ML20077S314
| ML20077S314 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Crane |
| Issue date: | 08/12/1980 |
| From: | Fasano A Office of Nuclear Reactor Regulation |
| To: | Lester Tripp NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20077S281 | List: |
| References | |
| FOIA-83-349 NUDOCS 8309220016 | |
| Download: ML20077S314 (1) | |
Text
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August 12, 1980 MEMORANDUM FOR:
M. Tripp, Chief. Engineering Support Section #1, Reactor Construction and Engineering Support Branch, Region I FROM:
A. N. Fasano, Chief, Site Operations Section, TMI Program Office
SUBJECT:
USE OF FURMANITE FOR TEMPORARY REPAIR OF DH-V1 AT TMI-l The purpose of this memorandum is to formally request applicable regional review, evaluation and followup of the subject concern.
Reference documentation concerning this matter was discussed with and provided to you and S. D. Reynolds on June 30,1980 The issue is applicable to making a determination of the acceptable mettallurgical condition of DH-V1 for restart operation of TMI-1.
Preliminary findings of the in-office review, including any recommendations for additional licensee or NRC actions, are requested to be completed by August 31, 1980.
Please contact D. R. Haverkamp, Senior Resident Inspector, TMI-1, or myself if you require additional infonnation concerning this matter.
hW t sq A. N.
asano Chief, Site Operations Section TMI Program Office d
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J. Allan J. Collins R. Ca'rlson R. Keimig L. Gage 1
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i Metropolitan Edison Company ATTN: Mr. R. C. Arnold Vice President P. O. Box 542 Reading, Pennsylvania 19603 Gentlemen:
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Subject:
Region I Inspection Report No. 50-289/77-05 and 50-320/77-09 75 tpq This refers to the inspection conducted by Mr. A. Fasano of this office b
on February. 22-25,1977, at the TMI Site and at the Met Ed Corporate Office, of activities authorized by NRC License Nos. DPR-50 and CPPR-66 and to the discussions of our findirigs held by Mr. Fasano with Messrs.
Colitz,, Toole, and Lawyer of your staff at the conclusion of the inspec-tion, and to a subsequent telephone discussion between Mr. Colitz and Mr. Fasano on February 28, 1977.
Areas examined during this inspection are described in the Office of I
Inspection and Enforcement Inspection Report which is enclosed with this-letter.
Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observations by the inspector.
Our inspector examined the steps you have taken to correct some of the items' of noncompliance brought to your attention in the letters dated
,May 28, 1976 and August 27, 1976.
As shown in Item A of Appendix A to this letter, your corrective action for these items had not been comple-ted in ac.cordance with the commitments in your letters dated June 21, 1976 (GQL 0882), September 30, 1976 (GQL 1372), November 12, 1976 (GQL 1579), and September 21, 1976 (GQL 1318).
Therefore, in your response to Item A of Appendix A, as described below, we request that you also includs new date(s) by which the corrective action for these items will be completed.
Dget adI47
Metropolitan Edison Company 2
MAR 2 31977 Our inspector also verified the steps you had taken to correct the item of noncompliance brought to your attention in a letter dated November 18, 1976.
We have no further questions regarding your action at this 4
time.
1 In addition, our inspector examined those activities conducted under your license. relating to the subject covered in your letter to this office dated December 16,1976 (GQL 1692).
We have no further questions regarding this matter.
Based on the results of this inspection, it appears that certain of your activities were not conducted in full compliance with NRC requirements, i
as set forth in the Notice of Violation, enclosed herewith as Appendix i
A.
These items of noncompliance have been categorized into the levels as described in our. correspondence to you-da.ted December 31, 1974 This notice is sent to you pursuant to the provisions of Section 2.201 of the NRC's " Rules of Practice", Part 2. Title 10, Code of Federal Regulations.
Section 2.201 requires you to submit to this office, within twenty (20) days of your receipt of this notice, a written statement or explanation in reply including:
(1) corrective steps which have been taken by you and the results achieved; (2) corrective steps which will be taken to avoid further items of noncompliance; and (3) the'date when full com-pliance will be achieved.
i In accordance with Section 2.790 of the NRC's " Rules of Practice", Part 2, Title 10, Code of Federal Regulations, a copy of this letter and the 4
enclosures will be placed in the NRC's Public Document Room.
