IR 05000270/1974007
| ML19317D368 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/23/1974 |
| From: | Jape F, Robert Lewis NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19317D364 | List: |
| References | |
| 50-270-74-07, 50-270-74-7, NUDOCS 7911270580 | |
| Download: ML19317D368 (14) | |
Text
{{#Wiki_filter:. UNITCD STATES , Mi! [ p[.N./t, ' DIFICTOPATE OF PSGUIATCRY OPERATIC:iS . ATOMIC ENERGY COMMIS310M (' L.
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Facility Nato: Oconec Unit 2 Dochet No.: 50-270 Licence No.: DPR-47 Category:
M ention: Seneca,Southdarolina . Type of License: B&W, TWR, 2568 Pv(t) 'Pfpe of Inspection: Routine, Unanncunced Dato.s of 7<<spection: October 1-4, 1974 Dates of Previous Inspectien: ' August 29, 1974 Principal Inspector: F. Jape, Reactor Inspector Facilitics Test and Startup Dranch Accompanying Inspectors: R. F. Rogers, Reactor Inspector Facilities Test and Startup Branch T. N. Epps, Reaccer Inspector Facilities C erations Branch
'Cther Acconpanying Persennel: None ' [d ' 'U ~ 4 */ -dfd-L Principal Inspector: s_ Date F. Jape, ' Reactor Inspector / Fa,cilitics '"est and Stdr' cup Branch . , Revicved ty: 4 (ni/f.
..ki% .- r.t/ /o-23 W i Date-R. C. Lovis, SeniorfP.cactor Inspt ctor Facilities Test and' Secrtup Brandh .
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R0 Rpt..No. 50-270/74-7-2- ~ . I') -, w.
, - SDSUI.Y OF FINDINGS
I.- Enforectent Actica . .
A.
Fiolations 1.
.Mua following violations are cencidered to be Category II severity: , _ n.
Conduct of Testing , Criterion 'XI of Appandix 3 to 10 CFR 50 requires testing I to be perforced and documented in accordance with written t i test procedures.
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Centrary to the above, the require:ents for sera tests ' vere not properly docu=ented and discrepancies wurc ,
! not expeditiously resolved or corrected.
(Details II, j i paragraphs 2.a, 2.b, 2.c, 2.d, and 2.e) b.
Exceeding Powet Level Cutoff Limit , , Paragraph 3.5.2.5d(2) of the Technical Specifications i . requires xenen reactivity be asymptotically approaching , j equilibrium at steady-state rated power prior to ' j increasing reactor power above 82.5%. . j Contrary to the 1bove, on June 20, 1974, power was - ?: H increased above S2.5% prior to establishing. xonen . .'- equilibrium.
' e. ;. Duke Pouer Ccepany reported the above violaticu ~ in ' ' Abnor=al Occurrance Report No. A0 270/74-8, dcted 5? June 28., 1974.
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Failure to Provide Redundant Boric Acid Scurcer, .:...J Technical Specification 3.2.2 specifics-the redundant boric acid-sources requirca during reactor operation.
,-{ $5 Contrary to tha above, on July 18, 1974, the volume of concentrcted beric acid was less than specified.
'l Duke Power Company reported the above violation in - ', Abnornal' Cccurrence Raport' No. A0 270/74-9, dated July 29,;1974.
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Power Level Cutoff Exceeded During a Trnnsient ~ ' Technical Specification 3.5.2.5d(2) requires xenon reactivity to be asytptotically approaching equilibrium at steady-state rated power prior to increasing reactor power above 82.5%. Contrary'to'the above, on Septe=ber 10, 1974, reactor power increased abcvc 82.5% in response to the opening of two turbine bypass valvec.
- i Duke Power Company reported the above violation in Abnormal Occurrence Report No. A0 270/74-11, dated September 24, 1974.
II.
Licensee Acticn on Previously Identified Enforcerent ihtters A.
Violations i
Technical Specification 6.1.2.2.i(2) previously required the Nuclear Safety Revie.r Committcc, USRC, to review and l ~.
audit proposed changes that may involve en unreviewed safety question.
The Technical Specification has been changed, on July 19, 1974, to require the NSRC to review those changes that constitute an unreviewed safety question as determined by the Superintendent.
(DPC letter to ! Region II, dated August 8, 1974).
Itco is resolved.
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. 2.
A radioactive shiptent containing byproduct n:terial was imprcperly transferred to a cocpany who was not authorized
to receive the material.
