ML19221A063

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Telefaxed Items Re Plant Status from 790406-10
ML19221A063
Person / Time
Site: Crane Constellation icon.png
Issue date: 04/10/1979
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To:
References
NUDOCS 7905190052
Download: ML19221A063 (37)
v • d • e


Text

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NUCLFAR REGULATORY CCFF.ISSION CLTS's'uFlIWICE: CFFICE OF INSPECTION AliD E."FORCEMENT 'n'ASHINGTON, D. C 20555 URGENT D'." E D I AT E ASAP FACSIMILE SERVICE REQUEST DATE: f/ / # I/ A)26 MESSAGE TO: 8/1Y 00 4) /7t/d[ SS h / (Name) // (Office / Division - Agency /Ccmpan9T STATE AND CITY: TELECO?Y NUMBER: AUTO: YES NO (Rapifax - 50 secs./page) (3-M. - 4 Mins /EMins ) (Xerox - 4 Mins /6 Mins OT'.iE R : (Transmission Mcde: Mins VERIFICATION NUMBER: /f EXCLUDING COVER SHEET RETURN COPIES - YES NO. OF PAGES nu PESSAGE FRCM: _f _fy P % vf _"L ( ime) / (Uf fice/ Divi sion - Agency / Ccepany) EU!LDING: EAST WEST TOWERS _ 0FFICE FHONE _ TELECCPY NL'MBEP.: 301 492-5137 - PAPIFAX - ~.UTCMATIC Tdi M 2-7255 - 3M VRC AUT'"ATIC 301 492-7264, - XEROX (:C01) - M'<'iUAL VERIFICATION NUP.3ER: 301.:92-792_3_ - (S ethe sda, l'.0) ?.aceived/ Time -Date Tr.....i tte d/ Ti.c.e Ca te 127 019

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$31 P An K A v t '. u t S */- N,, ,p .u c c r e n u s s i a, e s *. e.s < tv A N I A 19406 g,.... November 1,1978 McMORANDUM FOR: Nerman C. Meseley, Directcc, Divisico of %cter Operatiens Inspection, IE FROM: Ecyce H. Grier, Directer, Regico I SU3)ECT: LICENSEE PEUCRMANCE EVALUATION In respense to your telephene request cf Icst Friday, I am ferwcrding the enc!csed inicrmcrion relative to licensee performance at Ccivert Cliffs, Three Mile Island, Salem cnd Cyster Creek. My memcrendum of December 13,1977 to H. D. Thernburg en this subject contains informaticn relative to incico Point, Pecch 3cticm cnc Mi!! stone. If ycu have cdditienc! questions en this mcrier, please Ier me know. I would like to tcke this opccrtunity to reiterate my pesifico thc! ct this time, in the cbscoce of apecific criteric for "ncrmc! pericrmcnce", Region I hus no operating reacter licensee that I consider to hcVe cn overcl! pericrmance that is either chnermal er ci unusual safety concern. I believe the Region ! sicif wculd suppcci me in that F C'. iticn. This is not to scy that there have not been occasiens when a licensee has ex libited chnermcl pericrmance in a porticular crec. For excmple, we hcvc just recently impcsed a civil pencity ct Ginna far chnermal perictmence in the radicticn prciccrien crec yet the cvercil perictmence at Ginnc is generclly considered to ha goed. Other similar examples ceutd be cited. Identifying crecs cf cbncemel pericrmance by licensees and tcking ccticn to bring such pericemcnce heck to the norm is our regulcr icb. If we do cur ich prep 2rly, we shculd evcid recchiry c sitection in which a licensee's overcll perfcrmance k.cs beccme cbccrmal. w/., L n .;Wn, mn,J cEH. Criar C-ay/d f or Enc!csurc: Dir As s!cted TrtANSMIIIED VIA FACSIMILE - 11/if73 127 022 =

