ML20031C281

Compliance Rept 50-029/65-03 on 650609-11,21-22 & 0720. Noncompliance Noted:Excessive Tritium Releases from Ion Exchange Pit Leak

ML20031C281
Person / Time
Site:	Yankee Rowe
Issue date:	07/29/1965
From:	Robert Carlson US ATOMIC ENERGY COMMISSION (AEC)
To:
Shared Package
ML20031C278	List: ML20031C277 ML20031C281
References
50-029-65-03, 50-29-65-3, NUDOCS 8110070018
Download: ML20031C281 (23)

Text

{{#Wiki_filter:. P U. S. ATOMIC ENERGY COMMISSION v) REGION I DIVISION OF COMPLIANCE }h j July 29, 1965 1,- CO REPORT NO. 29/65-3 ,g + -g! l

Title:

YANKEE ATOMIC ELECTRIC COMPANY Of LICENSE NO. DPR-3 & mm-906 .) Dates of Visits: June 9 - 11, 21 - 22, 1965 E'- 7. % 6 4 ~ and Ju A 1965 [o/r I, R. T. Carlson, Reactor Inspector lJO By .or if ,l lI

SUMMARY

I #' The licensee is conducting an effective tritium evaluation and ~ control program. Federal and State Authorities have expressed interest in the tritium problem. Tritium released via the ion exchange pit leak exceeded the limits of 10 CFR 20, Appendix B, Table II, for liquid releases to the unrestricted area. A Form AEC-592 was issued. Pit repairs have been completed. Corrective and preventive measures relating to the recent reactivity incident have been placed La effect. A noise analysis study of the main coolant system has been initiated. I Primary to secondary leakage has been detected in steam generator No. 3. The first shipment of irradiated fuel to Nuclear Fuel Services, Inc., has been dispatched. Details of the shipment are dis-cussed in the report. The licensee has been presented with a safety award by the Hartford Insurance Group. (continued) t i h l i: -- 8110070018 650816 . ?/ PDR ADOCK 05000029 G PDR

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. DETAILS I. Scope of Visits hf Mr. R. T. Carlson, Reactor Inspector, Region I, Division of Comr 1 lance, visited the Yankee Atcxnic Electric Company [3 (Yankse) reactor facility at Rowe, Massachusetts, on June 9 - A1, 21 - 22, and July 20, 1965. Mr. H. W. Crocker, In-spvction Specialist (Criticality), Region III, Division of 4 h[f Cumpliance, accompanied Mr. Carlson during the June 9 - 11, .N 1965 visit. The visits included the following: $j

Y A.

A review of the effectiveness of the licensee's [R,({ tritium evaluation and control program. / 4 D. A review of the radioactivity releases from the .s s: [ lon exchange pit and the recently completed pit '[@" repairs. + f; C. A review of the corrective and preventative measures i j taken with respect to a recently experienced reactivity abnormality. t D. General discussions with cognizant personnel. regarding [ the current status of the main coolant system noise ,] analysis. E. I A review of the licensee's initial irradiated fuel shipment to Nuclear Fuel Services, Inc. (N"S). F. Discussions w',th licensee personnel regarding recent ['; problems at ' he Experimental Boiling Water Rm ctor (EEWR) and the Nuclear Ship SAVANNAH (NSS). l j The principal persons contacted were as follows: 1 l 4 Yankee Mr. W. P. Johnson, Plant Superintendent l l l (continued) l , l '* ,m, ~ V"4'A. \\ ;g..: a L. k.

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e Scope of Visits (continued) Mr. C. E. Haseltine, Chief Engineer Mr. J. B. Randazza, Assistant Chief Engineer Mr. G. C. T.ndognini, Plant Reactor Engineer Mr. J. R. Himmelwright, Technical Assistant 0 Mr. L. H. Heider, Chemical Engineer Mr. D. B. Pike, Plant Health Physicist Mr. J. Devincentis, Engineer (Boston Office) 3;; Westinghouse Atomic Power Department (WAPD) h gn sW Mr. B. James, Engineer (( Mr. C. Benton, Engineer .35! !T II. Results of Visits p,<? A. Tritium f-1. Evaluation and Control Program The inspector reviewed facility records and held i discussions with Messrs. Johnson, Heider and Pike, to determine the ef fectiveness of the licensee's tritium evaluation and control program *. The following is provided for information purposes: The periodic sampling program has been con-a. tinued. The tritium concentration in the vapor container atmosphere has decreased, based on the results of the latest vapor container atmosphere condensate sample (0.56 uc/ml); however, the licensee is co. - tinuing to limit personnel access to two hours per week per man pendt ig further (continued)

• CO REPORT NO. 29/65-2, paragraph II.B.

