IR 05000255/1989010

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Insp Rept 50-255/89-10 on 890327-31.No Violation Noted. Major Areas Inspected:Confirmatory Measurements Including, Review of Action Taken on Open Items (IP 92701),QA & post- Accident Sampling (IP 84750)
ML18054A803
Person / Time
Site: Palisades Entergy icon.png
Issue date: 06/16/1989
From: Bocanegra R, Schumacher M
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
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ML18054A802 List:
References
50-255-89-10, NUDOCS 8906230198
Download: ML18054A803 (12)
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Text

U. S. NUCLEAR REGULATORY COMMISSION REGION II I Report No. 50-255/89010(DRSS)

Docket No. 50-255 Licensee:

Consumers Power Company 212 West Michigan Avenue Jackson, MI 49201 Facility Name:

Palisades Inspection At:

Palisades Site, Covert, Michigan Inspection Conducted:

March 27-31, 1989 (Onsite)

April 27, 1989 (Region III)

May 19, 1989 (Region III)

Inspector:~~

Approved By: c-///~

M:'~.Schumacher, Chief Radiological Controls and Chemistry Section Inspection Summary License No. DPR-20 6fah Date

&//m Date Inspection on March 27-31 and April 27, 1989 (Report No. 50-255/89010(DRSS))

Areas Inspected: Routine announced inspection of confirmatory measurements including: review of action taken on open items (IP 92701), quality assurance, confirmatory measurements for in~plant radiochemical analysis, environmental monitoring, and post accident sampling (IP 84750);

Results:

Laboratory quality control was generally good, and confirmatory measurements results were very goo Problems with strontium analyses appear to reflect weak licensee oversight of vendor service The licensee met at the Region III office with the NRC to discuss the issue of frequent maintenance problems with the Post Accident Sample Monitoring (PASM).

At the meeting the licensee gave a brief history of the maintenance problems, and discussed past, present, and future corrective actio A followup telephone conference was held on May 19, 1989.

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DETAILS 1.. Persons Contacted

  • 0; Anderson, Quality Assurance
  • C. Axtell, Staff Health Physicist
  • G. Brunet, Licensing
  • +#T. Chartrand, Chemistry Supervisor
  • M. Grogan, R.M.C. Supervisor
  • +#C. Hillman, Chemistry Superintendent
  • J. Lewis, Technical Director
  • +#D. Malone, Sr. Nuclear Licensing Analyst
  • R. Margel, QA Administrator
  • M. Moore, R.M.C. Support
  • J. Paver, Chemistry Support Supervisor
  • +#R. Rice, Operations Manager
  • G. Slade, Plant Manager
  • M. Willers, Sr. H.P. Technician

+T. Palmisano, Palisades System Engineer Superintendent

+#T. Saarela, PASM System Engineer

  1. M. King, Section Head
  1. M. Eldrige, Systems Engineer
  • +E. Swanson, NRC Senior Resident Inspector

+#M. Schumacher, NRC Radiological Contra.ls and Chemistry Section Chief

+A. Januska, NRC Senior Radiation Specialist

  • Present at the entrance or exit meeting +Present at Region III meeting on April 27, 198 #Present at telephone Conference on May 19, 198.

Licensee Action on Prevfously Identified Findings (IP 92701)

(Closed) Open !tern (50-255/87016-01):

Analyze a liquid waste sample for Sr-89, Sr-90, gross beta and send results to Region III for comparison with the NRC reference laboratory *result The comparison showed that the Jicensee 1s results for gross beta were in agreement, and H-3; Sr-89, and Sr-90*results were in disagreement with the NRC reference laboratory (Table 2).

The.tritium analysis done by the licensee in~house was anomalously high indicating a possible problem with contamination or data transcriptio The strontium analyses done by a licensee contractor laboratory were also significantly high and in disagreement in contrast to previous years when they were lo Th vendor laboratory was also low, although in agreement, in cross check comparisons of Sr-89 and Sr-90 with an independent reference laboratory during the years 1986-198 **

  • The licensee appears not to have performed a QA audit of its vendor or to have reviewed the vendor's cross check recor The tritium results also indicate weak management oversight of this analysi The problems were discussed with licensee representatives at the exit meeting and in a telephone discussion on April 20, 198 The licensee was told that a description of plans to improve management oversight of vendor laboratory services would be requested in response to this repor This will be tracked under Open Item 50-255/89010-0 During the current inspection, two samples were split to provide a comparison for gross beta, strontium, and tritium between the licensee and the NRC reference laborator These will be followed under Open Item 50-255/89010-02 as discussed in Section This item (Open It~m 50-255/87016-01) is close (Closed) Open Item (50-255/87016-02):

Review gamma libraries and make necessary corrections for accuracy and consistenc The inspector reviewed a copy of the gamma library currently used for the gamma spectroscopy system Rh-106 gamma peaks are now identified by the longer lived parent Ru-10 Branching intensities and half-life have also been changed to correspond to Ru-10 (Closed) Open Item (50-255/87016-03):

Calibrate replacement gamma Detectors 2 and 1 within two weeks of receipt of certified standards and by mid July respectively, and Detector 3 by approximately August 1, 198 The inspector examined calibration records for 1987 and found that the three detectors had been calibrated as agreed.