LICENSEE PERFOR"ANCE EVALUATION OUESTICN - CALVERT CLIFFS 1 & 2 Frca the data evaluated, Calvert Cliffs facilities appeared to exhibit performance which deviates frca the norm. Provide ycur analysis as to why the perfonnance of each Calvert Cliff's plant appears to stand apart frem other facilitie< Recent experience indicates that these facilities are above averace pe rfo rmers. These plants operate with nore stringent recorting requirements, a fcrty-four percent reduction in LER's during the past year, a belcw average number of items of noncompliance, and a high plant availacility factor. LICENSEE PERFORMANCE EVALUATION CUESTICN - THREE MILE ISLAND 1 Frcm the data evaluated, Three Mile Island appears to exhibit perforrance which deviates f rcn the ncrm. Provide ycur analysis as to why the performance of Three Mile Island appears to stand acart from other facilities. The plant staff was supplemented and changes occurred in advance of the licensing of Unit 2, to preclude the dilution of management attentien to the coerating uni t. The operating history of Unit I to date does not indicate any particular dif ficulties which could be attributed to inadequate management control during the plant's corstruction. Licensee perfcnnance is considered to be above average. _ LICENSEE PERFORPa.NCE EVALUATION CUE 5 TION - SALEM 1 Do jeu bei; eve that the Salem 1 facility has an aincrmal cerformance cccord? 'o. This licensee is one of the neuer R2gian I licensees and is censid+r d to be an average performer. No particular cperati.ig dirficulties have been experienced due to plant control ruta design or operator canicois. EquipTent necblems experienced during starSp are considared to be J.c r:3l eVOIuti0ns. 127 023

TMI 1 SIGNIFICANT PAST PRC3LEMS 1. Enforcement Past problens have been identified in the areas of radiation pro-tection and physical protection. Radiation protection probler.s were primarily related to identification and administrative centrol of radiation /high radiation arcas. The most noncompliances occurred in 1977 (ten infractions /cne deficiency) and general improvement has since been noted in this area. Physical protection inadequacies resulted in civil penal tiu3 ceing issued in 1974 and in early 1976. An additional noncampliance was fcund in June 1976 in the area of physical protection, which resulted in a management meeting. In 1977 only one infraction was identified regarding TMI 1 physical protection. No noncompliances were found in 1978 'or either unit concerning physical protecticn. Noncompliance in other areas has been scattered throughout varicus areas, and does not appear indicative of major specific or generic probleas. 2. Ge n e ra_l, The licensee had no riajor probic,ns identified during pre-opera-tional testing or first two years of facility operation. TMI 1 had a relatively problem-free transition frca time of fuel load thrcugh completion of pcaer ascension testing. Capacity f actor has since been above average. During recent refueling cut: e, the scheduled outage time was celayed about one week due to problems encountered with the fuel tr.tnsfer carriage and main rcfueling hrdge nely in the putage, and 3WST dome failure found late in the cutcge. 127 024

2 TMI 2 SIGNIFICANT PAST PRC3LE4S 1. Enforconent Noncompliance has generally been scattered throughout various areas, and has not been indicative of significant specific or generic prcSlems. 2. General No significant prnblems occurred during preoperatic. cl testing, however, the follcwing substantial delays occurred s. ring startup testing. ECCr Actuation on 3/29/78 (LER 78-22/99X) About 2 week delay due injection of NaOH ECCS Actuation on 4/23/78 (LER 78-32/99X) (Also LERs 78-33/li, 78-34/lT) Criginally installed (first of a kind) Main Steam safety valves failed to properly rescat af ter lif ting, which led to rapid seconJary/ primary systen cooldown and this ECCS actuation. Corrective action for event included a 5 nonth outage for design change and replacement of the Main Steam safety valves. Atmospheric dump valves bellows rupture on 1/15/79. Tao week delay due replacement of bellows. 127 025

f 3 Dates subject /cc nnent IAL's 1. 77-07 9/1/77 Inspections /Acticns Concerning Decay !!aat Renoval Punps Enforcement Meetinos 1. 76-13 6/16/76 Security and Security Plan fianagement Meetinos (fiot SSIP)

