IR 05000530/1986023
| ML17300A607 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 10/05/1986 |
| From: | Clark C, Richards S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17300A606 | List: |
| References | |
| 50-530-86-23, NUDOCS 8610220293 | |
| Download: ML17300A607 (12) | |
Text
U. S. 'NUCLEAR REGULATORY COMNISSION
REGION V
Report,No.
50-530/86-23 Docket.Nos.
50-530 License No.
CPPR-143 Licensee:
Arizona Nuclear Power Project P. 0.
Box 52034 Phoenix, Arizona 85072-2034 Date Signed ol~ /K Date Signed Facility Name:
Palo Verde Nuclear Generating Station Unit 3'
i Inspection Conducted:
September 9-16, 1'986 Inspected by:
C. Clark, Reactor Inspector
, I Approved by:
S. Richards, Chief, Engineering Section
~summar Areas Ins ected:
Routine, announced inspection of activities relating to a Containment Structural Integrity Test (SIT) and Integrated Leak Rate Test (ILRT).
The inspection included review of procedures, interviews with personnel, witnessing portions of the SIT and CILRT, inspection of containment building, associated penetrations and piping,. systems.
During thi.s inspection, Inspection Procedures 63050, 70307, and 70313 were covered.
Results:
Of the specific items inspected, there were no violations or deviations identified.
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DETAILS Arizona Nuclear Power Pro ect (ANPP)
- R. R. Baron, Compliance Supervisor
- K. Jesberger, Compliance Secretary
- W. D. Roman, Operations Engineering R. Klock, Operations Engineering
- W. L. Bichlmer, Operations Engineering
+W. J.
Jump, ANPP-Transition Manager
- D. M. LeBoeuf, QA Representative Bechtel Power Co oration (BPC)
P. Gal'anti, SIT Supervisor B. Blum, SIT Engineer L. Young, SIT Engineer The inspector also talked with other licensee and'ontractor personnel during the course of the inspection.
- Attended the Exit Meeting on September 16, 1986.
2.
Containment Structural Inte rit Test (SIT) and Containment Inte rated Leak Rate Test (CILRT)
a.
Procedure Review The inspector reviewed the Unit 3 SIT and CILRT procedures as described in Bechtel's procedure nu'mber IP-5.29, 'Revision 2 of November 8, 1985, "Primary Reactor Gontainment Structural Integrity Test Procedure,"
and the licensee's Procedure Number 91 PE-3CL02, Revision 0 of November ll, 1985 (and latest applicable test change notices (TCN)), "Integrated Leak, Rate Test."
This review was to ascertain compliance with plant technical specifications, regulatory requirements, and applicable industrial standards as stated in the following documents:
Palo Verde Nuclear Generating Station FSAR, Section 3.8.1.7.1,
"Structural Integrity Pressure Test," and Section 6.2.6.1,
"Reactor Containment Integrated Leakage Rate Test."
Proposed Technical Specifications, Palo Verde Nuclear Generating Station, Unit No. 3.
Appendix J to.10 CFR 50, "Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors."
Regulatory Guide 1.18, Revision 1, "Structural Acceptance Test for Concrete Primary Reactor Containments."