If this report contains any information that you (or your contractor) believe to be proprietary, it is necessary that you make a written application' within 20 days to this office to withhold such information from public disclosure.
Any such application must be accompanied by an affidavit executed by the owner of the information, which identifies the document or part sought to be withheld, and which contains a statement of reasons which addresses with specificity the items which will be considered by the Commission as listed in subparagraph (b)(4) of Section 2.790.
The information sought to be withheld shall be incorporated as far as possible into a separate part of the affidavit.
If we do not hear from you in this regard within the specified period, the report will be placed in the Public Document Room.
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dSIIEUIS77 Metropolitan Edison Company 3
Should you have any questions concerning this inspection, we will be pleased to discuss them with you.
Sincerely, x
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runner, Chief Re c' tor Operations and Nuclear S/pport Branch
Enclosures:
1.
Appendix A, Notice of Violation 2.
Region I Inspection Report No. 50-289/77-05 and 50-320/77-09 cc w/encls:
J. G. Herbein, Manager, Generation Operations - Nuclear J. J. Colitz, Unit 1 Superintendent R. L. Wayne, QA Manager, Design & Construction T. M. Crimnins, Jr., Safety & Licensing Manager R. W. Heward, Jr., Project Manager W. A. Verrochi, Vice President, Design & Construction G. Miller, Un'it 2 Superintendent s
Gerald Charnoff, Esquire Miss Mary V. Southard, Chairman, Citizens for a Safe Environment (Without Report) bec w/encls:
IE Mail & Files (For Appropriate Distribution)
Central Files Public Document Room (PDR) local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
Technical Infonnation Center (TIC)
REG:I Reading Room Region Directors (II, III, IV)(Report Only)
Comonwealth of Pennsylvania
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Miss Mary V. Southard, Chairman, Citizens for a Safe Environment j
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,u, II. I Form 12
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U. S. NUCLEAR REGULATORY CCIDfISSION 0FFICE OF INSPECTION AND ENFORCDd. INT REGION I 50-289 IE Incpection Report No:
50-289/77-05 and 50-320/77-09 Docket No:
50-320 DPR-50 Liccncee:
Metropolitan Edison Company License No:
CPPR-66 P. O. Box 542 Priority:
C Reading, Pennsylvania 19603 Ca tegory:
B-1 Safeguards
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Ler.ntion:
Middletown, Pennsylvania (Three Mi-le Island)
Unit 1:
Typa of Licensee:
Unit 2:
PWR 2772 MWt (Bul) of Inspection:
Routine, Announced Datca of Inspection:
February 22-25, 1977 Unit 1 Dates of Previous Inspection:
February 17-18, 1977-and 2 Reporting Inspector:
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. 3/23/77
.,. m A.4. F'sano, Reactor Inspector DATE a
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3/7.3/77 Accompanying Ins ectors: j S. Durr eactorInsktr DATE Y'f",
3 /23 /77 W/A.
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J/T. Smit 4, Reactor /ns DATE or Or.vi % :-
Oth;r Accompanying PersonneJ.:
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'! /13/7 7 DATE Revicved By: SD k23[i7
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l A. 4. Davis, Chief, IGactor Projects Section No.1, DATE l
Reactor Operations and Nuclear Support Branch l'\\
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Nonroutine Event Reoorts, Unit 1 Selected Reportable Occurrences were reviewed to verify that:
a.
The cause was identified and that details were clearly reported.to the NRC and facility management; Corrective action described in the licensee's report was taken to prevent recurrence; Each event was reviewed and evaluated as required by the Technical Specifications; and Safety limits, ifmiting safety system settings, and limit-ing conditions for operation were not exceeded.
This review included discussions with members of the plant i
staff, inspection of.PORC meeting minutes, internal site memoranda, physical observation of affected equipment, work requests, and surveillance procedures.
b.
The Reportable Occurrences reviewed were:
(1)
ER 76-40/3L, Abnormal Degradation of the Seal Ring in DH-V1.
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(2)
ER 76-41/3L, Empty Fluid Reservoir of the Hydraulic Shock and Sway Suppressor located in Position RC-14.
4 (3)
ER 77-01/1T, the "A" Diesel Generator, DG, would not start 3
in the event of an offsite power loss without an ES signal.
