50-400 Licanse No.:
CPPR-158 Facility Name:
Harris 1 Inspection Conducted:
December 2-6, 1985 l
Inspectors: 7 iv
/- /J-86 R. W. Newsomt Date signed i
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Approved by:
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ElaRe, Section Chief Qate Signed Er ineering Branch C-vision of Reacter Safety
SUMMARY
Secpa:
This routine., unannounced inspection entailed 65 inspecter-hours at the site in the areas of oreservice inspection (PSI) cf safety-related piping welds including review ef proceduras, observation of work, data review and evaluation *,
and indepencent ultrasenic verification examinations; also, general observation cf construction activities, ccristruction prcgress and material storage.
Results:
Two violations were identified - Preservice examination procedures incorrectly reference subsequent code addendas - paragraph 5.a.(5):
Failure to follow procedure for correction of examination data, paragraph 6.a.(6).
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r-REPORT DETAILS W
1.
Persons Cgntagted Licensee Emoloyees
- J. Harness, Assistant Plant Manager
- N. J. Chiangi, Manager, Quality Assurance / Quality Control (QA/QC)
- C. R. Gibson, Assistant to Plant Manager
- R. B. Van Metre, Manager, Technical Support "C. L. McKenzie, Director, QA/QC, Operations
- C. R. Osman, Principal QA/QC Specialist
- T. W. Broebach, Project Engineer Inservice Inspection (ISI)
- P. W. Howard, Regulatory Compliance
- M. G. Wallace, pegulatory Compliance Other licensee employees contacted included construction craftsmen.
engineers, technicians, security force members, and office personnel, Other Organization
- R. Saunders, Level III Examiner, Nuclear Energy Service, Inc.
NRC Resident Inspector
- G. Maxwell, Senior Resident Inspector
- Attended exit interview
- Attended exit interview and contacted by telephone on December 12, 1985
- Contacted by telephone on December 12, 1985 2.
Exit Interview The inspection scope and findings were summarized on December 6, 198Ss with those persons indicated in paragraph 1 above; on December 12, 19S5, Region II held a conference telephone call with the persons ihdicated in paragraph 1.
The purpose of the call was to inform the licensee that After further review of the PSI data and procedural requirements, and in-office discussions between the inspectors and regi6nal management it was concluded that one item reported on December 6 as an unresolved item - (Prese-Vice examination procedures incorrectly reference subsequent code addendas) would be upgraded te a violation.
Two new additional items (one violation and one unresolved item) were also reported to the licensee.
The inspectors described the areas inspected and dis:ussed in detail the inspcetion findings.
No dissenting comments were received from the licensee.
The folloying new i.tems were identified during the inspection and subsequent in. office review.
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2 (0 pen) Violation 50-400/E$-48-01,PreserviceExaminationProcedures IncorrectlyReferengeSubsa'quentCodeAddendas-paragraph 6.s,(E),
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('Open) _ Viol-att an 50-400/85-48-03, Tailure to follow Procedure for Correction of Examination Data - paragraph 6.a.(6).
(0 pen) Unresolved Item 50-400/85-48-C2,PowerWireBrushingPriortoSurface Examination.s - paragraph 6.a.(~ ).
3 (0p*4n). tinresolved Item 50-400/85.-48-04, Independent Technical Review of Examinatien Data - paragrc.sh 6.a.(7).
The licenste dia not identify as proprietary any of the material provided to or rev'iewed by t,he inspectors Gur$69 this insphetton, 3.
Licensee Action on Orev1ous Enfor:pment Mattera This subj'ect wa.s not addressed in tht inspection.
4.
Unrtscived Iter.s l'eresolved Items are matters abobt which more information is required to determine whether. they are accsouble or may involve a violation or deviation.
Two new ufwesolved items identified during this inspection are s
discuissed in caragraphs 6.a.(3) and G.a,(7).
5.
Independent Inspectioh Effort (g2706)
The insoectors conducted a general inspection of tne containment, auxiliary building, and material storage aren t'; observe constrbet1on progress and construction activi't.iu such as welding, material handli69, nousekeeping on'd
- storage, The inspestors did not obsene any cuestionabic workmanship.
The inspectors (ho observ6d that material protection. hancling, and storage appeafed adequate.
Within the areas examined, no violations or e viaticas wers identified.
6.
PreserviceInspection(PSI)
The inspectors examined documents, activities, and records, as indicated below, to datermin'e Whether PSI was being conducted in accordarce with applicable procedures, regulatory requirements; and lii:ensee comitments.
