IR 05000498/1987069

Preoperational Insp Repts 50-498/87-69 & 50-499/87-69 on 871104-06.No Violations or Deviations Noted.Major Areas Inspected:Chemistry/Radiochemistry Program & post-accident Sampling Sys

ML20236Y454
Person / Time
Site:	South Texas
Issue date:	11/30/1987
From:	Murray B, Nicholas J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20236Y450	List: IR 05000498/1987069 ML20236Y448
References
TASK-2.B.3, TASK-TM 50-498-87-69, 50-499-87-69, NUDOCS 8712140005
Download: ML20236Y454 (7)

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i APPENDIX U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-498/87-69 Operating License: NPF-71 50-499/87-69 Construction Permit: CPPR-129 Dockets: 50-498~

50-499 Licensee: Houston Lighting & Power Company (HL&P)

P.O. Box 1700 Houston, Texas 77001 Facility Name: SouthTexasProjectEiectricGeneratingStation, Units 1

.and 2 (STP)

Inspection At: .STP, Matagorda County, Texas Inspection Conducted: November 4-6, 1987 Inspector: M J,/B. Nicholas, Seni6r Radiation Specialist n/so/p7 Da t'e

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F'acilities . Radiological Protection Section Approved: (OlM /Ikl[I')

B. Murray, Chief, Faciliti Radiological

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Protection Section Inspection Summary Inspection Conducted November 4-6, 1987 (Report 50-498/87-69)

Areas Inspected: Routine, announced preoperational inspection of the licensee's chemistry / radiochemistry program and the post accident sampling syste Results: Within the areas inspected, no violations or deviations were identified. One previously identified open item was close Inspection Conducted November 4-6, 1987 (Report 50-499/87-69)

Areas Inspected: No inspection of Unit 2 was conducte Results: Not applicabl Nk $DO G

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.. y DETAILS Perscos Contacted HL&P

• H. Kinsey, Jr. , Plant Manager  !

• L. R. Casella, Engineering 5. E. Citzler, Lead Chemistry Technician D. E. Collins, Senior Chemistry Technician

• W. P. Evans, Licensing Engineer

• R. A. Gangluff, Chemical Analysis Supervisor W. M. Gattis, Lead Chemistry Technician

• S. M. Head, Licensing Engineer Supervisor

• F. Joche, Chemical Support Supervisor

• L. Parkey, Plant Engineering Manager  ;

• R. J.~Rehkugler, Supervisor, Quality Assurance Audits '

R. E. Schirmer, Chemical Analysis Technical Supervisor C. L. Teets, Chemistry Technician J. J. Woods, Nuclear Chemist l

• T. E. Underwood,' Chemical' Operations and Analysis Manager j i

Others i

• R. Carpenter, Senior Operations Resident Inspector, NRC

• B. W. Nicholson, Chemical Support Startup, Volt Corporation Denotes those present during the exit interview on November 6, 198 . Followup on Previously Identified Inspection Findings (Closed) Open Item (498/8624-03): Primary Chemistry Program - This item was discussed in NRC Inspection Reports 50-498/86-24, 50-498/87-01, arid  ;

50-498/87-29 and involved the lack of an established and implemented i primary chemistry program including a procedure for the preparation of radioactive calibration standards and the testing and verification of primary chemistry and radiochemistry analytical procedures used to meet Technical Specification requirements. The NRC inspector reviewed Procedures PCP06-ZM-001, " Preparation of Radioactive Sources," Revision 1, draft, and OPRP10-ZL-0015, " Radiological Laboratory Preparation of Radioactive Standard Solutions and Calibration Standards," Revision 4, l June 22, 1987, and determined that these procedures contained sufficient information to prepare reproducible radioactive standards which would be ,

traceable to the National Bureau of Standards for all counting geometries  !

and matrixes utilized by the plant. The NRC inspector reviewed primary "

l chemistry and counting room instrument calibration and quality control data and results of intralaboratory crosscheck chemistry samples and .

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determined that the licensee had verified all primary chemistry and a radiochemistry analytical procedures. Thi item is considered close )

(0 pen) Open Item (498/8624-07): Postaccident Sampling System - (see I paragraph 3.)