On July 12, 1974, DPC has revised , their procedure, HP/0/B/1005/01, " Procedure for Shipment
and Receipt of Radiosceive Material," t a require confirmation that the receiver has a proper license-to accept the chipment.
Letter to Re3 on. II is dated August 8,1974). - Iten is reco1ved.
9 3.
Tachnical Specification G.6.2 1.A requires a written report ' to be sub=itted to the connissien concerning radioactivity ' in the component cooling system.
A' report was submitted . by DPC to RO:II on July. 10, 1974, and supplecentary inferration was submitted on August 28, 1974, Item is reco1ved.
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Safety Items _- a
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. . . ., . . R0 Rpt. No.-50-270/74-7-4-i ^s _ . III.
Uew Unrecolved Items
' 74-7/1 Corpletion of Power Ascensien Testir; , t
Licensee has not established a schedule for completing the power ascensien test program.
(Details II, paragraph 4) 74-7/2 Activity in the Component Cooling System i Measures to determine the source of radioactivity in the cooper.cnt cooling system are scheduled to be perforced during
the Oconee 1 refueling octage.
(Details I, paragraph 6) , ! 74-7/3' Hotwell Level Control and Emergency Fcedwater Systen Failures On September 17, 1974, after a reactor trip, the~feedwater control, hotwell level control and c=crsency feedwater system > experienced equip ent failures.
The reportability of the incident has not been deternined.
(Details II, paragraph 2) i 74-7/4 LPI Valve Failure . -' . Corrective teacures to_ prevent recurrence have not been fully
icplcnonted.
Licencee is considering replacement of these
valves with a throttle valva of a different design. '(Details I, l - paragraph 5) . IV.
Status of Previously Recorted Unresolved Items
4 74-4/1 Overpressuriention of CF Tank 2A Corrective ceasures to prevent recurrence have been verified.
A telephone was installed on August 19, 1974,'to permit co==unication_between the operator in the Centrol Roca and the core ficed fill valve location.
(DPC AO Report 270/74-5, dated June 3, 1974).
Item is closed.
74-4/2 Underprescurication of CF Tank 2B ' Corrective-=easures to prevent recurrence have been completed.
' This' incident,has been discussed with'all station operating personnel.
(DPC A0 Report 270/74-6,. dated June 4, 1974).
q . Iten is closed.
j-74-4/3 4 Vital nus. Inverter Shunt Trip _n ' i } Removal of the shunt' trip on.the vital AC bus. sts '.ic inverters I has been completed., (Letter' report:to RO:I! frc= DPC, dated April:17, 1974). _ Item is' closed. '(Details I..parngrcph 3)
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.____ -. -. ...- .- .. -. - -... . .. . '3 R0 Rpt. No. 50-270/74-7-5- - . 74-3/1 Terporary Station Modificctiens_ s The administrctive procedure fer processing temporary station modifications was issued July 1, 1974.
Item is closed.
74-3/2 HP-31 Racet Interlock Licensee has completed revicu of this ite= and incpector had no further questiens.
Iten is closed.
73-9/1 Body Wall Thickness of Valvea 2-51-24i and 2-51-243 datad The Oconce Valve Vall Thickness "erificatien Report, June 3, 1974, has becn revieued and all questiens have been resolved.
Iten is closed.
(Details I, paragraph 4) . V.
Unusual Occurrences A.
AO' 270/74-7, "Licuid 1:aste D'nnesal Vr.lve Failure. 2L5?D-1" ES valve 2L*4D-1 f ailed resulting in flow blechtge f:cn the reactor building surp to the sucp pumps.
The abner =cl occurrence report, dated June 25, 1974, was reviewed during this inc;cction.
j T. ten is closed.
.D.
A0 270/74-S, "Exceedine Powar !cvel Cutoff" , i Licensee failed to estchlich renen ecuilibruiu prior to increasing ' reactor pcuer above the power Icvel specified in Techni:al Cpecificatien 3.5.2.5d(2).
L?C's abnormal eccurrence repert, dated June 23, 1974, was reviewed during this inspection.
Ita= is closed.
A0 270/74-9. " Failure to Provide R2dundant Ecric Acid Sources" C.
A leaking valve diluted the strength of the concentrated beric acid in the storage tank to less than that required by Technical Specification 3.2.2.
Corrective mecsures ns described in DPC's chnorcal cccurrence report, dated July 29, 1974, vere reviewed.
The licensee commenced reactor shutdcwn at apprc:citately 25. per hour upcn er.ceeding tha limiting conditica for operaticn, ICO.