The applicable code, for PSI is the Amerit:1.9 $ociety of Mechanicel Engineers.
Boiler and Pressure Vepsel (ASME S&PV) CSde, Section %I,1980 edition with Nuci ar Energv Services (NES) has respectibi-addenda through winter 1981.
t lity as the PSI contracter.
liowever, nondestructive eddy current ext:ninations had been ccncucted by Canam Ins;',ection and Technical Se vices Laboratory (TSt,.).
NES Leve! III examiners are performing the altrasonic examination evaluatiens.
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3 a.
Review of Procedures (730525)
(1) The following,precedures were reviewed in the areas of procedure
-apareval and qualification of NDE personnel:
_ Procedure No.
Title
- 157-501 (R1) Chg, 1/1 Procedure for Ultrasonic Examination of Piping Systems (NES) 80AS051 (RO)
Ultrasonic Examination Procedure for Reactor Vessel Welds From the OD surface 80A5036 (RO)
Procedure for the Operation of the RFV ID Examination Positioning Device for the Inside Surface Ultrasonic Examination of the Reactor Pressure Vessel for Shearon Harris Nuclear Power Diant Unit 1 80A5037 (21)
Automated UT Examination Precedure for Reactor Vessel Shell Welds l
(Plus'Fleid Changes FC-1 through FC-7) 80A5040 (R1)
Automated Ultrasonic Examination Procedure for Reactor Vessel Nozzle to Shell Welds 80A5030 (RO)
Manual Ultrasonic Examination Procedure for Vessel Nozzle Safe End Welds (Plus Field Change FC-1)
IST-401 (R1) Chg. 1/1 Liquid Penetrant Examination (Color l
Contrast, Solvent Removable) NES IST-604 (RO)
Multifrequency Eddy Current Procedure for Westinghouse 04 Steam Generater Tubing Using The MIZ-18 Digital Eddy Current System (Canam Inspecticn)
IST-101 (R1)'
Preservice and Inservice Data Control Procedure (NES) t 6
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4 (2) The inspectors also reviewed the above listed ultrasonic examina-tion procedures to ascertain whether they had been reviewed and approved in accordance with the licensee's established QA procedures.
The above procedures were reviewed for technical adequacy and conformance with ASME,Section V Article 5 and other i
license commitments / requirements-in the below* listed areas:
type of apparatus used, extent of coverage of weldment, calibration requirements, search units, beam angles, DAC curves, reference level for monitoring discontinuities, method of demonstration of penetration, limits for evaluating and recording indirations, recording significant indications, and acceptance limits.
(3) The inspectors also reviewed the liquid ' penetrant procedure, IST-401, to ascertain whether it had been reviewed and approved in t
accordance with the licensee's established QA procedures.
The above procedure was reviewad for technical adequacy and conformance with ASME,Section V, Article 6, and other licensee commitments / requirements in the following listed areas:
specified~
me thod, penetrant materials identified, penetrant materials analyzed for sulfur, penetrant materials analyzed for total halogens, acceptable pre-examination surface, drying time, method of penetrant application, surface temperature, solvent removal, dry surface prior to developing, time and method for applying developer, examination technique.- and evaluation technique.
While reviewing the liquid penetrant examination procedure, the inspectors noted that power wire brushing of surfaces prior to liquid penetrant examination was allowed by the procedure.
This practice may close surface openings and be detrimental to the penetrant examinations.
This concern was discussed with the..
licensee who has agreed to address the power wire brushing issue and make appropriate changes to resolve the issue.
Pending NRC review of the actions taken regarding this concern the matter will be ident"4ed as Unresolved Item 50 400/85-48-02, Power Wire Brushing Prior to Surface Examinations.
(4) The inspectors reviewed Eddy Current Procedure, IST-604, for technical content relative to: multichannel examination unit, multichannel examination equipment is specified, examination sensitivity, material permeability, method of examination, method of calibration and calibration sequence, acceptance criteria, qualification of NDE personnel, and procedure approval.
(5) During the review of procedures IST-501 (R1), Ultrasonic Examina-l tion and IST-401 (R1), Liquid Penetrant Examination, the inspectors noted that these procedures were written to satisfy the requirements of ASME Section XI 1980 edition with addenda through winter 1982.
Since the " Code of Record" committed to by the licensee is the ASME Section XI 1980 edition n Ith adder.da through
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l winter'1981, as stated in their Preservice Inspection Program (RI) submitted to the Office of Nuclear Reactor Regulation (NRR), the inspectors discussed this discrepancy with the licensee.