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79-C4 2/9/79 "edule 30700 2. 75-03 1/14/75 Module 30700 3. No " umber 3/5/74 Environmental Consideraticos Civil Penalties 1. 74-30 9/10-12/74 $4,000. - !nspector entry through security gate 2. 76-02 1/28, 2/5-6/76 510,000. - Unauthorized entry C2.Lin:d am c nt ;.c :-ting 50-239/79-04 (1ll 1) cad C0.>^0/,:9-05 (iill 2). All ;t5cr i tuas listed ata /c

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'q' J.T~ l3 GA Rh SI #[ Letter from E. F. Dowling to E. A. Womack dated Ape;g 7* 1979 subject Inst rumentation Status e,,[* I. L Cencral observation of instrument status eb5 X' 1. Flow, level and pressure transmitters ere expected to fail at ".*. -.,.I _ some point due to two mechanisms. (a) high radiation or (b) submersion in water 3 2. Radiation levels (estimated at 10 rad /hr) should start to effect BY transmitters some time after 1200 hours on 4/1/79 (integrated dose 105 rad.) Degradationshouldbegradualwithtime, until the integrated 6 6 dose reaches 10 to 10 rads (10 is to + 41.7 days: 10 equal to + 417 days) at which time the transmitter will cease to function. 3. Calculation of water level in the Reactor Building indicates that a large number of transmitters are submerged and have been for a number of days. Few f ailures have been reported. The transmitters are sealed and have been qualified by tests to high temperature, pressure and steam conditions (286 F, 60 psig), but have not been tested for submersion in water. There is no way to predict how lo g the submerged transmitters will continue to function. 4. Transmitter failure is expected to be by increase in noise level, gross deviation from redundant indications and finally loss of signal. shows which transwitters are vulnerable due to location above building floor and by virtue of radiation resistance. Attachment 2 defines alternative ways to obtain parameter measurements. This attachment will be updated when additional information is available. Attachment'l \\ I \\ i27 030 4

1 t 105 Rads Level (Water Volume) ' SY (Bldg Elevation) Transmitter 107 Rads 99?' 6" String No., Parameter, Foxboro 2'-3 179,630 gal. V/ SP6B-PTl SGB Pressure 3'-0" 222,990 RC14A-DPT-3 & 4, Loop A RC Flow 3'-6" 260,155 RCl-LT 1,2 & 3, Press. L/' S P6B-PT 2 SGB Pressure Level RC14A-DPT 1 & 2,. Loop A RC 22 - PT 1 thru 8 RQ_ Flow Reactor Coolant Pump Seal Cavity Pressure RCl4B-DPT 3 & 4, Loop B RC Flow Note: This group may be located at this SPlA-LT 2 & 3, SG A Operate icvel or the next level Level higher SPlA-LT 4 & 5, SGA Start up Level SPlB-LT 1, SGB Full Range Level SPIB-LT 2 & 3, SGB operate Level SPIB-LT 4 & 5, SGB Startup Level 5'-2" 384,038 SPlA-LT1, SGA Full Range SP6A-PT 1 & 2 Level SG-A Pressure r RC3A-PT 3 & 4 j RC Pressure Wide Range RC3A-PT 5 RC Pressure Low Range f RC3B-PT 3 RC Pressure Wide Range Assumption: 3 1) HY transmitter will begin to fail about 10 Rad. ~ 2) Foxboro transmitter will begin to fail above 107 m 3) Transmitters have been receiving 1000 R/hr. 4) Both BY and Foxboro transmitters may fail if submerged in water. 5) Water height is related to volume by 1 ft. per 74,330 gallons, j 127 031 r