The questien regarding preper chutdown rate vhen a limiting ccndition for operation is exceeded was diccussed with licensec An intrastation letter, dated October 2, 1974, was tanagement.
iccued to ectchlich a shutdcwn rate cf not less than 10% per hour whenever a LCO is eneceded.
Itca is clcsed.
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A0 270/74-10, " Failure of Reactor Euilding Tan Motor Starter"
A fault in the Reactor Building Cooling Unit 2A fan notor starter resulted in tripping the supply breaher :: Motor Control Center 2XSl.
Iten was reported by DPC and Abnormal Occurrence Report No. 270/74-10,-dated August 23, 1974, has bacn revicued.
Corrective measures to prevent recurrence have been implecented.
Ite= is c1csed.
~ . A0 270/74-11, " Power Level Cutofft, Exceeded Durine A Transient" E.
! Two turbine bypass valves failed open, while the reactor was ' operating at 80%, which placed a de and on the centrol syste. Reactor power increased to approninntely 83% thereby eneceding the technical specificatica requirement to establish-xenen , equilibruin befera increasing abcve 32.5% pcvar.
The failed components in the control systen were replaced and the syste= ' was tested to verify correct operation.
Iten is closed.
. T UE 270/74-2, " Radiation Moniter Inocerable Durine neacter Buil_dir.; ' Purge" i,. A reacter b111 ding purge was conducted with the radiation coniter
in calibrate position rather than in operate position.
Ita= vas ] reported by DPC and the correctiva actica to prevent recurrence J.
- vac verified by the inspector.
Item is closed.
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UE 270/74-3. "Missine Guide Pin fren Valve 2L?-12"
l The internal guide pin frca a valve in the lou pressure injection lina failed, preventing preper closura ef the valve.
The broken piece has not been recovered and is >2lieved-to be ccatained in ', the systen piping.
The progran to conitor for failed fuel pins and to detect nevenent of the part with the loose par:s ' conitor was verified.
Licences is censidering replace 2nt of the valve uith a thrcttle valve of a different design.
Replace-
cent date has not been established.
(Datails I,' paragraph 5) G VII.
Other Sitnificent Findings J ", None ., VIII.
Manaconent Interview A canagement interview was held on October 4,1974, with the following in atrendance: . ~., % . . . ---44 m w e wm.e-4p' ..ae 4.m.4.saww w
.. , , . i t I R0 Ept. No. 50-270/74-7-7- ' ' ,- Duke Power Co.pany m J. 2. Smith - Statien Manager J. W. liampton - Administration Services 0. S. P,radhan - Superintendent of Maintenance L. E. Schmid - Superintendent of Operations R. M. Koehler - Superintendent of Technical Services T. S. Barr - Technical Services Engineer , J. W. Cox - QA Engineer The items of violations, listed in Section I of the Sutmary, were discussed.
The status of previously identified enforcement natters, described in Section II of the Su==ary, were discussed.
The nc~ unresolved itens in Section III of the Sunnary were discussed.
(Details I, paragraphs 5 and 5, Details II, paragraph 4 and Dateils III, paragr4ph 2) - The status of previously identified unresolved itens uns discusced.
The inspector stated that cil of these items ::cre censidered resolved.
(Catails I, paragraphs 3, 4 rnd Section IV of Serrary) The inepector stated that responses to R03's 74-3, 74-6, 74-8 and 74-9 have been verified and there are no questions regarding these items.
(Detail I, paragraph 7) The unusual occurrences, described in Secticn V of the su nary, tare discusced.
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- 4. . . ,~) R0 Rpt. No. 50-270/74-7 I-1 ..- L -{ - /0 -a/- 7 /td % b-cc. c( DCTAILS'I Prepared bv.
Date F.' Jape, Reactor Ine;.pector ' Facilities Section racilities Test and Startup Branch Dates of Inspection:,0ctober 1-4, 1974 J[' f
G * /v rbt /..V /o-3I-71 Reviewed by: R. C. Lewis, Senior (nspector /,! Date , racilities Section V Facilities Test and Startup Eranch .I.
Individuals Contacted Duhe Pcwer Cc:pany (DFC) E. Bollinger - General Fercien Construction Electrician J. Nin - Electrician E Ada s - Instru:ent and Contrel Engineer R. Knoerr - Assistant Plant Engineer L. E. Schedd - Superintendent of Operations W. M. McClain - Shif t Supervisor M. A. Susinno - Junior Engineer W. A. Brewn - Staff Chemist D. C. Smith - Chemist R. L. Wilson - Ferforcance Engineer T. S. Barr - Techrical Services Engineer ! A. R. Tranklin - Junior Enginee: O. S. Bradhan - Superintendent of Maintenance J. Davis - Planning Engineer 2.