The inspector's findings were acceptable except for those c.
Unresolved Items delineated below.
Also inspection findings relative to additional information concer,ning these events are summarized, as appropriate.
(1)
With respect to ER 76-40/3L:
On November 6,1976, the body to bonnet seal ring on the Decay Heat Isolation Valve, DH-VI, which had been leaking.2
.5 gpm, began to leak excessively during a plant cooldown.
This valve is normally closed during power operation and the increased
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11 leakage resulted when the valve was opened to provide cooldown of the reactor coolant system.
The valve is not isolable from the reactor coolant system and, therefore, will require an extended shutdown to make permanent repairs.
The licensee chose to effect a temporary repair until the next refueling outage.
r An engineering evaluation of the problem determined that an acceptable repair could be made by drilling four holes, 90 ' apart, through the valve body in the area of the seal ring.
This would provide access to the thread relief area directly above the seal ring gasket and below the retaining ring.
A commercial sealing compound, "Furmanite," would be injected through special adapters threaded into the drilled holes.
The licensee engaged a consul. ting firm to evaluate.this method of repair.
The consultant performed a stress and fatigue analysis.of the effect caused by drilling the holes and found them to be acceptable within ASME Code established criteria.
The consultant also suaaested
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that. as a result of the chemical analysis performed by the licensee showina a leachable chloride content of 50 RgM and a total chlorida enntent of 1300 - 17nn opM, the nuclear steam system sunnlier (NSRM); Rabcock and Wilcox, be consulted concerning the advie=h414+y af f a4=r+4_ng Furmani+e.
The concern was the increased potential for stress corrosion cracking (SCC).
The final recommencation of the consultant was to use the Furmanite.
The NSSS letter, dated November 4,1976, advised that, due to the critical locaticn of the valve and the relatively high chloride content, they could not recommend the use of Furmanite.
Concurrently, the licensee stated that the laboratcry, on running a blank sample to verify the chloride chemistry, found the background contamination of chlorides to be 50 PPM.
Considering this, the laboratory felt that the actual chloride content was approximately 5-8 PPM.
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12 The ljcensee's staff reviewed the various racn---adatient_;
and decided to use the Furmanite due to the reduced
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chlbrice values reported by the lahv and thMher - -
p6sitive factors such as:
(1) the known low operating temperature of the valve,1400F; (?.) the corrosion resis-
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tant characteristics of 316 stainless steel; (3) the l
low oxygen content of the reactor coolant water; and (4) if the leak is completely stopped the area exposed to water will provide very low quantitites of leachable chlorides and no evaporating mechanism for concentrating the chlorides, thus, minimizing SCC problems.
The staff also recommended the following restrictions:
(a) The valve be repaired at the next refueling outage.
(b)
The valve (seal ring area) be completely sealed with Furmanite so that leakage does not cause vapor con-densation.'
(c)
The temperature of the valve does not exceed 100 C 0
l and material temperatures are kept as far below that i
as possible.
I The procedure using the Furmanite repair method was approved by the Plant Operation Review Committee on November 7,1976, and the leak was successfully repaired.
The inspector reviewed the above described repair program and was informed by the licensee that plans are now being made to leave the Furmanite repair in place beyond the next refueling outage for some extended period of. time.
The licensee also stated that further engineering evalua-tions are being incorporated into a report that is to be issued within the next 2-3 weeks.
This item, 77-05-02, is considered unresolved pending the NRC's review of the licensee's supplemental engineering report and the valve repair schedule.
This review will be completed prior to facility restart following the forth-coming refueling outage. '
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' g 631 PA83K AVENUC KING OP PatuSSI A. PENN5Yt.VANI A 19 40,G Docket No. 50-289 Metropolitan Edison Company ATTN: Mr. R. C. Arnold Vice President P. O. Box 542 Reading, Pennsylvania 19603 Gentlemen:
Subject:
. Inspection 50-289/77-14 This refers to the inspection. conducted by Mr. A. Fasano of this office on April 18-22, 1977 at Three Mile Island Unit 1, Middletown, Pennsylvania of activities authorized by NRC License No. OPR-50 and to the discussions of our findings held by Mr. Fasano with Mr. Colitz of your staff at the concTusion of the inspection.