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= -4_ Results of Visits (continued) evaluation. The concentration in the main coolant was 1.53 uc/ml on June 4,

. [

1965 - 2.8 uc/ml in February 1965. The I most recent results of other samples were ] noted to be equal to, or less than, those previously reported *. The sample analyses are currently being done by Isotopes, Inc.,

gfj, ibl; Westwood, New Jersey.

Controls for Radiation, Inc., Cambridge, Massachusetts, has also b2en ibkjf used on occasion.

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(;Sh b. The licensee is purchasing a scintillation '{" counter from Packard Instrument Company for the analyses of liquid samples. The estimated cost is $6,000. The instrument is expected I ~ to be available for use prior to the Core IV - V outage, August 1965. {' c. Difficulties have been encountered in the search for adequate tritium air monitoring equipment. According to Mr. Pike, the background from radon-222 in the vapor con-tainer abnosphere prevents an accurate deter- / mination of the concentration of tritium i pending a decay per'iod of at least two weeks. The time delay negates the main advantage of having on-site equipment. The licensee is cur-rently consult'ing with the Nuclear-Chicago Corp-oration for assistance on this problem. The inspector suggested a contact with the E. I. DuPont de Nemours and Company, Savannah River l Plant, for possible further assistance in this ( F (Continued)

• Ibid.

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. Results of Visits (continued) regard. The licensee will calculate at-k mospheric tritium concentrations, i.e., p; in the vapor container and other likely points, on the basis of atmosphere conden-sate sample results pending resolution of the radon problem. L E({sc; d. An item of noncompliance with respect to

f tritium releases via the ion exchange pit leak is discussed in paragraph II.B.

l:f[. 'I:. (( Based on the results of this and previous

• reviews and discussions, it appears to the inspector that j /..

the licensee is conducting an active and effective tritium evaluation and control plogram. 2. Federal and State Interest. The inspector obtained the following information i regarding Federal and State interests in the tritium ,l problem at Yankee from a review of facility records and discussions with Messrs. Johnson and Pike: The U. S. Public Health Service, Civision of Radiological Health, through the Massachusetts Department of Public Health, requested and was l granted Yankee's cooperation in conducting a tritium release study at the Yankee Facility. The study, as far as the inspector could de-termine, consists of the taking of a number of samples, both in-plant and environmental, on a (continued)

• Ibid.

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) 1 < Results of Visits (continued) l one-time-only basis. The samples were obtained i on June 24, 1965 in the presence, and with the assistance, of representatives of the three above named organizations and 7 representative from the ri Northeasterr4 Radiological Health Laboratory (U. S. Department of Health, Education and Welfare), Winchester, Massachusetts. The latter organiza-tion is scheduled to perform the sample analyses.

z Yankee personnel obtained duplicates of all the E;Nh samples except those from the waste system cover (f[?j gas and the vapor contain3r atmosphere.

The Yankee pfd samples have been aaalyzed by Isotopes, Inc. The IEN g ;p Uf ' results were not significantly different from those previously obtained and reported, Mr. Johnson said that Yankee will be provided with a report of the [ results of the samples obtained by the Division of Radiological Health. l-Yankee has also agreed to take, and has been taking, samples of the condenser cooling water effluent for the Massachusetts Department of Public Health. Samples are obtained each time a release is made i via the normal waste disposal system. The samples are disposed of if not called for within a week. B. Ion Exchange Pit Leak - An Item of Noncompliance Repairs to the ion exchange pit have been completed and the pit returned to normal service. The cause of the previously [ experienced leakage

• was attributed to a faulty concrete con-i struction joint in the northwest corner of the pit, near the 1

l b (continued)

• CO REPORT NO. 29/65-2, paragraph II.C.