General
This inspection was conducted to review results of power ascensien tart-ing, follow-uo of previously repcrted violaticus and unresolved irmas, and conduct a review of selected cbncr:al cccurrences.
3.
Vital Eus Inverter Shunt Tri, 1.
Follow-up on a previously identified prcblem 1/ regarding the AC vital - bus static inverters was conpleted during this inspection.
Modifica icn 1./ See RO In'spection Report ';o. 50-270/7?,, Detalla I, parcgraph, - .
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EO Kpt. So, 50-270/74-7-2- . ' .s , 17, 1974.
. 0-223-D, " Shunt Trip Device Renoval," was cocpleted on September The nodification record; for this change were examined by the inspector and were found to be in agree:ent with Administrative Procedure 10, . "Muclear Station "odificctions," dated June 20, 1974.
This previously identified unresolved ite=, 74-4/3, is now closed.
f 4.
Body Wall Thickness of Valvas 2-51-244 and 2-51-24 5 - The engineering evaluations and ueld repair documentation of the 4 inch Velan check valves (2-51-244 and 2-51-245), contained in the licensse's i ! report en reactor coolant systen pressure boundary valves tinitun wall i thichucss, dated November 22, 1973.
The inspecter cetzented that the The did not state whether the repairs were tajor or minor.
report licensee's representative responded by staring that the repcirs uere l ninor and the report ueuld be revised to include cn engineering ~ { evaluation supporting this finding.
r Supplement 1 to the report <bted July 19, 1974, states that the repairs were minor and the applicable codes d31.7 cid 316.5 does.- require additicnal hydr static testing after repair.
The suppletant also j citrasonic test and liquid penetrant examination confirred stated that the integrity cnd accepta'aility o f the weld r: pairs. The incpector Ltd no further questions and unresolved iten 73-S/l is closed.
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Missinn Guid: Pin fren 2LP-12 . I The. guide pin from the internals of Icu pressure injection valve, 2LP-12, uns discovered nissing on June 30, 1974.
Th2 licensee's r2 port this shcuid en this incident was reviewed and the inspector stated that , have been reported as an abnormal cccurrence rather than as an unusual
' Correcti-e acticas taken by the licensea were exanined by the . cycnt.
inspector.
These are surnarized below.
OP 1104/05. "Epw Pressure In ection systen" s a.
The procedure for operating the icw pressure injection syste us been revised on June 7,1974, to include a step to encura flos rate ' - of at least 3C00 gpn thrcugh 2LP-12.
The purpose of this specificc-tion is to mininire ficw induced vibration which is believed to be e the tajor cause of the failure.
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Leone Parts "anitoring . . \\ The loose parts monitor is in service at all tites the systcn is i set up to alarn at specified noise levels. The system is naintained in service with IP 2C0/31, "Locse Parts Manitor Calibration."
. . , Since the valve f ailure, no unusual noises have been detected.
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.. . . . . 'N R0 Rpt. No. 50-270/74-7-3-Reactor Coolant Monitoring for Fuel Clad Failure c.
radienuclide leakage f rca fuel pins A conitsring nrogram to detect since the power to the reactor cociant systen has been in ef fect Reactor coolant sanples are anclyzed escalaticn progran began.
To date fuel perfornance by daiP, to uansure fuel per fornance.I-133 ratios indicates that.no failed fue use of the I-131 to - e:<is t in Occace 2.
, The total activity of the reactor coolant has also been fol] owed during the power, escalation progran using scintillatien techniques Results of these deta and gross garna teasuretent en a daily basis.
indicate no f ailed fuel pins.
The inspector had no questions regarding the =cnitoring progran establish Replacement to datect movecent of the loose part and fuel clad failure.
is being considered by the licensee te of this valve, and others like it, Procu-erent data and replacerant schedule is current prevent recurrence. This ma*ter is being carried as an unresolved item being establiched.
pending replacenent.
6.
Activity in the Comoonent Couling System The licensee's response on this previously reported viclation 1! has been verified and the violation is considared closed.
A procedure, T? 240/09, "RCP Thernal Barrier Hydrostatic Test," has This test is schedul-been prepared and is currently being revicued.
ed to be conducted during the Oconee 1 refueling outage to deternine the scurce of the activity.