The licensee indicated that he had discussed this point with NRR but was unable to produce documentation supporting this discussion and there did not appear to be a formal request to NRR which would allow the licensee to use the winter 1982 addenda.
The licensee is in violation of Title 10 code of Federal Regulations Part 50.55a paragraph (9) subparagraph (2) which requires the licensee to use ASME Section XI 1980 Edition with addenda through winter 1981 if authorization from the Director of the Office of Nuclear Reactor Regulation has not been obtained. This item is. identified as Violation 50-400/85-48-01, Preservice Examination Procedures Incorrectly Reference Subsequent Code Addendas.
(6) On December 4, 1985, the NRC inspectors conducted verification examinations on a selected sample of welds that included examples of welds where technical changes to the examination data had been
- made as a result of data rewrites.
The NES NDE lead examiner was P' invited to accompany the inspectors during these verification examinations and it quickly became apparent that the NDE lead examiner was very familiar with the examination of the specific welds involved although in some cases there was no documented evidence that he had ever examined the weld.
The lead examiner knew specific locations of welds even when they were not visually m
discernible due to surface contouring for PSI and in one case because of cladding on the pipe base material.
He was also able to tell the inspectors how to manipulate their transducer to see specific indications and how and where to dampen specific signals when it appeared that the signal could not be dampened.
The NRC, inspectors verification examinations were performed using
( Region II's ultrasonic equipment and the examinations compared i
favorably with the final examination data and evaluations made by NES (see paragraph 6.b.2 of this report for sample selection and conclusions by the inspectors).
On December 5,1985 the NES NDE lead examiner was requested to j
perform a liquid penetrant examination on a weld where the initial examination data indicated that the rewrite had altered the reported results.
The re-examination confirmed the results reported in the final report with some small, differences noted in the reported indication size.
The inspectors did nc+. detect any problems with the final examination data wheri compared to the t
components involved.
3 1
l During the inspectors in-office review on December 12, 1985, of the Preservice and Inservice Data Control Procedure, IST-101 i
Rev. I and NES inspection data reports obtained by Region II, l
changes were observed to technical entries on data sheets prior to i
the completion of the NES review process that were not in 1
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accordance with paragraph 5.2.E. of the data control procedure.
Paragraph 5.2.E requires that corrections to data reports are to be completed by a single line drawn through the incorrect entry, f
initialled and dated by the responsible individual when the correction is made.
Examination data sheets were observed in some instances where the NDE lead examiner had written' " rewrite" on the initial examination data sheet that had been signed by the examiner and given a control number.
In most cases a new data sheet would be submitted on the same day as the initial data sheet, however in some instances technical entries or evaluations would change with no explanation or evidence of additional i
investigation.
The method used to correct examination data sheets was not in accordance with paragraph 5.2.E. of the data control procedure IST-101, and is in violation of 10 CFR-50 Criterion V.
This item was reported as Violation 50-400/85-48-03, Failure to Follow Procedure for Correction of Examination Data.
(7)
In addition to the item reported above, the inspectors review of
- NES Procedure IST-101, R1 revealed that the diagram 'or data
% flow, illustrated in Atta; 3 ment 1 of the procedure, delineated the -
NES NDE lead examiner to review the examination data for technical and administrative accuracy and then in a subsequent step allowed w
the same individual to sign-off the data as the technical reviewer.
This method of controlling data is inappropriate when I
it results in the individual signing off data that he previously had input to.
The licensee was notified of this conflict in data i
review / flow on December 12, 1985, when the item was reported to
% the licensee as Unresolved Item 50-400/85-48-04, Independent Technical Review of Examination Data.
b.
Observation of Work and Wo'rk Activities (730538)
The inspectors observed a limited amount of work activities due to the limited number of examinations being performed and the time required for independent ultrasonic verification examinations utilizing Region II equipment and personnel.
The inspectors reviewed certifica-tion records of equipment, materials, and NDE personnel which had been and will be utilized during the required PSI examinations.
The reviews conducted by the inspectors are documented below.
(1)
Examiner Qualification The inspectors reviewed the qualification documentation for the below listed NES, CONAM and TSL examiners in the following areas:
employer's name, person certified, activity qualified to perform, effective period of certification, signature of employer's designated representatives, basis used for certification, and annual visual acuity, color vision examination and periodic recertification.