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17 !: k Results of Visits (con tinued) f [ 3Yc ,ds it floor. The faulty arcia was chipped out and regrouted. This b: was followed by the inatallation of a waterproof membrane, jj,, protective pads and walls as previously described *. Mr. m;}$ Johnson told the inspector that there has been no indication D2it of pit leakage since completion of the repairs. [hkU l '~ The inspector reviewed the facility records reflecting M radioactivity releases to the ground via the pit leak. The ! SIl average concentration of tritium released, occurring during f ';g the period of the licensee's cognizance of the presence of {

tritium, i.e., March and April 1965, was 1.5 x 10-2 uc/ml.

t. -

This concentration is in excess of the value listed in 10 l's CFR 20, Appendix B, Table II, 3 x 10-3, and is in non-compliance with the technical specifications, paragraph D.2.g. (2). A Form AEC-592 was issued. ~ Other radioactive constituents contained within the releases from the pit were within 10 CFR 20 limits. The inspector noted that the above facts were adequately docu-mented**. I C. Reactivity Abnormality The inspector reviewed facility records and procedures and held discu ssions with Messrs. Johnson, Heider and Pike, to determine the status of the corrective and preventative measures H that were proposed by the licensee following the reactivity ab-normality that was experienced in March 1965***. All proposals ) have been put into effect except that pertaining to the instal-i ~ lation of a pressure sensing line on the input side of the filter l unit. Mr. Johnson told the inspector that the latter modifica-tion would be made during the Core IV - V outage. (continued)

• Ibid.
  • CO REPORT NO. 29/65-2, paragraph II.C.
    • CO REPORT NO. 29/65-2, paragraph II.A.5.b.

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f ; - k . Results of Visits _ (continued) Noise Analysis D. The inspector obtained the following information re-l sis of the garding the licensee's plans to conduct a noise ana y l report on the main coolant system

• from a review of an internasubje h

site. r y The fluctuations in main coolant flow and nuclear powe i in an /. level will be measured at different operating condit ons p] y;g the two and to attempt to determine the relationships between I" detect possible fluctuations caused by internal vibrations; diation 1.e., those front.the, core internals and/or the lost irraThe da j l Qfy with that obtained from an analytical vibration stu y

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program test specimens. m Il being conducted by WAPD. l W' e' t Irradiated Fuel Shipment _ .[ [ E. Yankee The initial shipment of irradiated fuel from the [- Services, Inc., Facility at Rowe, Massachusetts, to Nuclear Fuel July 26, 1965**. T& ten assembly,

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near West Valley, New York, was dispatched on The shipment was made using the Westinghouse 75 I d to Yankee ***. fs This was the first use of the cask. Yankee site prior to its use. k The inspector made visual examination of the caswitnessed the l t conducted; and Q and its associated equipment; reviewed procedures and facility records of tes s d Westing- } held discussions with cognizant personnel of Yankee an l following ,j- ;, house. i paragraphs: i (continued) e-f. 29/65-2, paragraph II.H.l. by phone

• • Actual date of shipment transmitted to inspector
• CO REPORT NO.

communication from the licensee. and associated documentation

license,

• • • The cask hazards analysis, are filed under DN 70-596.
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~ m . Results of Visits (continued) 1. Assignment of Responsibilities and Preparedness of Personnel Westinghouse was delegated the responsibility, by Yankee, for the preparation and supervision of the loading of the cask *. Mr. Ben James was the field $[ representative of Westinghouse. The inspector dis-cussed the delegation of responsibility with Mr. h@y} p Johnson, who acknowledged that Yankee maintained overall responsibility for the shipment. Mr. j f Haseltine was following and coordinating the on-

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site activities for Yankee. T@[T ]; The inspector held preliminary discussions with t Messrs. Haseltine, Heider, Andognini, and Pike, [- on June 9, 1965, to assess their knowledge of ,.l the equipment, requirements of the shipping .i n license, and their individual responsibilities in that regard. Based on these discussions, the inspector concluded that their collective knowledge of these items was marginal. This subj ect was dis- 'j cussed with Mr. Johnson on June 9, 1965, who stated

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that a meeting would be held to more adequately in-form the Yankee personnel. Subsequent discussions i with the persons involved, indicated a greater awareness of the above listed items than had been previously noted. -5 4 2. Cask and Associated Equipment i A number of items were noted to be at variance j with the descriptive material referenced in the '{Y (continued)

• Yankee Application for shipping liccnse, April 21, 1965, page 2.