Areas examined during this inspection are described in the Office of Inspection and Enforcement Inspection-Report which is enclosed with this letter. Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with l
personnel, and observations by the inspector.
Our inspector also verified the steps you have taken to correct the item of noncompliance brought to your attention in a letter dated March 23, 1977.
We have no further questions regarding your action at this time..
Within the scope of this inspection, no fi; ems of no,ncompliance were observed.
In accordance with Section 2.790 of the ilRC's " Rules of. Practice, Part 2, Title 10, Code of Federal Regulations, a copy of this letter and the enclosed inspection report will be placed in the NRC's Public Document l
Room.
If this report contains any information that you (or your con-tractor) believe to be proprietary, it is necessary that you make a written application within 20 days to this office to withhold such information from public disclosure.. Any such application must be accompanied by an affidavit executed by the' owner of the information, which identifies the document or part sought to be withheld, :nd which contains a statement of reasons which addresses with s;!acificity 4
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Metropolitan Edison Co.
2 gyg jg77 the items 'which will be considered by the Ccmmission as listed in subparagraph (b)(4) of Section 2.790.
The information sought to be withheld shall be incorporated as far as possible into a separate
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part of the affidavit, If we do not hear from you in this regard within the specified period, the report will be placed in the Public Document Room.
No reply to this letter is required; however, if you should have any questions concerning this inspection, we will be pleased to discuss them with you.
Sincerely,
. _ 4 d
. Brunner, Chief Re tor Operations and Nuclear p6pportBranch
Enclosure:
Office of Inspection and Enforcement Inspection Report Number 50-289/77-14 cc w/ encl:
J. G. Herbein, Manager, Generation Operations - Nuclear J. J. Colitz, Unit 1 Superintendent R. W. Heward, Project Manager, GPUSC Miss Mary V. Southard Chairman, Citizens for a Safe Environment (Without Report) bec'w/ encl:
IE Mail & Files (For Appropriate Distribution)
Central Files Public Document Room (PDR) 1.ocal Public Document Room (LPDR)
Nuclear Safety Information Center Technical Infonnation Center (TIC)(NSIC)
REG:I Reading Room.
Region Directors (II, III, IV) (Report Only)
Comonwealth of Pennsylvania Miss Mary V. Southard, Chairman, Citizens for a Safe Environment l
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U.S. NUCLEAR REGULATORY COMJiISSION t
OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
77-14 Docket No. 50-289 License No.
DPR-50 Priority Category C
Licensee:
Metropolitan Edison Company P. O. Box 542 Reading, Pennsylvania 19603 Facility Name: Three Mile Island Unit 1 Inspection at:
Middletown, Pennsylvania Inspection conducted:
April 15,18-22,1977 Inspectors:
/7 4-, M f/7/ 77 A. N. FAsano, Reactor Inspector date
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signed date signed date signed Approved by:
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- a. n. vavis, t.nier, xeactor t'rojects Section No.1 RO&NS Branch date signed Inspection Summary:
Inspection on April 15,18-22,1977 (Report No. 50-289/77-14)
Areas Inspected:
Routine, unannounced inspection of plant operations; followup on IE Circulars; general plant cleanliness; and a tour of plant areas.
The inspection involved 45 inspector-hours on site by one NRC inspector.
Results:
No items of noncompliance or deviations were found.
(N.
, Region I.. Form 12
-(Rev. April 77) se n. 1 ft Ann
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DETAILS 1.
Persons Contacted Mr. S. Bailey, Mechanical Engineer Mr. K. Bryan, Shift Foreman
- Mr. J. J. Colitz, Unit 1 Superintendent
- Mr. W. W. Cotter, Supervisor, Quality Control Mr. T. Crouse, Control Room Operator Mr. D. Deiter, Control Room Operator Mr. J. Fritzen, Senior Engineer Mr. J. Hall, Inservice Inspection Engineer Mr. C. E. Hartman, Lead Electrical Engineer
- Mr. G. A. Kunder, Unit 1 Supervisor of Operations Mr. W. M. Metzger, Mechanical Foreman Mr. L. Noll, Shift Foreman
- Mr. J. P. O'Hanlon, Unit Superintendent of Technical Support Mr. D. Pilsitz,. Shift Forena5
,Mr. W. E. Potts, Supervisor of Licensing
- Mr. M. A. Shatto, Engineer Associate III Ms. P. S. toner, Chemist Mr. J. Thunstedt, Control Room Operator
- Denotes those present at the exit interview.