At t ac hme n t 2 Measurement Alternative Primary Source Alternate Source Reference Backup Parameter of Measurement or Measurement Sheet RC Pressure RC3A-Pr 3&4 RC22-PT 1 thru 8 Note: Temperature (Wide) ESFAS vs saturation pressu-RCP Seal Cavity via steam tables RC33-PT 4 Pressure (wide) ESF/.S RC2-TA 1&2 Pressurizer Temp. CA-PI Pressurizer steam o water sample pressu RC Pump Vibration RC3A-PT 5 (low) RC Pressure less tha-500 RC Temperature InccY'e T/Cs RC4A-TE 2&3, THot RC4B-TE 2&3, THot RCSA-TE 2&4, TCold RCSB-TE 2&4, TCold RC-TE9 RC4A-TE 1&4, TH RC4B-TE 1&4, TH RCSA-TE 163, TC RCSB-TE 1&3, TC i RCISA-TEl, TH RCISB-TEl, TH RC15A-TE2, TC RC15B+TE2, TC RC15A-TE3, TC RC15B-TE3, TC RC-TEll MU-TES Accounting for Coola 127 032

- Primary Source Alternate Source Reference Backup Parameter of Measurement _ of Measurement _ Sheet DH6-TE 162 SP3A-TE 1&2 Steam Gen. Saturatic Temperature AP3B-TE 162 Steam Gen. Saturatic Temperature RC Flow Loop A RC14A RC Pump Motor DPr 1,2,3 & 4 Current RC Flow Loop B RC14B RC Pump Motor DYI 1,2,3 & 4 Current SG Operating SPlA-LT 2&3 SG-A SPlA-LT 1 SG-A Level SP1B-LT 2&3 SG-B SPIB-LT 1 SG-B RC Temperature See RC Temp. Sheet SPl A-I.T 4&S SG-A SPlB-LT 4&S SG-B Feed Water Status S ..,le Lines as Ltvel Indicators Press. Transmitter Across Feed Water Line and Main Steam Line SP3A-TE 162 SG-A Use one element as heating element by applying low volta; Other clement will read different if element is covered uncovered. SP3B-TE 1&2 SG ', 127 033

3-Alternate Source Reference Backup Primary Source of Measurement of Measurement Sheet Parameter SG Wide Range SP1B-LTl SG-B Serple line as . eve; indication Level SPIA-LTl SG-A Pressurizer RCl-LT1,263 MU14-LT 1&2 (MU Tank Level) Level MU?-DPT 1,2,3,4 (Seal injection MU4-DFT (Let-devn flow) Pressurizer Level Alter-nate Calcula-tion Procedure c Proc ed u_re : w at incurements using MU4-DPI Step 1 - Record let-down flo Step 2 - Record RC pump seal injection flow at increments using MU7-DPI 1,2,3 & 4 Step 3 - Record MU tank level at increment using MUl4-LT 1&2 Step 4 - MU tank volume is 4388 gallons. MU tank galls per inch - 31. Fressurizer volume 11,230 gallons. Pressuriser gallone Per inch - 24. Steo 5 - Determine volume of let-down. ment = volume in gallons. Item 1 x time incre Step 6 - Determiner volume of RC pump injection. ment Item 2 x time incre Step 7 - Subtract result of Step 6 from result of Step 5. Step 8 - Subtract previous MU tank level from level determined at Step 3. 127 034

TO: SIG DISTRIBUTION B&W - Trailer #26 April 10, 1979 Bob Long - Trailer #26- /A b Ivan Porter - Met-Ed Op.