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UI PT MT RT EC II A JEC II Itd GRT III REM Method - Level Examiner (NES)
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GG II II II JTH II II II SM II II MS RTS III III III Method - Level Examiner (TSL)
UT PT MT RT EC III RMS II SDG I
CMC (2) The inspectors cond'ucted verification ultrasonic examinations '
using Region II's equipment on portions of the below listed welds.
The examinations were performed in order to evaluate the technical adequacy of the ultrasonic examination procedures being used to perform preservice ultrasonic examinations and to assess the validity of the information being reported by the ultrasonic i
examiners.
The ultrasonic examination procedure used to perform
. the verification examinations was IST-501 (RI) Chg. 1/1.
Size 1-SW-FT-601 1-ISI-51-29 3"
S1-13-1-SW-4 1-ISI-CS-7 4"
1-CT-SW-E4 1-ISI-CT-1 8"
1-RC-SW-A3 1-ISI-RC-23 6"
RC-2-FW-7 1-ISI-FW-MS-RC-2 31" 1-AF-SW-84 1-ISI-AF-7 4"
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The v.erification u'ltrasonic examinations conducted by the inspectors indicated that the procedures being used to conduct the preservice examinations are adequate and that the information being reported by the ultrasonic examiners compares favorably with the verification examinations.
The verification examinations also indicated that a conservative examination was being performed.
The only problem encountered by the inspectors was in defining the boundary of the weld metal in pipe joints due to the quality of surface grinding and in one specific instance, due to clad welding on the pipe base metal.
The inspectors were able to over come this problem by using an additional instrument and a compressional wave transducer to continuously monitor the inside diameter (ID) surface configuration.
These problems caused many of the data corrections made by the NDE lead examiner and could be identified in many cases as ultrasonic beam redirection to the ID.
(3) The following listed ultrasonic equipment and materials certifi- -
cation records were reviewed:
Ultrasonic Instruments
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Manufacturer / Model Serial No.
Sonic MKI 781306 KK USL-48 212200 AI S-80 10244-9 Minature Angle Beam Calibration Blocks Serial No. 783913
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Serial No. 785363 Ultrasonic Couplant Batch Numbers Ultragel II 8336 & 8443
, Ultrasonic Transducers Size Frequency Serial No.
.5" 2.25MHz E20000 1.0" 1.0MHz J22462 1.0" 1.0MHz J22463 1"x1" 1.0MHz F30199
.5" 2.25MHz L-19108
.5"x1.0" 2.25MHz B 3388
.312"x.625" 2.25MHz A 3342
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(4) Magnetic particle yoke serial number 6853 was_ used for the perfirmance of PSI examinationu ' The inspectors reviewed tne lif t i
test qualification documentation to verify contrciling document
- '.. requirements were met.
s li (5) The inspectors observed the liquid penetrin't examination of weld 1-RH-SW-D19B on 150 1-IS1'-RH-2.
The cbservation was compared with the applicable procedure [and tw Code in the following' areas:
apecified. method, penetrant material's identified; pf.netrant
- materials analyzed forc.elogens and ful fur; acceptable pre-r examinat(on surface; drying r.ime; method of peretrant application; penetration ytime; surface temperature; solyt.nt removal; dry i
surface pHor' to developing; type of developer; ' examination technique; evaluation technique; and reporting of examination results.
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The above examination resulted in the enh'theem'ent of two linear
' indications,oneindicatjorlwasabovetheotherandbothmeasuring.
3/32" in length.
Both s
of the ASME Code and cc,ind; cations weregacceptable to Section XI mpared favenbly' to the licensehls final liquid penetrant examina*; ion data sheet.
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(6)
The inspector reviewed the bitowC11sted penetrant material certification re' cords to ascertaf niff the sdfur and ha7 ogen content of the materir? was withir.* acceptable content ifmits. -
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828058, 83K052, 83M015 C'eaner/ Remover
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82X080, 84J040, 84M021 d
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, Developer 82J062, 84J002, 83LO94 p
(7)
The ini;pectors reviewed the qualiffcation documiotation for the
,below 1isted TSL & CONA6 addy current equipment t_o ve ri fy contro,lfed documents were ret'.
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1 TSL M12-13't.
Scrial Numbers 052 a 075 j
COVAM MIZ-16' Serial Number 007 s
(8)
The inspectors reviewed certification documentation for the eddy current calibraticr.' standard identified as Z1292, Heat No. 2185..
9 c.
