ML19249F056
| ML19249F056 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 08/24/1979 |
| From: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| 790821, NUDOCS 7910030889 | |
| Download: ML19249F056 (3) | |
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SACRAMENTO MUNICIPAL UTILITY DISTRICT El 6201 S Street, Box 15530, Sacramento. California 95813; (916) 452-3211 August 21, 1979 Mr. R.ll. Engelken
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gN.crjNbk* @ 0 Office of Inspections and Enforcement
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U.S. Nuclear Regulatory Commission 1990 N. California Boulevard j
h'alnut Creek Plaza, Suite 202 h
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Uninut Creek, California 94596
G, W JG y,., 3 Docket No. 50-312 Rancho Seco Nuclear Generating Station, Unit No. 1
Dear Mr. Engelken:
Information requested by Item 1 of I.E.
Bulletin 79-17 is enclosed.
A review of safety related systems watch may contain stagnant oxygenated borated water has beqn made at Rancho Seco.
Piping which has been evaluated as being of concern has been highlighted on the ce-closed Process and Instrunentation Diagrams (P&lD's).
Preservice inspect. ions were performed only on Nuclear Class 1 piping (i.e.,
that piping connected di.rectly to the Reactor Coolant System out to the second isolation valve.) The inspections consisted of nanual ultrasonic testing conducted in accordance with the 1971 edition of Section XI of the ASME Boiler and Pressure Vessel Code with addenda through and including Summer 1971.
No indications were noted.
A total of 16 uelds have been volumetrically examined per Section XI requirements or as a result of augmented inspections instit-uted following our receipt of IE Circular 76-06.
Of these welds, four (4) were in the Decay Heat System, eight (8) were in the liigh Pressure Injection System, two (2) were in the Core Plood Systen and two (2) were in the Reactor Building Spray System.
Inspection was made with ultrasonic procedures developed and qualified in accordance with the 1974 cdition of Section XI with addenda through and including Summer 1975.
No indications have been noted.
In response to IE Circular 76-06, all affected piping in the Decay lleat and Containnent Building Spray Systems was hydro. statically tested in accordance with Section XI ('74 through '75) requirements during the First Refueling.
During the Second Refueling, additional hydrostatic tests were performed on the Decay lleat, Containment Build-ing Spray and lligh Pressure 'njection Systems.
1074 184 291000 s 'i f I L C T P. I C S Y ', T !." 5 E 5: VIN G M O r. E T it a s C '; 0, 0 C 0 IN ! !! ! !i E - P. OF C A l i F 0 R ii i A
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Tn addition, Reactor Coolant System and all piping connected directly to it are Icak checked prior to restart following refueling per Section XI requirements.
No leakage at welds has been evident during any of these tests or inspections.
As a result of the problems apparent at Three Mile Island 1, all af f ected accessible piping in the IIigh Pressure Injection, Decay Heat, Containment Buildine Spray and Spent Fuel System was visually in-s p m.m c r ei;;:.s o f a:.gn.
1..
- J Ieakage was found.
The chemistry controls for all hot systems containing t eactor coolan' fluids are well defined by the B&W Water Chemistry Manual (BAU 1385). They include:
- Range 17-1800 ppm B (Soluble poison)
Li as Li-7 0.2 to 2.0 ppm pH
- A function of P.aric Acid and Li content Conductance - A function of Boric Acid and Li content Dissolved 0 -
0.1 ppa nax.
2 Chloride Ion -
0.1 ppm max.
Fluoride Ion -
0.1 ppm max, llydrogen Gas -
15-40 cc/kg Total Gas 100 cc/kg nax.
For cold shutdeun conditions the restriction on dissolved oxy-gen is removed, provided there is no concurrent exceeding of the Cl or F-specification.
If Cl exceeds 0.1 ppm, N II is added to the cold systen.
dropbelowb.kppmprior to 250 F, N l1 i" During heatup, if 0 does not 24 2
added to provide for oxygen scavanging.
During system depressurization fm opening (refueling), the 0'H and total gas specifications are voided.
Systems cannot undergo 2
2 heatup with Cl or F-levels exceeding 1 ppm.
Similar specifications hold for systems which interf ace with reactor coolant fluid, i.e., Decay Heat, Spent Fuel Pool, Borated Uater Storage Tank, Denineralized Reactor Coolant Storage Tank, Letdotm Pur-ification System and Reactor Coolant Radwaste Systen.
Here O content i t, controlled only in t. hose systens which routinely provide f$uidto the circulating reactor coolant (i. e., Dil, BWST, DRCST, LDP and RCR).
llalide impurities are controlled in all systems.
Those systems having only LOCA safety functions, i.e.,
Core Flood Tanks, and Containment Spray, do not have specifications beyond the required B content or NaOH content.
1074 18b
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j Since startup operations in 1974 t.he described chemical spec-i fications have been maintained with the folJowing connents-1)
During hydrotesting of prinary <;ystems it was found that all of the radwante ion exchangers (including letdown purification demineralizers) had been loaded with improperly specified resin which was contributing Cl-.i t levels of approximately 1 ppm.
The problem was defined prior to hot hydrotesting and all dead legs were flushed with specification water prior to cont.inuation of the startup program.
2)
A lon;', tern special test prograu wa., initlated in 1973 to attempt to determine if Li (pIl control) programming, in conjunction with raintenauce of 0 at very low level at end of cycle, could aid in reduction of crud overall production or inhibition of transport out of the fuel zone.
Minor deviations froa the specified Li levels were experienced.
No cleanup circulation programs have been necessary nor sig-nificant design channes made to acconodate cher.istr controls.
The initial design provided for letdown purification of up to 140 gpm and Jucluded a backflushinr, filter of 1 nicron effective filtration.
Respect uily Suhnitted, 3
y k\\ s John J. PattiEt Assistant General Manager and Chief Eur,ineer JJM: R'dC: ch cc:
Director, Division of Operating Keactors, Office of Inspection and Enforcement, Uashington, D.C.
20355 10/4 186
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