  1. 8[77 N00 Vic Stello - (f4RC

) (Trailer #7) riilt Levenson - Bldg. #26 Cable Spreading Room htY G Ackermann - Bldg. #26 ? Attached is a status report by the Special Instrument Group on diagnostic i ns trumenta tion. Report will be updated daily. x\\ N\\ ( R. BALL RB:dr b ,o 4 ~ 127 035 ~~

ige 1 SPECIAL INST,iUMENT GROUP - STATUS REPORT Date 9 April AB Time 2030 0 nstrument Type Primary Function Who is Location & Type Vital Signs Prior Action New e or Class in Recovery Using of Indication of Health Results Action Person amputer Backup TC readings Control Room Continued 1)CableAvailE Lionel opera tion able

2) Hookup Banda Put on 2 multi-point
3) Spare core Ken Schroe-.

der ( Core Determine core Core evalu-Safety cabinets D.C. current

1) Techs can now 1)Howoften R. M.

Stectors relocation ation Resistance do does Tech Ball . l (greaterthan group want? 20 meg)

2) A test proce-Ask Milt
f.

dure was written (Z98A) ~ 3% down

counters Neutron indicator Control Room Recorder on one at Value and Discriminator &

Ask shift to Acker-3 a time fluctuations gain checked record both mann Sub-criticality (plateau) BF 5 3 40 c/s = 1 nv Th N CD V A

Pa RMge2 SPECIAL INSTRUMENT GROUP - STATUS REPORT Date 9 April Time 2030 Instrument Type Primary Function Who is Location & Type Vital Signs Prior Action New [ or Class in Recovery Using of Indication of. Health Resul ts Action Pei SPND Indicate lower part Core evalu-Computer printout Resistance great -Arkansas P&L Reytew by HDW Ack g (Sel f-powered of core is whole ation er than 10 on (Jim Poale) is of TDR mar. neutron detectors ) good ones brinoing in TDR Will do TC's then SPND's TC's Core top temperaturc Core Eval. Two on strip charts Resistance con-

1) Duke is tak-
1) Compare Duke (Thermocouples)

Redistribution Opera tors in S.R. tinuity and ing some TC & TMI for Control Room reasonable value resistance l ow.resis tan :e computer printout

2) Have, resistors 2) Ackermann from computer will show terminals and Milt to ground i
3) What did TC'
3) 7F & 8F both do as a noisy function of pressure Movable incore Core integrity Core Eval.

Spreading Room Motion Went 3 ft. into (S.R.) core in location N-8 (3 ft. into fuel) Solid stop Practically no rs; change in current-sa detector appears wet and dead c3 u sa

Page 3 SPECIAL lilSTRUMENT GROOP - STATUS REPORT Date 9 April RMB Time 2030 Instrument Type r-imary Function Who is Location & Type Vital Signs Prior Action, tiew in Recovery Using of Indication of Health Results Ac t i.,n or Class Pe.i Pressure and Indicate water Control Roon Control Room On-scale read-

1) Lost B OT5G level location for coolint ing fluctuations wide range level
2) Procedure written by utility to put in dP between FW fica and s6 cam pressure
3) Have dP cell from Lynchburg 4)Tapisoutside
5) Will ao on both OTSG's Pressurizer level Level indicator Check all 3 to Act 12 indicated high computer wit noise, then OK Sct Is one not powe r-c Bailey says.de-ed?

powered last longer N Pressure Have been heavi-flo fluctuation Still monitor-Sct ly irradiated when pump is off-ing of PF0's c Foxboro (not boiling not ou guaranteed for pressure source W highradiati'on)

--~ w _ Date _ 9 April SPECIAL INSTRUMENT GROUP - STATUS REPORT .t Time _ __2030 R New P for Action _ 3 Who is location & Type Vital Signs Ac tf on Pe1 Primary Function of Indication of. Heal th Resul ts t Type Using T hot is coming Detennine RTO Schr in Recovery bridge avail-Jer Control Room Computer printout out on 109 Loop temperatures I RTD's below flow nozzle I Can we find leak? Pressurized to clea, i c up Is beirig read i on computer? ,surizer .ve What can trip primary pump and what has erature been disabled? k ba N O u 4 I I .}}

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