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h V PIl Results of Visits (continued) gj, 1.h+ h license. All of the items noted have been accounted for in formal submittals to DML by ,3 8 7 Westinghouse and Yankee

• with the following

%n exceptions: a. A 1/8" hole is drilled through the internals in one of the three cask-mounted connectors lY, in each of the two secondary cooling systems **. [ di The holes are to provide pressure relief to

w the secondary system should the hoses become if disconnected during shipment.

The drilled 'A connectors are visually identifiable. ,O .= b. Spare secondary cooling system hoses and fittings are available on the car ***. I c. The Application states that the primary cooling system pressure relief valve will be equipped with a particulate filter on the dis-charge cide. The actual installation includes an extension hose connecting the discharge of the relief valve to a 30 gallon drum mounted on the railcar. The drum vent incorporates the i specified filter. f d. The primary system pressure gauge and sampling l nozzle were noted to be protruding beyond the i periphery of the cask lid. As such, they were subj ect to damage by striking. The inspector (continued)

• Letter from Westinghouse to DML dated May 17, 1965; letter from Yankee to DML dated July 1, 1965; and others.
  • This item is in accordance with verbal agreements made between representatives of Westinghouse and Yankee, and DML.

The in-spector obtained this information through phone communications with DML.

• • • Ibid.

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~, , Results of Visits (continued) discussed this with Mr. Johnson. The protruding items were subsequently noted to have been re-positioned in the available lid recesses, e. The cask body weldment was noted to be equipped with two of the gas pressure relief devices described in the Westinghouse Application *. g The inspector noted that one of these devices S,, was bent approximately 15 degrees at the weld 57[ 7 joining the head of the device with its throat ,l 4 section. The inspector discussed this with Mr. Johnson who subsequently 3tated that both [g he and Mr. James had inspected the bent device 3 ./' and concurred in the opinion that the integrity of the device had not been affected. B n The cask and associated equipment examined by the { inspector appeared to be in compliance with the ~ requirements of the license. It is noted by the inspector that some significant submittals by Westinghouse and Yankee have not been incorporated in the license by specific reference **. Consequently, a recent submittal by Yankee *** is i considered by the inspector to be acceptable for the first shipment ****. J+ h l 3. Hydrogen Problem 7 l l Hydrogen was generated within the cask during l flushing and hydrostatic testing preparatory l L. l (continued) j t l [

• Letter from Westinghouse to DML dated August 24, 1962.

f

• • e.g., Letter from Westinghouse to DML dated May 17, 1965.

I

• • • Letter from Yankee to DML dated July 1, 1965.

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• • • • Discussed in telephone communication with DML, July 19, 1965.

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s, Results of Visits (continued) to loading. The inspector noted gas bubbles rising to the surface of the water-filled cask during a period when the lid was removed. Initially, representatives of both Yankee and Westinghouse attributed this to entrapped air. [ The inspector discussed with Mr. Johnson the i. advisability of identifying both the composition jg. and source of the bubbles before loading the fuel. ggf Mr. Johnson said that this would be done. The 1lg bubbles were subsequently determined to contain {,;t 45% hydrogen and to be coming from the fuel basket. y: d{p Westinghouse made an evaluation of the problem ((^' and submitted a report of their findings and ~ conclusions to Yankee. The inspector reviewed f~ a copy of the report at the site. The report attributed the bubbles to corrosive attack on the materials of construction within the basket. l The following statement was noted. "On the basis of these tests, we have l concluded that the basket will perform l' in the manner intended during normal transport and that corrosion rates for j the materials are such that no signi-I ficant change in mechanical integrity is anticipated." { The report did not discus,sjthe possibility of forming explosive mixtures of gases above the c surface of the primary water. The inspector dis-I cussed this with Messrs. Johnson and James, both ,J of whom stated that they did not expect any signi-ficant amounts of hydrogen to be generated by this means. In any case, they stated this was no different (continued) i m-u,nug ap\\ w.=, q kr -s v

M hf 4 Results of Visits (continued) g 1

1 1

from hydrogen generation by radiolytic dissocia-d tion of the water, which they have no control over. It is noted by the inspector that neither the cask $dd hazards analysis nor the submittals by Westinghouse f,33 and Yankee to DML address themselves to this problem *. The inspector observed the cask loading operations. 7 There was no evidence of bubble generation noted FN6 or reported. The cask loading is discussed further f,.$ in paragraph II.E.6. tr{ Periodic liquid and gaseous samples were taken ['g. from the water in the cask subsequent to its load-4.1 I ing. The inspector reviewed the results of these samples and noted the only significant concentra-tion of the materials of construction of the basket wa' rickel, 1.35 ppm. The maximum concentration of hydrogen gas was 35% by volume. Mr. James told the inspector that he would be present during the unloading of the cask at NFS, and that he planned to check conditions at that time **. 4. Procedures Procedures covering the fuel shipment operation were available at the site and were considered to be ade-l quate by the inspector. Some special procedur,s l were generated as the operation progressed. Mr. James was authoring the procedures. Mr. Johnson told the inspector that all procedures were reviewed l by Yankee. (continued)