3. Postaccident Sampling System The NRC inspector reviewed the licensee's postaccident sampling system (PASS) to determine agreement with commitments in Section 9.3.2 in the Final Safety Analysis Report and the requirements in NUREG-0737, Item II. The NRC inspector inspected the area in STP, Unit I where the PASS was installe The liquid and gas sample panel, PASS laboratory facility, and PASS control panel were complete The PASS had undergone preoperational testin The PASS in-line instrumentation was installed in the various PASS panels and had been tested and calibrated. The licensee had implemented a preventative maintenance and quality control program on the PASS in-line instrumentation. PASS operating procedures and backup analytical procedures to the in-line analyzers have been approved. The NRC inspector verified that the licensee's PASS and associated procedures provide equipment and procedures that satisfy the requirements of NURfC-0737, Item II.B.3., for representative sampling and analysis of reactor coolant and containment atmospher The licensee had completed theoretical and operational training for all lead and senior chamistry technicians on the PASS which provided two trained and qualified PASS operators on each shif The NRC inspector verified that the licensee's testing of the PASS confirmed representative sampling of reactor coolant and containment atmosphere and demonstrated that the PASS procedures, instrument analytical sensitivities, and analytical results of chemistry parameters are consistent with PASS requirements. The licensee had not established and implemented a PASS operational monitoring program and had not demonstrated system capability to sample and analyze a sample of reactor coolant and a sample of containment atmosphere within the required 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> in accordance with NUREG-073 Open Item 498/8624-07, "Postaccident Sampling System," will remain open pending completion of the following matters before exceeding 5 percent powe * Develope and implement a PASS operational monitoring progra * Demonstrate the capability to sample and analyze a sample of reactor coolant and a sample of containment atmosphere within 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> No violations or deviations were identifie i l

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L i 4. Attachments lhe licensee's confirmatory measurement results concerning a radiological

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unknown sample prepared by the Radiological Environmental Sciences i Laboratory in Idaho Falls, Idaho, are documented in Attachments 1, 2, and . Exit Interview

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The NRC inspector met with the NRC senior resident inspector and the licensee representatives denoted in paragraph 1 at the conclusion of the inspection on November 6, 1987. The NRC inspector summarized the scope of the inspection and discussed the inspection findings, results of the radiological confirmatory measurement, and the actions necessary to close the PASS open item before exceeding 5 percent power as described in paragraph _ _ _ - _ _ = _ _

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ATTACHMENT 1 Radiological Confirmatory Measurements Confirmatory measurements were performed by the licensee on liquid radiochemistry samples prepared by the Radiological Environmental Sciences Laboratory (RESL) in Idaho Falls, Idaho. The samples were provided to the licensee for analysis in July 1987. The licensee's analytical results were !

compared to the known sample activities and the results of the comparisons are i presented in Attachment 2 for official documentation. Attachment 3 contains !

the criteria used to compare results. The licensee's results for the 1987 RESL sample were in 100 percent agreemen .

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l ATTACHMENT 2 RADIOLOGICAL CONFIRMATORY MEASUREMENTS RESULTS l

South Texas Project RESL Liquid Sample (Standardized 12:00, MST, January 11,1987)

STP Results NRCResults1/ STP/NRC Comparison Nuclide (uCi/ml) (uCi/ml) Ratio Decision 3H 1.3810.13E-04 1.55 0.03E-04 0.89 Agreement 895r 2.0210.05E-04 2.1210.06E-04 0.95 Agreement 80Sr 1.96 0.11E-05 1.9210.08E-05 1.02 Agreement 55Fe 8.7910.29E-05 9.4710.19E-05 0.93 Agreement i 54Mn 2.8110.07E-05 2.7010.05E-05 1.04 Agreement 60Co 2.53i0.06E-05 2.6010.05E-05 0.97 Agreement 137Cs 3.8610.06E-05 3.81i0.11E-05 1.01 Agreement 1! NRC results were taken from the standard certification supplied to the NRC Region IV office as prepared by RESL and traceable to the National Bureau of Standards.

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ATTACHMENT 3

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Criteria for Comparing Analytical Measurements The following are the criteria used in comparing the results of capability tests and verification measurements. The criteria are based on an empirical relationship established through prior experience and this program's analytical requirement In these criteria, the judgement limits vary in relation to the comparison of the resoiutio NRC VALUE Resolution =

NRC UNCERTAINTY LICENSEE VALUE Ratio =

NRC VALUE Comparisons are made by first determining the resolution and then reading across the same line to the corresponding ratio. The following table shows the acceptance value RESOLUTION AGREEMENT RATIO

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

16 - 50 0.75 - 1.33 51 - 200 0.80 - 1.25

>200 0.85 - 1.18 The above criteria are applied to the following analyses:

(1) Gamma Spectrometr (2) Tritium analyses of liquid sample ,

(3) Iodine on adsorber (4) 895r and 90Sr determination (5) Gross Beta where samples are counted on the same date using the same reference nuclid _ _ _ _ _ - _ - - _ _ - -