2.
Licensee Action on ~ Previous Inspection Findings (Closed). Noncompliance 289/77-05-01:
Reference the following:
- IE Letter dated March 23, 1977.
- Licensee response letter dated April 12, 1977.
- Licensee Memos dated April 1,1977, April 4,1977 and April 5,1977 on the subject of training given to Electrical Maintenance and I&C maintenance personnel.
- Administrative Procedure 1001, Document Control, Revision 8, April 12, 1977.
The inspector reviewed the licensee's response to the noncompliance, failure to establish measures to assure that conditions adverse to quality are promptly identified and corrected.
The actions taken by e
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(Closed) Unresolved Item 289/77-08-01 : Revise procedure 1106-1, Turbine Generator, to require procedural step check off and procedural section signoff.
The inspector reviewed Revision 16, dated April 7,
'1977, of this procedure.
The revision includes instructions for the initialing of procedural steps and includes lines along the side of the steps to be addressed.
(Closed) Unresolved Item 289/77-08-02: Write alarm response procedure for alann added by C/M 518.
The inspector reviewed alarm response
. procedures PRF 3-6 and PRF 3-7, CRD Sysi.em AC Trip Confirm and CRD System DC Trip Confirm, respectively, Both procedures are Revision 0, April 8,1977.
(Closed) Unresolved Item 289/77-09-01 : Revise Refueling Procedures RP 1501 and 1504-14.
Th4 inspector verified that both procedures have been modified to include sign off lines to assure initialing of procedural steps.
Reference RP 1502-1, Refueling Operations, Rev. 4, April 5,1977 and RP 1504-14, Removal and Installation of Fuel Transfer Tube Blank Flange, Revision 2, April 8,1977.
(Closed) Unresolved Item 289/76-25-02: Safety Cabinets for Storage of Flammable Material in the 0/G room or their removal.
Metal safety cabinets have been installed in the D/G roan hall.
The cabinets were in place and found closed by the inspector.
N (Closed) Unresolved Item 289/77-05-0?: DH-V1 Supplemental Engineering Report and valve repair schedule.
Reference Met-Ed memo GEM 0715, Continued Operation of DHV-1 utilizing Furmanite March 4, 1977.' This report was reviewed.
The conclus' ns contain in the report in part are based on.a low level of ch ride 1 hing from the Furmanite.,
The licensee plans to operate until e1' refueling outage.
During the interim the licensee will review t onger term effects created I
by the use of Furmanite.
The NRC has ested and received samples f
. of Furmanite and independent analyse are eing perfortred to detennine the amount of leachable' chlorides i the Fur nite.
The final NRC position will be based on the resul s of the indepedent analysis. d, i
gl\\h This is unresolved item 289/77-14-2.
(Closed) Unresolved Item 289/77-10-01 : Code requirements to identify the ultrasonic test frequency.
Data sheet wsld number. NID-018, April ll,1977 was reviewed.
The data indicates that the Reactor i
Builcing Spray System pipe welds ware tested using a transducer
- frequency and control setting frequency of 5 Miz.
This satisfies the code requirements to identify the ultrasonic test frequency used.
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g Kino or mussia. PENNSYt.VAM A I S4H Docket No. 50-289 Metropolitan Edison Company ATTN: Mr. J. G. Herbein Vice President P. O. Box 542 Reading, Pennsylvania 19603 Gentlemen:
Subject:
Inspection 50-289/77-19 This refers to the inspection conducted by Mr. P. Kellogg of this office on June 7-9, 1977, at Three Mile Island Unit 1, Middletown, Pennsylvania, of activities authorized by NRC License No. DPR-50 and to the discussions of our findings held by Mr. Kellogg with Mr. J. O'Hanlon of your staff at the conclusion of the inspection.
1 Areas examined during this inspection are described in the Office of Inspection and Enforcement Inspection Report which is enclosed with this letter.
Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observations by the inspector.
Within the scope of this inspection, no items of noncompliance were observed.
In accordance with Section 2.790 of the NRC's " Rules of Practice", Part 2, Title 10, Code of Federal Regulations, a copy of this letter and the e'nclosed inspection report will be placed in the NRC's Public Document Room.