(Open) Open Item (50-255/87017-02):

Licensee to implement regular use of control charts on gamma spectrometer system and to consider use of only the more i~tense lines in the energy c~librations. Using the more intense lines of a check source the licensee tracks six different parameters on control charts for each of the two germanium detectors; however, this has not been proceduralize The licensee agreed to revise appropriate procedures to reflect laboratory practic Confirmatory Measurements (IP 84750) Quality Assurance The inspector reviewed the latest germanium detector calibration records and daily QC graphs for the month of March 198 The inspector examined the results of the licensee's cross check program with an outside laboratory for 4th quarter 1987, 2nd quarter 1988, and 3rd quarter 198 The results for 4th quarter 1987 show a few disagreements, but an obvious 30% bias existed for all iodine cartridge sample The inspector noted that although no corrective action was documented, the 2nd and 3rd quarter results indicated that the 30% bias had been resolved, and corrective actions for the few disagreements were adequat *

  • Chemistry's three lithium drifted germanium detectors have now been replaced with intrinsic germanium detector The calibration procedure for the germanium detectors has been rewritten and revised four times resulting in significant improvemen Improvements included increasing the number of counts accumulated per peak, using mixed gamma standards (v europium-52), computerized energy curve graphing, and a more extensive precautions sectio To a great extent, the very good results in the confirmatory measurements appear to be directly attributable to these change The Lower Limit of Detection (LLD) is the smallest concentration of radioactive material in a sample that can, apriori, be detected with 95% certaint The licensee is required to meet LLD limits found in Technical Specification Table 4.24-3 for radioactive liquid effluent At the inspector's request, an LLD was determined by the licensee for the one liter release geometry using vendor supplied softwar Then a hand calculation was performed for comparison and found to agree with the vendor's software value, and appears to meet the T/S limit for the

nuclides selecte Sample Split Six samples (spiked particulate air filter, reactor coolant, waste gas, VCT gas, Safety Injection Refueling Water, and spiked charcoal adsorber) were analyzed for gamma emitting isotopes by the licensee and in the Region III Mobile Laboratory on site.

Comparisons were made with the licensee's two chemistry detector The licensee achieved 80 agreements in 82 comparisons as listed in Table l; the comparison criteria are given in Attachment The two disagreements occurred in the primary coolant sample (PCS) on both detectors for Co-5 The Co-58 energy peak is flanked by two I-132 peaks in the general region of 810 Ke For TIS related reactor coolant analyses, the licensee performs consecutive counts to allow the I-132 to deca On a later count of this sample the licensee was able to identify Co-58 at levels below 10 CFR 20 Appendix B limit A modified batch release composite sample and a liquid sample spiked with reactor coolant will be analyzed for gross beta, H-3, Sr-89, and Sr-90 by the licensee and the results reported to Region III for comparison with an analysis by the NRC reference laboratory on a split of the sample (Open Item 50-255/89010-02) Environmental Monitoring (IP 84750)

    • The inspector examined the 1987 Radiological Environmental Monitoring Repor The report indicates that the program is being implemented properly and that the results showed no apparent effect of plant operatio Post Accident Sampling System (IP 84750)

The inspector reviewed selected licensee records pertaining to the Post Accident Sample Monitor (PASM) system including maintenance, trafning, and audit The records indicated that weekly training on the system was hampered by frequent equipment breakdowns which resulted in performance of certain steps by simulatio The inspector's review of maintenance records indicated that approximately 70 work orders were submitted for the system over the period from 1986 to the present with completion time averaging about 100 day Problems with the PASM system had been identified in Licensee Audit No. -OT-87-5 performed July 198 The associated deviation report (D QG-87-40) indicated that the licensee's immediate response was to assure alternate methods were known to the technicians by means of caution tags hung for the affected step Other actions taken over roughly the following six months included review of system history and developement of an action plan to effect long term correction of the more persistent problem The review disclosed that failure to stock parts which had caused repair delays for certain components had been correcte However, it also noted PASM maintenance was 'slowed by competing priorities and budget considerations with the result that minor repairs to PASM were delayed until a more critical repair was neede The review identified nonfunctional or improperly functioning pressure indicators, thermocouples, and valves which did not necessarily render the system inoperable, but which could cause confusion resulting in ineffective training and questionable sample result Following the audit, steps were taken to speed up PASM maintenance work orders by putting them on the Operations Concerns List if they affected the system's capability of providing a sampl Nevertheless, the inspector's review indicated that these steps appeared to have only limited effect on maintenance response until December 1, 1988, when the auditor indicated in a follow up letter to the plant manager that he could not close out the Deviation Report because of continuing problems with the PASM pane Maintenance response appe2red to improve thereafte *