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4 ai ~ C +J 4' I 44) Irl.l JI) I 'I"'fj "") fJ I <<rtb "4 ~ '-)! ' 'Ja>>> 4 , "3':. ' '.4"'4547' I + If )QJ f4'4 t) f'4 '4 Jf 4)475 ) ' ')JJI 7 4'~l.f 4,',>e"r r ~.>*.>> > (.<<)I ~ P<>I<<[ i- " ~ Jf lib .)F (9) Pressurization system in service. No violations with NRC requirements or deviations were identified. Observation of Work and'ork Activities Prior to the SIT and CILRT, the regional inspector performed area surveys for pressurized components (such as tanks, fire extinguishers, etc.), valve lineups and instrument location assignments within the Containment Building. The purpose of the instrument survey was to locate and evaluate the placement of the taut wire displacement transducers, temperature sensors and dewpoint sensors. This inspection revealed that the sensors were located within the tolerances of the installation procedures. The pressurized component survey identified one fire extinguisher which had not been removed. It was promptly removed by the licensee. The inspector also verified that electrical penetrations were not pressurized above test pressure. The operation of the pressurization equipment (air compressors, after-coolers and air dryers) used for pressurization of the Containment Building was inspected to assure that procedures for prevention of potential problems were enforced. This included evidence of checking the pressurizing air for indications of oil contamination, establishment of communications between CILRT control center and the pressurization station, adequate cooling water being supplied to the after-coolers, and that control of the after-cooler air temperature was being maintained during pressurization. The inspector witnessed selected portions of the following SIT and CILRT activities: (1) Initial pressurization. (2) Initial SIT containment surface crack inspections. (3) SIT at 69.0 to 69.5,psig. (4) Depressurization and'4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> hold for stabilization prior to start of CIL'RT. (5) Repressurization to above 49.2 psig for CILRT. (6) Stabilization. (7) Data acquisition. (8) Completion of CILRT. (9) Leakage rate verification test. (10) Initial Containment Building depressurization. (Il) Final SIT containment surface crack inspections. (12) Completion of SIT. Applicable electrical and mechanical penetrations were inspected. Applicable portions of the valve lineups were inspected to see that they were completed in accordance with procedure and'hat no unidentified artificial barriers were erected. The overall performance of the SIT and CILRT crew members was observed by the inspector. Attributes evaluated were: availability of test procedures; test prerequisites being met; proper plant systems in service; special test equipment calibrated and in atr'4) )e tt I V,yflt I )<< I V[ ~ e h 'rj ",, f')feed 'f A " I'ae-a O' I,', >> ) '}.Vr ') '""":) a C'a(),J ~ *e -. l "~ v O' r, ir ',' It@ I I " l'aca( oc I' f t I) I
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'e(fl 'j f I c "l I'J"'pear'I f y'ct lt 'a I )et e)chhcvf )yjt c) .)f)j3 ..a: P) 3')(y ' y, " '.)eyf Q" I",").f,)V~ f" e itp I I r ff , ' ll, )CII (J f)lg) I C)ft Itaf, 'I 'fy tl)tree "hfyfel p r f,hl' e." I lf((' j >'= I f(( c "yae 'ffere 'q(y I If
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lc Pe 'yy jig f h f(jf. )'Ch Jtt Iy) g(a-Iet(f J r aa ay Ijr)fI 'y 'I (lf ' 1 teat $ I 'I '\\ ~ r ~Ip " )= a ,", ~ I ~ ~ service; and crew actions timely and correct. Crew members had received SIT and CILRT training prior to the test; this appeared evident by satisfactory performance of their duties. The licensee commenced pressurizing the containment for the SIT'on September ll, 1986. At the 10 psig hold, test personnel had to enter the 100 ft elevation personnel, hatch to tighten a valve adjustment nut on the inside door equalizer valve to secure a leak .through the valve. The initial SIT pressurization and 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> hold'or SIT inspections at 69.0 to 69.5 psig was completed at 2:00 a.'m. on September 13, 1986. After depressurization to 41.8 psig, a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> hold, repressurization and stabilization, 4:00 p.m. on September 14, 1986 was declared the official start time for the CILRT,. An 8-hour CILRT was completed at 0:01 a.m. on September 15, 1986, and a 4.75 hour8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> verification test was completed at 7:30 a.m. on September 15, 1986. All SIT inspections were completed by September 16, 1986. Data readouts from Dewcells Number 4 and 5 were dropped out of the CILRT data samples calculations, since they were trending up, while the other 4 were trending down. The CILRT procedure only requires at least three dewpoint sensors in operation during the test. The preliminary review of concrete crack mapping and displacement data indicated that the containment.performed as predicted during