If this report contains any information that you (or your con-tractor) Selieve to be proprietary, it is necessary that you make a written application within 20 days to this office to withhold sucn information. from public disclosure. Any such application must be accom-panied by an affidavit executed by the owner of the i~nformation, which identifies the document or part sought to be withheld, and which contains a statement of reasons which addresses with specificity the items which will be considered by the Conmission as listed in subparagraph (b)(4) of i
Section 2.790.
The information sought to be withheld shall be incorporated as far as possible into a separate part of the affidavit.
If we do not hear from you in this regard within the specified period, the report will be placed in the Public Document Room.
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UUL 0 61977 i
Metropolitan Edison Company 2
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No reply to this letter is required; however, if you should have any questions concerning this inspection, we will be pleased to discuss them i
with you.
Sincerely, m s El o
. Brunner, Chief Rea r Operations and Nuclear Su port Branch
Enclosure:
Office of Inspection and Enforcement Inspection Report Number 50-289/77-19 cc w/ encl:
L. L. Lawyer, Manager, Generation Operations - Nuclear G. P. Miller, Superintendent R. W. Heward, Project Man.ager, GPUSC Miss ' Mary V. Southard, Chaiman, Citizens for a Safe Environment (Without Report) bec w/ enc 1:
IE Mail & Files (For Appropriate Distributi.on)
Central Files Public Document Room (PDR)
Local Public Doctanent Room (LPDR)
Nuclear Safety Infor1 nation Center (flSIC)
Technical Infomation Center (TIC)
REG:I Reading Room Reg' ion Directors (III, IV) (Report Only)
Conmonwealth of Pennsylvania Miss Mary V. Southard, Chairman, Citizens for a Safe Environment l
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0FFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
77-19 Docket No.
50-289 License No. DPR-50 Priority Category C
Licensee:
Metropolitan Edison Company P. O. Box 542 Reading, Pennsylvania Facility Name:
Three Mile Island, Unit 1 Inspection at:
Middletown, Pennsylvania Inspection conducted: ' June 7-9, 1977 Inspectors:
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A. B. Davis, Chief, Reactor Pro.jects diate signed Section No.1, RO&NS Branch Inspection Summary:
Inspection on June 7-9, 1977 (Report No. 50-289/77-19)
Areas Inspected:
Routine, unannounced inspection of plant operations including observations of the control room and a general plant tour; followup on previously identified Unres'olved Items;- followup on responses to NRC Bulletins and-Circulars; review of Licensee Event Reports. - The inspection involved 42' inspector hours on sir.e by two NRC inspectors.
Results:
No Items of Noncompliance were identified.
Rigion I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted
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Metropolitan Edison Company Mr. R. Barley, Lead Mechanical Engineer Mr. W. Cotter, Supervisor - Quality Control
- Mr. C. Hartman, Lead Electrical Engineer Mr. G. Hitz, Shift Supervisor Mr. G. Kunder, Supervisor of Operations Mr. L. Holl Shift Foreman
- Mr. J. O'Hanlon, TMI-1, Unit Superintendent Mr. J. Principe Quality Control Inspector
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- Mr. M. Shatto, Engineer Associate II, Nuclear Mr. H. Shipman, Operation Engineer II i
Mr. R. Summers, Engineer Nuclear II The inspector also talked with and interviewed 7 other licensee employees during the course of the inspection.
Other Accompanying NRC Personnel H. D. Thornburg, Director, Division of Reactor Operation Inspection
- denotes those present at the exit interview.
2.
Licensee Action on Previous Insoection Findings (Closed) Unresolved item 289/77-05-05:
Completion of revision documentation of limitorque adjustment procedures.
The inspector reviewed procedures 1420 LTQ-1,2 and 3 which have been revised and.
have been approved, completing this item.
(Closed) Unresolved item 289/77-14-02, DH-V1 Furmanite Chloride analysis.
Two samples of Furmanite were given to the NRC for i
analysis.
The first sample was approximately 4 grams, the second about 22 grams.
The samples were forwarded to the Idaho Health Service Laboratory (IHSL} for analysis.
The samples were analyzed for chloride content and for leachable chloride.
The first sample (4 gram) gave results that did not agree with results obtained from three laboratories doing similar analyses.cni the furmanite.