Licensee representatives met with NRC representatives in the Region III office on April 27, 1989, to discuss NRC concerns relating to PASM operabilit Licensee representatives described system problems and corrective actions underway and planne They stated that problems that would render PASM inoperable were being given high maintenance priority and pointed out that alternate methods of obtaining a sample remained

availabl They stated that the PASM system served as a backup to containment and failed fuel monitors for assessing fuel damage and indicated that the containment monitors were seldom if ever inoperabl By telephone call on June 8 and 12, the licensee representatives provided additional details on monitor availability for the 1987-1988 perio PASM was out of service 672 hours0.00778 days <br />0.187 hours <br />0.00111 weeks <br />2.55696e-4 months <br /> (8%) in 1987 and 432 hours0.005 days <br />0.12 hours <br />7.142857e-4 weeks <br />1.64376e-4 months <br /> (5%) in 198 They stated that the primary assessment monitors (containment hydrogen and containment radiation monitors) were available (at least one channel) throughout the period and that the failed fuel monitor was unavailable for only five days during the perio Licensee representatives also presented an overall action plan that included replacement of unreliable components including those identified in the audit, completion of a modification project to install in-line monitoring, evaluation of PASM design with implementation of needed changes, upgrade timeliness of maintenance, and miscellaneous system improvement Although projected completion was somewhat slow, the action plan should provide significant improvements in system reliabilit *

Licensee representatives provided an update of progress on the action plan during a telephone conference held on May 19, 198 They indicated that the in-line monitoring project was nearing completion (acceptance expected mid June), that chemistry sampling procedures were revised, that comparability between PASM and NSSS samples had been reverified, and that modification (replacement) of more unreliable components would be moved from 1990 to 1989 maintenance outag Licensee representatives agreed to provide in response to this report an updated action plan confirming the timetable for its completio (Open Item 50-255/89010-03)

No violations or deviation were identifie.

Open I terns Open Items are matters which have b~en discussed with the licensee, which will be reviewed further by the inspector, and which involve some action on the part of the NRC or licensee or bot Open items disclosed during the inspection are discussed in Section 2, 3, and.

Management Meetings (IP 30703) Exit Interview, March 31, 1989 The inspector met with licensee representatives denoted in Section 1 at the conclusion of the inspection of March 31, 198 The scope and findings of the inspection were discussed including the results of the confirmatory measurements comparisons (Section 2), lack of management oversight of vendor laboratory services (Section 2), and persistent maintenance problems associated with the PASM

(Section 5).

The inspector expressed concern to the licensee about the operability of the PASM and the apparent slow response to PASM repair order The licensee acknowledged the inspector's commen The inspector discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspector during the inspectio Licensee representatives did not identify any such documents or procedures as proprietar PASM Meeting in Region III office, April 27, 1989 A meeting with licensee representatives (Section 1) was held in the Regional Office on April 27, 1989, to discuss NRC concerns with PASM operabilit Licensee representatives described system problems and corrective actions underway and planneo (Section 5).

NRC representatives acknowledged the licensee's presentation and indicated a need for additional detail concerning certain action plan item Telephone Conference on May 19, 1989 A follow-up telephone conference was held on May 19, 1989 with licensee representatives (Section 1) to discuss the licensee action plan (Section 5).

Licensee representatives provided a status update and indicated that completion dates for certain action plan elements would be moved u The licensee agreed to confirm the details and submit an updated action plan in response to this inspection repor In telephone calls on June 8 and June 12, 1989, licensee representatives also provided additional details regarding operability of PASM and of other monitors used to assess fuel damag Attachments: Attachment 1, Criteria for Comparing Analytical Measurements Table 1, Confirmatory Measurements Program Results, 2nd Quarter 1989 Table 2, Confirmatory Measurements Program Results (Gross Beta, H-3, Sr-89, Sr-90), 2nd Quarter 1987