PSI Data Review and Evaluation (73055)
,i Records of completed nondestructivb examinations wer'e selected and reviewed.to ascertain whether:,the'mer. hod (s), technique and extent of the examination complied L with' the -ISI plan and applicable NDE procedures; findings were 'groperly recorded and evaluated by qualified personnel; programatic deviations were, recorded as required; personnel, instruments, /calibra, tion blocksjand NDE materials (penetrants, cou;<lant:) were dedgnated e p l
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Records selected for this review are listed below:
Iso. No./ Item Weld I.D.
NDE Method 1-ISI-FW-MS-RC-1 1-MS-SW-B6 UT 1-MS-SW-83 UT 1-RC-SW-N5 UT 1-RC-SW-06 UT 1-RC-SW-P6 UT 1-ISI-RH-2 1-RH-FW-17(A)
UT 1-ISI-51-29 1-SW-FW-601 UT 1-ISI-CS-7 S1-13-1-SW-4 UT 1-ISI-51-10 SI-SW-C8 UT 1-ISI-CT-1 1-CT-SW-E4 UT 1-ISI-CT-14 1-CT-FW-185 UT 1-ISI-RC-23 1-RC-SW-A3 UT 1-ISI-FW-MS-RC-2 RC-2-FW-7 UT 1-ISI-AF-7 1-AF-SW-B4 UT 1-ISI-FW-MS-RC-2 1-FW-FW-486 UT 1-FW-SW-E3 UT Reactor Vessel Shell 1-SH-RV-010 UT Weld 1-SH-RV-004 UT Reactor Vessel Inlet Nozzle to Shell Weld UT Nozzle at 335' Reactor Vessel Inlet Nozzle to Shell Weld UT Nozzle at 95*
Reactor Vessel Safe Nozzle to Safe End UT End at 335' Reactor Vessel Safe Nozzle to Safe End UT End at 145*
1-ISI-FW-MS-RC-3 1-MS-FW-255 MT 1-MS-SW-A3' MT 1-MS-SW-A3A MT 1-MS-SW-A38 MT 1-RC-SW-03 PT 1-RC-SW-P8 PT 1-RC-SW-N6 PT 1-RC-FW-5 PT 1-RC-SW-02 PT Reactor Vessel Safe 1-SH-SR-01 PT End t
m
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1 11 1-ISI-RH-2 1-RH-SW-0198 PT RH-2 RH-FW-17 RT CT-15
- CT-FW-185 RT CS-7
- CT-SW-E4 RT AF-7
- 1-AF-SW-B4 RI
- Construction radiographs were reviewed to confirm ultrasonic signal reflector locations.
(2)
The inspectors reviewed records of the Steam Generator (SG) tubing eddy current examinations.
The reviews were compared with the applicable procedures and the Code in the following areas:
the multi-channel. eddy current examination equipment has been identified including indicator, meter, tube, strip recorder, and tape; method for maximum sensitivity,is, applied; method for determining material permeability recorded; material permeability,
has been recorded; ' method of examination has been recorded; examination equipment has been calibrated in accordance with the applicable performance reference; amplitude and phase has been calibrated with the proper applicable calibration reference and is recalibrated at predetermined frequency; 100% coverage of steam i
generator tubes occurs during the examination; and acceptance i
criteria is specified or referenced and is consistent with the procedure or the ASME B&PV Code.
The tubes selected for review by the NRC inspectors were originally examined by CONAM and sometime later independently examined again by TSL.
The objective of the examination by TSL was to assure the validity of the examinations conducted by CONAM.
The data comparisons made by the NRC inspectors indicated that with the exception of a few minor deviations due to probe. speed and independent calibration curves the data generated by the two independent examinations compared favorably.
Examination data for l
the tubes listed below was used by the NRC inspectors to make this comparison.
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12 TUBE ID Row - Column SG-A 12 -
6 15 - 74 15 - 86 41 - 74 10 -
8 29 - 14 SG-B 5-1 20 - 45 33 - 46 15 - 50 22 - 33 41 - 29 SG-C 14 - 77 29 - 29 5-23 21 - 21 22 - 33 31 - 34 Within the areas examined, no violations or deviations were identified, except as reported in paragraphs 6.a(5) and 6.a(6) above.
l I
_.___,____.._,_._-_.__._.___.,__,__.,______,.,--__._,.,.,__.,-,..,,__,m,
_ - _ _,. _.. _.,., _. _ _ -,. _... _. -. _ _ _ _. _ _.,