Also during the refueling outage, 1solaticn Modification 0-262-5, "CC Drain Tank Pump Discharge Heade This Valve and Telltale Vcive," is scheduled to be installed.
modification will also assist in deternining the source of the radio-Basically thic change enables isolatica of the cec;cnent activity.
There is sora evidence th: cooling systen fren the rad;aste systen.
inoicates activity in the ec=penent ecoling syctem any be due to a leak f rom the liquid waste disposal header.
. Since the work on this problem has not yet been completed, this iten vill be carried as unresolved item 74-7/2 pending follow-up of the --11 See RO Inspection Report No. 50-270/74-4, Detailc I, paragraph 3.
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The inspector had no further questions on the planned e program to resolve this tatter.
7.
Regulatory Operations Bulletins The licensee's response to the follovng E03's has been reviewed by the inspector: a.
R03 74-3, " Failure of Structural er Seismic Support Bolts on Class I Co cencats" DPC's response, dated April 16, 1974, stated that a procedure would be proposed and a Unit 2 inspection veuld be accorplished prior to startup uhfch was scheduled for April 21, 1974.
The inspector verified that these ccer.itzents wera net.
IT 14C0/67, "Reacter Vessel, Steam Generator, and Pressurizer Structural Supports and/or Folt Inspection," was issued en April 19, 1974.
The inspectica en Ocenee 2 tas conpleted en April 19, 1974, and May 8, 1974, and all structural supports e.nd bolts were declar-ed acceptable en May 9,1974.
b.
R03 74-6. " Defective Westinchoose Type W-2 Control Switch Ccrpenant" In response to RGB 74-6, tha licensee has reported that no Uesting-house W-2 type control svitches are utiliced at Oconee.
DPC response is dated June 28, 1974, and the inspector had no questic on this natter.
RGB 74-8, "Deficienev in 1TE Molded Ccse Circuit Breakers. T cre HE-3, c.
- -- z In rasponse to RC3 74-6, the licensee has reported that there are no : ITE Molded Case Circuit 3reakers, Type EE-3, utiliced in the safety systers at Occnee Nuclear sectien.
The licensee's response is dated August 19, 1974.
The inspector had no questicas on this natter.
d.
R03 74-9. " Deficiency' in General EI cetric '5 del 4KV Ma ?ne-Elast Circuit Dreakers" In respcase to RO3 74-9, the licensee has reported that there are no General Electric Model 4KV lhgne-Elast circuit breakers in the ! ' - Oconce Nuclear station safety systems.
Ihe-licersee's recponse is dated Septamber 5,1974, and the in-spector had no questions en this r.etter.
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'. .. . . ' n Q RO Rpt. No. 50-270/74-7 11-1 '/ e <' 71 sf -, - 2., '- DETAILS II Prepared by: /( . / m ~_14! - ' Date R. F. Rogers, LII, Reactor Inspector Facilitics Section . Facilities Test and Startup Eranch Dates of Inspection: O c t obe r 1-4, 3 9 7 '. N ' 'O '? 4 . ,( / - -- w 74- .A' Reviewed by: Date _R. C. Lcuis, Senior Reacter y Inspecter, Facilities Section Facilitics Test and Startup Branch . . 1.
Persennel Contacte_d Duke Pcrer Ccupp.nv (DPC) J. E. Snith - Plant Manager R. M. Koehler - Supervisor of Technical Support R. II. Wilsca - Perf crnance En;;ineer T. S. Barr - Technical Services Engineer ... , . .. , 2.
Review of Test Data The inspector reviewed the results of six power ascension test proce-dures and the following discrepencies were noted: TP /2/A/200/31 - Pseude Control Rod Ej 2ctirn Test a.
filled Enclesure 13.3 reactimeter los and calibraticn sheet was net Pre-anplifier, range, and dia;;nostics calibrations are required in.
The leg sheet is required to ha ecmpleted per stap in step G.6.
The calibration of the reactimeter cannot be varified in 12.5.
this test.
TP/2/A/EO/24 - Pcuer Inhalance Detector Cerrelatien b.
Steps 12.2.3.9 thrcugh 12.2.3.14 were not completed.
A icg entry indicates that this was because cf a xenon oscilla:ica.
A revisian (i!6) to relax the test requirements was submitted cc Septenber 30, 1974.
This revisicn mcdifies the procedure to reflect what was actually done en June 8, 1974.