. Attachment 1 ATTACHMENT. CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS This attactvnent provides criteria for comparing results of capability tests and verification measurement The criteria are based on an empirical relationship which combines prior experience and the accuracy needs of this progra In these criteria, the jodgment limits are variable in relation to the comparison of the NRC's value to its associated one sigma uncertaint As that ratio, referred to in this program as "Resolution", increases, the acceptability of a licensee's measurement should be more selective. Conversely, poorer agreement should be considered acceptable as the resolution decrease The values in the ratio criteria may be rounded to fewer significant figures reported by the NRC Reference Laboratory, unless such rounding will result in a narrowed category of acceptanc *RESOLUTION RATIO = LICENSEE VALUE/NRC REFERENCE VALUE

, r \\

Agreement

<4 0.4 -.5 -.6 - 1.66 16 -

0.75 - 1.33 51 - 200 0.80 - 1.25 200 -

0.85 - 1.18 Some discrepancies may result from the use of different equipment, techniques, and for some specific nuclide These may be factored into the acceptance criteria and identified on the data shee TABLE l U S NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT CONFIRMATORY MEASUREMENTS PROGRAM FACILITY: PALISADES FOR THE 1 QUARTER OF 1989

NRC----*---

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lE-06

  • ~

1 E--1:)3 6. 1 E--06 2E-04 3. 4E--*06 sr:::-06 1. 5E-06 6E-*05

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.-, OE*-04 E-03

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  • ~JE-*1)3 i:-.1 I

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. -, *:;;E-01

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.

.::..

1. 9E-02 3. ~5E--03 3. 'JE--05 1. 4E*--05 1. :?::E--04

~. '7' E -- (> {:.

1 lE*--05

.-. 6E*-06

.

..::.

/~, * 2E-06 1. 2E-* 1:),:_:,

1. 'iE--03 7. OE*-06 4. OE-04 4. 1. E -n,~.

  • i. OE-06 2. 1 E*--06 9. 2~E-()5 3. 1. E --*Of'.'.
    .

1. 3E--C>2 Ii II f::.E-04 4. f:E--*03

,:_,II 3E-04 4. OE*--02 171. 4E*--04 3. 7E--02 c:" i.'.:.E-*04

  • -' *

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  • =* *-*. 3E*--04 c:"

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311 l E-02

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1_.I I lE-*04 4. 3E*-02 211 6E--03 4. lE-02 2. 4E-03 0. OE*-01 (i. OE-:) 1 511 5E--Ci3 c:" *-'. OE--04

. f::.E*-02 3, 4E*-03 7.,:_!:,[-03 1 4-E-03 1. 3E-03

.-,

L. 5E-04

---LICENSEE:NRC----

RATIO RES T

9. 7E--*O l c:"

._1 * 6E 00 A

1. OE 00 2. 5E 02 A

l. 2E 00 1. 2E 01 A

1:1

,_.. 4E-01 4, 1E 00 A

1:*1 I

' 5E--Ol

.'.'.;.. 9E 01 A

'~*. 9E*-01 c::" OE 00 A

  • -* *

l OE 00 I

5E 00 A

.

i.:*a

  • ~J II 7E*-01 3. 2E ()2 A

9. t.E-01 1. 2E 02 A

1. 6E (;~)

3. 7E 00 A

,-, 7E-Ol

-:z 7E O l A

7 *

  • -*.

1 3E (:1()

-z 2E 01 A

.

  • -*.

l. 2i::: l)\\)

c:"

._I II 7E 00 A

,*~1 9E--01

,;,. 5E 01 A

7.

1 1E 00 1 4E ():2'.

r,

.

.

H

'7'. ::::E-01

...:.. ::::E 01 A

1. 2E 00 2a 2E 01 A

II 7E 01 A

l. OE 00 1. lE <)2 A

I~). 7E*--O 1

/:,1 11 7E (i 1 A OE (i()

.., 9E 01 A

.

  • =>II C) * OE-01 1. OE 01

[I l

1E (ii)

2. 4E (i 1 I\\

.

t-1 1 2E 00 r. 2E 01 A

.

  • -*.

1. 1E 00 7. OE 00 A

1. 6E 00 7. OE 00 A

--- ~-------------------

TABLE 2 U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT CONFIRMATORY MEASUREMENTS PROGRAM FACILITY: PALISADES DATE: 3RD QUARTER 1987 SAMPLE NUCLID NRC VAL. NRC ER LIC.VA LIC.ER RATIO RESOL. RESULT

LIQUID H-3 5.58E-04 1.40E-05 6.00E-02 2.53E-03 107.53 3 D WASTE G BETA 3.65E-04 1.70E-05 3.lOE-04 4.70E-05 0.85 21. 5 A

SR-89 2.6()E-07 2.00E-08 (9.00E-07 3.46 1 D SR-90 5.30E-OB 6.00E-09 1.70E-06 7.00E-07 32.08 D

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