The second sample, 22 grams, was divided among this lab (IHSL) and two l
other laboratories.
The results from this sample were consistent with the licensee's results.
The total chloride is in the order of l
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50 ppm.
The leachable chloride is less than 10 ppm.
The most probable explanation of the high chloride results in the 4 gram sample is external contamination between the time of sampling and IHSL's measurement.
The inspector also reviewed the purchase request, order Number 31923 and discussed the method of receipt and handling the nuclear grade furmani te.
The furmanite was received on one sheet which was cut into strips about two to three inches in length and about k inch wide.
The pieces were kept in plastic bags for protection.
A total amount of 390.45 grams was used in the repair of va?ve OH-V1 The sample (4 gram) sent to IHSL had previously been sent to a GPU Laboratory, was held in this laboratory for a period of time and was then repackaged and sent to the NRC where it was ~ forwarded to IHSL.
The second sample was delivered to the NRC inspector from the original bag and immediately sealed in an envelope and forwarded to-IHSL.
Discussion with the licensee indicates that he is currently pursuing the purchasing of a suitable replacement valve for DH-V1.
3.
Plant Operations Shift Logs and Operating Records t
The Control Room Log Sheet entries 'for the period May 17 through June 7,1977 were reviewed for completeness.
Parameters recorded in the data sheets were independently checked by the inspector.
The comparisons were acceptable.
The log sheets were complete with required signatur.es.
The inspector had no further questions on this item.
Monitoring Instrumentation The following instruments were checked against the licensee's recorded data; BWST Temperature Sodium Hydroxide level and temperature Sodium Thiosulfate level and temperature
- Reactor Building Pressure Penetration pressure Reactor Coolant Pump Seal leak off flow
- RM-A-5, Radiation Monitor, gas The asterisk designates those recordings that were also verified at positions outside the controi room.
9.
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1 August 23, 1979 MEMORANDUM FOR:
Eldon J. Brunner, Chief, Reactor Operations and Nuclear Support Branch FROM:
Anthony N. Fasano, Inspection Specialist, Performance Appraisal Branch
SUBJECT:
PERMANENT CORRECTION TO THE DEFECTIVE DECAY HEAT ISOLATION VALVE DH-V1 AT TMI-l i
During a review of past inspection reports (50-289/77-05,14 aad 19) the subject valve was noted.
The licensee had made a temporary fix of the valve by using "Furmanite".
The inspection reports indicated closure of this item with the understcnding that a permancat corrective action would be taken during the 1978 refueling outage.
It was understood that either parts would be replaced or a suitable valve replacement would be accomplished.
Discussions with Mr. Haverkamp indicate that the Furmanite fix is still in place.
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Based on the original inspec. tion information it was and still is my conclusion k
that the Furmanite fix was to be considered a temporary fix.
It is my recommendation that the licensee (TMI-1) be requested to make a permanent mechanical fix of this valve before ret.urning to operation.
It is further recommendid that samples of Furmanite inplace be analyzed for residual chlorida content and that metalic samples be analyzed for effects.
b y/
.eng A. N. Fdsan Inspection Specialist Performance Appraisal Branch cc:
l R. R. Keinig D. R. Haverkamp I
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% * * * * * #g May 17,1979 HEMORANDUM FOK:
E. Brunnar, Chief Reactor Operations, Nuclear Support Brsuch, RI A. Gibson, Chief Health Physics Section MRU:
hsh TMI 2 Investigation e
ITEM OF CGICERN RELATED TO STARTUP OF THREE MIIE
SUBJECT:
ISLAND 1 Based on an interview performed on May 16,'1979, it appears that an operational related problem should be investigated prior to permitting 'DfI 1 to startup.
Shortly after the 1976 Unit 1 outage, a leak developed in valve DEV-1.-
DHV-1 is apparently a decay heat removal system; motor ' operated isola-tion valve, located in ' containment. Het Ed was permitted by the NBC to stop the leak by utilization of the "furminite" process under the proviso that the valve be fixed correctly within one year.
According to our source, he believes. the NRC may have granted permission for continued operation of the plant without repair of DRV-1.
. Picase review this issue and take action as required.
GP w
C. P.
as, Radiation Specialist TMI 2 Investigation i
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