The station review ccnnittce; had not yet reviewed this change.
TP/2/A/800/24 - Pcuer 1 balanc.e Detector Correlation c.
Enc'asure 13.6 test flew and stenary sheet does not indicate whether acceptance criteria nas been act for 12 of the 13 steps l
listed.
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- R0 Rpt. No. 50-270/74-7 II-2 'h l d.
TP/2/A/300/24 - Pouer Imbalance Detector Correlation Enclosure 13.8 critical CLA anc bcron concentration ucrksheet (2 pages) was not filled in, TP/2/A/800/23A - Centrolline Procedure For Re-escalatica Ta c.
7 51 Full Po.;e r Revision 03 dated January 21, 19 74, e as issued chich required addition to section 11.3 of the precedure a requirement to obtain the station superintendent's peraissien prior to escalatica to 40 pcwer to assure that proper attentica has been given to test r2sults.
This revisica.as not entered in tie procedure.
i. Additienal uinor administrative errors existed in the tests in the form of enclosures which were not filled in properly or ' completely during test performance. Administrative controls .such as in-prcgress QA audits did not identify many of these discrepencies.
Station test coordinators final revieu of , , , ccapleted precadures was..ct eff ective in correcting these itens , . .- . .. , or timely in nature.
-.. Summary - Items a through f are discrepencies in variance with 10 CFR 50, Appendix B, Criteria XI, as inplccented by applicable pertions of DPC Administrative Policy Manual (APM) articles 3. 2.1.7, "Docucentation ;" 4.1. 3. 3. " Test Coordinator ;" 4.1.5.1 Iest Procedure Revisions ;" and 4.1. 7. 2, " Test Coordinator Veri-fication of Test Cenpletion."
lteas a through e collectively are the subject of a violation.
3.
Pcuer Level Plateau Data Review Verification that the test results for the 0%, 15%, 40% and 75; plnteaus were evaluated by the licensee and that they were datermined to be acceptable prior to proceeding to the next plateau was perfer :d.
S tation review ccanittee revieu cf each plateau was satisf ac to rily documented.
4. _ Status of Power Ascension Testina A revicu of the status of power ascension testin; for this uait indicates that six tests have not been perferred.
The administrative review of ccapleted tests has not bee timely as required by DPC Administrative Policy M r.ual articl e 3. 2.1. 5.
Only one completed
test has been approved by the plant nanapur.
A schedule for ccmpletion of remaining tests has not been preculgated at the staticn.
The status of perfor ance and revicw of the power ascension test program will retain an unresolved iten.
A schedule fer ec.,latica has been requested.
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. P . , ~') R0 Ept. No. 50-270/74-7 III-1 . - DETAILS III Prepared Ey: .h 'b /O~ / ' Date T. N. Epps, ReactercIncpector Facilities Operatiens Branch Dates of Inspection: Cetober 3-4, 1974 e w v q~.+m /0e4, 7 hci . . e n 9.. _ _ _ _ _ _ _ - Rcviewed ':f A Date // F. J. ?cag, Chici) Fccilitias C erations Branch
1.
Individuals Contact _ed Duke Pouer Conran" (DPC) J. E. Smith - Plant Superintendent L. E. Schmid - Operating Ensincer T. S. Barr - Technical Services Engineer 0. S. Eradham - Ihintenance and Instru:ent Ensiacer 2.
Records of Operations _-: :.. .., - .. ,, - - , - The inspector reviewed the L' nit 2 centrol rcou log sheets, Ic; book, and the shift supervisor's log beck for the period fre Septe:Ser 16, 1974 through October 2, 1974.
An entry in the control roca ic; book for September 17, 1974, in-dicated that a turbiac trap occurred at 8:42 p.m. and resulted in At a reactor trip fren high reactor ecolant system pressure.
S:47 p.n. feeding the ste:n generators uith the Unit 3 energency feed pump was 'cegun.
Further review including diccussions with site perscnnal shewed that several talfuncticns occurred during Theca included failurc cf the rain feeducter derend this transient.
to reintain to run bach, failure of the hetwell level centrol sycte: hotuell level, and f ailure of the startup valva (FD':-35 "A") and energency block valve (FD'<!-33 "A") in the crergency feeduater line to open after being closed corentarily.
The licensec was in the process of preparing an incident report en , this cutj ect.
The inspector stated to the licensee that this iton would be carried as nn unresolved item pending the inspector's revicw of the incident report.
The inspector had no ce==cnts en other items reviewed during this inspection.
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