the SIT. The data readouts from two displacement transducers (D-2 and E-4) were questionable, and dropped out of data used in.the preliminary SIT data review, as allowed by the procedure. The data readouts from the remaining forty-two displacement transducers appeared to be normal. The licensee's preliminary results for the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (Pa 49.2 psig) Type A test, which did not include Type B or C additions, were a total time calculated leak rate of 0.0234 wt. X per day with a total time 95% upper confidence limit (UCL) leak rate of 0.0521 wt. X per day and a "mass, point" calculated leak rate of 0.0270 wt. % per day with a "mass point" 95X UCL leak rate of 0.0340 wt. X per day. Following the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Type A Test, a 4.75 hour8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> verification test was performed with an imposed leak rate of Lo = 7.49 SCFN or 0.1%/day, which produced a total time calculated leak rate of Lc 0.103 wt. X per day with a total time 95% UCL leak rate of 0.182 wt. X per day and a 'mass point: calculated leak rate of 0.0967 wt. X per day with a 'mass point" 95% UCL leak rate of 0.117 wt. X per day. These preliminary results appear to be within the latest allowed acceptance criteria. No violations of NRC requirements or deviations were identified. 'd ~ Procedure/Work Im rovement Comments The following comments on CILRT Procedure Number 91PE-3CL'02 were discussed with the licensee representatives, who stated that the inspector's observations would be considered for possible change/inclusion in the subject procedur ",'),>; >> C,.; +>>I:y,> I'.PI/.,: (I. "> 7 I),j',>';) ] r tr- ~,:, r! -.. t t p-: t'Sq, > g,t, '. -t, >> 5"' l -f '>t r gfglr', f<< ">).,,t 'f l) "r-> t 'F> r )I."'lf tl >g ~ ')'t ' S'jlf '" ~I'" > I'$ ~ g, >. I >,),~r, -r,:-)) g- >'t a,,-,rf >g r > ~ ) r f ) .)>~'>6 > t"W )'F'>I>M ~ >>>>' r) I'r,,>r, "r>)r>r >II,. ).'>t J >" . ' >>r >>Sfa>>> rr" ff>, >, > Ir> t>' ' $ >, > ', t. + ., > f> ) r ) )> ( r 'jg >F), I g r r I>l >> >,, Ilier>t > f>>fl> IC> ~ I I, I I jl tf T, ~ rrpf ) >, >"~f > - t ~ rl F F> tt >'r Ft, >'f t ) >> ")r,'>t > I a >) "f F> << >r I Ft >I -, t'(r ~ .'f> >) f ~ r>r 't> ) ', t = f ~ "'Il >,J')>">) '. r ~ '" ~ 'f . >>> t<<>" >.>> '", > ff.r>.' )' 'f"I" < >' ' >'>" '2 '4 't'> ) ) ~,)> ) "'.,',.) ' 't>> >" ~ 'i " " >>> PL I>>) ,I r rt>> f)%>I,,>D w" >t I q ".. ~,I . t .,',> <<., )'" ~ r l,t- )> I > $ >>>) f>>, S t >4 ">,P <<>> I r>( B>F, >gttt> > f f <<) f tt r ~ ' rr,r II r'r )>)rt>I *('C l>l P >I rl' ~I) I'> t >fP>) t f 4* ~ I Ir Paragraph 3.2.10 of the CILRT procedure references ANSI/ANS 56.8, 1981, "Containment System Leakage Testing Requirements", which states in paragraph 3.2.1'.7 (pressuring considerations) "Pressurized components such as tanks shall be removed..." During this inspection, the licensee had not identified or removed one fire extinguisher from thecontainment prior to the. inspector identification of same. As an aid in preventing recurrences in the future, the inspector observed that the CILRT work procedure could contain a sign off in it for verification that all fire extinguishers had been removed from containment. (2) Appendix P of the GILRT procedure had some valves incorrectly identified in it. (Example valves SIA-UV637 and SIA-UV647 were identified as valves SIB-UV637 and SIB-UV647..) The actual valves had label plates and yellow tags installed on them with the correct valve identification and the valves were positioned correctly for this test; however, the disagreement between procedure and actual valve installations never generated formal procedure changes. When the sub)ect valves were identified to the licensee, pen and ink changes to the master working copy of the procedure were generated. Since this same appendix has been used in several procedures and units, it should receive a thorough review prior to the next test. Also some instruction clarification should be issued to people working with the CILRT procedure, that re-emphasizes the requirements for a formal document change to correct valve identification in the work procedure. (3) The CILRT procedure does not record all major identified official CILRT results/data in it, such as actual CILRT leak rates, verification imposed leakage flow or leakage rates, etc. The information is available on various computer tape print outs, however, the information is not readily accessible if the test director or tapes are not available. (4) During valve alignment and leak team inspections, it was noted that additional valve location information in Appendix 0 and Appendix P would help in locating valves faster. Meetin The inspector met with licensee management representatives denoted in paragraph 1 on September 16, 1986. The scope of the inspection, observations and findings as noted in this report were discusse Vd ~'f F I't t t" <w I.')ttI'r"',KI 0
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