• Data provided DML and CO:HQ by the inspector on June 10 and 18, 1965.

l

• • The Co inspector assigned to NFS has been briefed on all noted l

problems. 1 g,,,j- - ~ [(gk g y.: b -.g - --} e.[id k sp g.. = -.n. s a

s Results of Visits (continued) 5. Preloading Tests and Calibrations j i The inspector held discussions with Mr. James who said that the following preloading tests and f calibration checks had been completed: l ) Calibration of all cask instrumentation. a. 3E [f[', 2 b. In-place test of primary system relief s A valve. The valve relieved at 73 psig vs. k t!$il a set point of 75 psig*. h'W [ C7 Flow equalization test of the two primary c. system pumps. Mr. James told the inspector i ^ that the valves were sealed in the calibrated positions. d. Phase checks of the building and railcar g power supplies for the cooling pumps. 7 Mr. James told the inspector that the secondary i cooling systems were operating continuously while 'l the cask was in transit from Westinghouse to the Yankee site, a total of four days. Approximate ly 1/4 tank of fuel was consumed during this period. ,). a A trial run in moving the cask from the yard to g. the irradiated fuel pit revealed inadequate 1 clearance during the lift operation between the p' l bottom of the cask and the building roof. In-g stallation of a shorter cable on the yard crane f' and raising the crane hook up-limit by six inches resulted in adequate clearance. Mr. Haseltine y' j told the inspector that the modifications had been l reviewed with the crane manufacturer and found to be adequate. (continued) l i )

• Westinghouse Repor t WCAP-1859, paragraph 4.2.0.

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\\ _, Results of Visits (continued) 6. Cask Loading Cask loading operations were done under the direction of Messrs. Andognini and Himmelwright. A health physics representative was present throughout the operation. Relocation of the irradiated fuel stored in the pit had been completed prior to moving the cask into position *. d__ w. A sequential loading procedure was employed. $[F Neutron multiplication in the cask was monitored L'/l6; ) I ?k daroughout the operation. A used reactor startup 8 >* source and a miniature fission counter were employed for this porpose. The minimum inverse multiplication I observed by the inspector was approximately 0.9. The license does not include a requirement for monitoring neutron multiplication during loading operations. l The licensee's original plan was to load the ten hot-test assemblies, decay-heat-wise, of the irradiated j fuel available in the pit **. This would have max- ) imized conditions for the subsequent heat transfer tests. However, a malfunction in the irradiated fuel handling boom necessitaced the use of alternate j loading equipment. With this equipment, only a t limited amount of the fuel in the pit was available. l The assemblies loaded are listed on Figure 1. ,j The inspector noted that the fuel assemblies were being charged such that the weight of each assembly would be borne by a flat side of the assembly during horizontal storage of the cask, its normal position on the railcar. (continued) }

• CO REPORT NO. 29/65-2, paragraph II.F.
  • Discharges from Cores I, II and III.

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\\. 1 Results of Visits (continued) 7. Post-loading Tests and Preparations for Shipment The inspector reviewed facility records and held discussions with Messrs. Haseltine, Heider and Pike regarding post-loading tests and other steps taken to ready the cask for shipment. The cask was hydrostatically tested for 45 minutes at 45 psig following torquing of the lid closure f;Y. bolts to 600 foot-pounds. There was no leakage diil noted. Heat transfer, shielding and contamination j jj_ tests were also completed satisfactorily and in D @g4 accordance with the requirements of the license, y 'ae A shAelding survey was conducted by the inspector b and confirmed the recorded data. The licensee concluded that operation of the cooling systems was not required for this shipment. Conse-quently, an auto-pressurization test of the primary system was not conducied. The records of cask pressure and temperatore for the 24 hour period preceding the last visit indicated that these param-eters were stable at 6 psig and 105 F. The required seals were installed on the cask head bolts. The seals had not been installed on the primary system drain and vent valves. Mr. Haseltine j ~ said that a final flushing of the cask was contem-l- 1 plated prior to shipment and that the required seals would be installed at that time. The rail-O car was noted to be posted with four " Caution - l Radioactive Materials" signs, one on each side. l A similar label had been prepared for application y. to the cask. Mr. Pike said that this would be installed prior to shipment. ( c o n t *. u e: d i 1 [ ^ J q - e .\\w a q@ p.~ ..m. m.

- Lj Results of Visits (continued) ', Mp fig F. Organization g ,6% Mr. J. E. Howard, Reactor Engineer (Boston), has iiif terminated his employment with Yankee to form Nuclear North-i hiQ east, a consulting firm in Hamilton, Massachusetts. Mr. gig Haseltine told the inspector that a replacement for Mr. '5-Howard was being sought CJtside the Yankee organization. J.N 4; G. Steam Generator Leak r. Steam generator No. 3 has developed a primary to i secondary leak. The current leak rate is calculated to be ~ i ca two gallons per day. The specific activity of the secondary 12" water in steam generator No. 3 is 5 x 10 7 uc/ml, a factor of 10 to 50 above its normal value. The activity in the remaining three steam generators is normal. Activity analysis of the water in steam generator No. 3 has been increased from once per week to daily. l Mr. Haseltine told the inspector that there has been no previous history of detectable leakage in any of the steam I generators. Repairs to the No. 3 unit are scheduled for the Core IV - V outage. H. Miscellaneous 1. Experiences at Other Facilities i l The inspector held general discussions with j Messrs. Johnson and Haseltine regarding recent i experiences at EBWR and NSS. These subjects were discussed during phone conversations preceding the last visit and during the course [ of the visit. (continued) s $r m r --y.-. -,m 4 - 'qg. (g,.:;, '.. i'K w:c,yh( ' g s gs: .y

- Results of Visits (continued) Mr. Johnson was initially uninformed with respect to the experience of the EBW2, i.e., the revelation of extensive defects in the primary piping system and in the stainless steel cladding of the reactor vessel. He subsequently related to the inspector the gist of a phone conversation held by him with Mr. G. Reed, Yankee Operations Manager, on this subj ect. Mr. Reed apparently had y been previously informed on this matter. His

ijj stated position, as related to the inspector vf

~5) by Mr. Johnson, was that the cracks in the cladding of the EBWR were due to chloride stress corrosion; and that this was the result 8 of problems with main coolant chemistry that is typical of BWR's. Mr. Reed also associated the fuel failures experienced at Dresden with 3 the same general problem of main coolant chem- [ istry. He sees no problem with Yankee and, as i of now, plans no maj or investigation of the [ Yankee Pacility in this regard. HCWever, Mr. Haseltine told the inspector that they were considering an inspection of the interior of [ the pressurizer during the Core IV - V outage. The inspector also discussed the apparent causes of the recent failure.. of the main coolant pumps on the NSS* as relate 2 to the containt ant leak rate test scheduled to be performed at Yankee at the start of the Core IV - V outage. 1 2. Modifications l i a. Pressure Reducing Orifices - Change No. 62 I Change No. 62, approved by DRL on April 30, 1965, i (continued) t i tCO REPORT NO. NSS/65-4, paragraph II.C. [ s ,. N ~ --,v-. .i W., "... -. AfW' fYL&lchN

x It fi Results of Visits (continued) i authorizes replacement of the pressure reducing orifices located in the primary cooling system I. bleed line with new orifices that will limit l a flow within a specified range. This work has not yet been done. Mr. Johnson told the in-f spector that it would be done during the Core IV - V outage je b. Filter in Waste Liquid Transfer System by

ap The inspector noted during a tour of the facility

$h that a temporary filter has been installed in the , hgr common discharge line from the waste liquid trans-6? fer pumps. The filter was being used for the gross removal of particulates in the waste gen-erated during the flushing of the spent deionizers, prior to processing these wastes through the evap-l orator. The results obtained have encouraged ( Yankee to consider making the installation perma-nent. The inspector pointed out that a perma-nent change in the installation would probably require approval by DRL. c. Flow Meter - Primary Water Makeup The installation of a flow metering device in the primary water makeup line from the primary water storage tank to the suction of the main coolant system charging pumps is being con-sidered. Mr. Johnson said that a proposed change would be submitted to DRL in the near i fu ture. t. 3. Safety Award f A safety award was presented to Yankee by repre- { l sentatives of the Hartford Insurance Group while i 1 l l } l l (continued) 3 N g -, .z fh b N n.

=, = f' r s Results of Visits (continued) the inspector was present for the June 21 - 22, 1965, visit. The inscription on the plaque reads as follows: " Presented to Yankee Atomic Electric Company in recognition and appreciation f of outstanding achievement in the interest of safety for the five year period from 'Ws January 1960 to January 1965." 7[h 6 4. Training

• i, 4,p The inspector noted that a reactor operator

(? training and reference manual was in the process of preparation. Mr. Johnson said that the ma- { terial was being prepared under the direction of I Mr. Andognini and that copies of the portions completed thus far have been issued to members [ of the support staff and the senior reactor I operators. The inspector discussed the pro-i posed contents with Messrs. Johnson and l Andognini and concluded that the described f material would prove helpful in maintaining i the proficiency of the operating personnel. 5. Visitors t 1 Three representatives of the Interretional Atomic l' q Energy Agency (IAEA) visited the plant on June 1 and 2, 1965. The purpose, according to Mr. Johnson, was to install seals on a missile shield inside the vapor container. The seals were installed by drilling l holes in some of the missile shield holddown bolts. As described to the inspector by Mr. Johnson, the installation of the seals has not affected the in-tegrity of the shield. l t L 6 (continued) l i. s. . -._ ) ss, \\j: s: in ~ ~ .s ,h ) Mn o @ M. - 4

r ( Results of Visits (continued) Mr. P. V. Judd, USAEC, Shippingport Atomic Power Station, was also a recent visitor to the site. Mr. Johnson told the inspector that present operations at Shippingport utilize more manpower than was used for similar operations at Yankee and that Mr. Judd was reviewing Yankee's organizational structure in conjunction with a planned reduction-in-force at Shippingport. y MW Three representatives of Rochester Gas and Electric [;;$r Company, Messrs. J. L. Cooley, E. J. Nelson and ['h L. D. White, Jr., were conducted on a tour of the 1 Yankee Facility by Mr. G. Reed, Operations Manager, f#g Yankee, during the period the inspector was present 4.m' on June 22, 1965. Uf s Mr. P. Allister Burt, Station Superintendent for W. Niagara Mohawk's Nine Mile Point Nuclear Sta tion, (( {" was also a recent visitor. R h I. Exit Interview Exit interviews were held with Mr. Johnson on June 9, 11 and 22, 1965, and Mr. Haseltine on July 20, 1965. The main y topics discussed included: 1. Radioactivity releases via the ion exchange

a;.

pit leak. i-FL ' 2. The proposed installation of a filter in the T' liquid waste transfer system and a flow meter in the primary water makeup system. '{ }: 3. The installation of seals on the vapor container 2, missile shield. [ i .s-(continued) h. . [s,, p I_ -_-_-.y, g oi, .2.1 g ih..[. p. . s z w

k,, Results of Visits (continued) 4 The extent of the knowledge of Yankee personnel regarding the specifics of the irradiated fuel [ shipment. {-'; 5. Cask instrumentation, including protruding gauges p and the bent gas pressure relief device.

.a s

6. Hydrogen generation within the cask. Q {d t, 7. Recent operating experiences at the EBWR and NSS,

,3

' d) The comments made by the persons interviewed regarding f0M f,h... these topics are included in the body of the report. i.'

Attachment:

k Figure 1 l e h' 3 t a a l (s t,, -:- @ .-. -.. ~ - - - - - - - + , ;.u [; R.U ?g ; 4, ,r e, M N,G ~-n ~< d

~ p YANKE'E ATOMIC ELECTRIC COMPANY IRRADIATED FUEL SiiIPet*NT l4tj B-99 jN i.4 II A-130 B-88 i~b} 10,264 .N II, III 77 B-84 11,190 11,889 I II l ~ l A-149 B-109 10,264 l~ II II j' j 11,206 11,206 L B-111 A-128 11.206 B-88 j 11,206 10,264 II i 11,206 Legend: B-99 - Fuel Assembly Number II - Core (s) Exposed In l 10,264 - Burnup, MWD /MTU I i i Fiqure 1 Cask Loading Arrangement w - nW A ,}}