ML20205N145

Insp Rept 50-416/87-04 on 870223-0312.No Violations Noted. Major Areas Inspected:Liquid & Gaseous Effluent Releases & Process Sys & Radiochemistry Qa,Including Results of Split Samples Analyzed by Licensee & Region II Mobile Lab

ML20205N145
Person / Time
Site:	Grand Gulf
Issue date:	03/18/1987
From:	Harris J, Kahle J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20205N132	List: ML20205N127 ML20205N145
References
50-416-87-04, 50-416-87-4, NUDOCS 8704020603
Download: ML20205N145 (10)

See also: IR 05000416/1987004

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, A [fr UNITED STATES

. NUCLEAR REGULATORY COMMISSION

[ REGION ll

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$ j 101 MARIETTA STREET, N.W.

• t ATLANTA, GEORGI A 30323

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Mg 2 3 MB7

Report No.: 50-416/87-04

l Licensee: System Energy Resources, Inc.

Jackson, MS 39205

Docket No.: 50-416 License No.: NPF-29-

Facility Name: Grand Gulf Nuclear Station l

Inspection Conducted:.. ebruary 23-March 12,1987

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Inspector: '

dL- Icl,[i l

J. D. Hafr (Date Signed) l

Accompanying'Perso 1: R. R. M'arston

G. L. Froemsdorf

Approved by: M](c b 3//J/g7

J.B.- hle, Section Chief (Date Signed)

l Divis n of Radiation Safety and Safeguards

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SUMMARY

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, Scope: This routine, unannounced inspection involved onsite and in-office l

l inspection in the areas of liquid and gaseous effluent releases and process  !

systems, and radiochemistry quality control, including the results of split

samples analyzed by the licensee and NRC Region II Mobile Laboratory,

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Results: No violations or deviations were identified.

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8704020603 870323 6

PDR ADOCK 0500

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REPORT DETAILS

1. Persons Contacted

Licensee Employees

• J. D. Bailey, Compliance Coordinator

• S. M. Feith, Director, Quality Assurance

• W. E. Edge, Programs Manager, Quality Assurance

• J. L. Robertson, Superintendent, Plant Licensing

• R. F. Rogers, III, Project Manager, Unit 1

• R. D. Mooman, Technical Assistant to the Manager, Plant Maintenance

• A. McCurdy, Manager Operations

• W. C. Eiff, Principal Quality Engineer, Nuclear Plant Engineering

• J. M. Lassetter, Count Room Specialist, Chemistry

• T. L. Williamson, Chemistry Supervisor

• G. O. Smith, Plant Chemist

• F. W. Rosser, Radiation Control Supervisor j

• R. Hutchinson, General Manager

• R. S. Lewis, Nuclear Plant Engineering

• G. W. Vining, PM&C

• A. J. Malone, IST Coordinator i

B. Lee, Supervisor, Quality Assurance Audits

J. Holmes, PASS Specialist

J. B. Edwards, Engineer, Maintenance

J. V. Parrish, Chemistry / Radiation Control Superintendent  !

C. Elisaesser, Technical Assistant, Operations '

R. Sorrels, Engineer, Technical Support

Other Organizations

J. R. Hunt, Vice President, Nuclear Containment Systems

NRC Resident Inspector

R. C. Butcher l

• Attended exit interview

2. Exit Interview

The inspection scope and findings were summarized on February 27, 1987, ,

with those persons indicated in Paragraph 1 above. Discussions were also

held by telephone on March 12, 1987, concerning tritium analysis and

Post-Accident Sampling. Licensee management representatives acknowledged

the inspectors' comments and expressed no dissenting opinions. The

licensee did not identify as proprietary any of the materials provided to

or reviewed by the inspector during this inspection.

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3. Licensee Action on Previous Enforcement Matters

This subject was not addressed in the inspection.

4. Audits (80721,84723,84724,84725)

Technical Specification 6.5.2.8 defines the requirements for the audits

that are to be performed under the cognizance of the Safety Review

Committee. The inspector reviewed the most recent audits of; Offsite Dose

Calculation Manual, Chlorine Detection System (Control Room Ventilation),

Chemical Control Program, Qualification and Training of Chemistry

Personnel, Process Control Program, Radiological Environmental Monitoring

Program, and Implementation of Regulatory Guide 4.15. " Quality Assurance

for Radiological Monitoring Programs (Normal Operations) - Effluent

Streams and the Environment."

The audits addressed the overall program content in addition to technical

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specification content. The audits appeared very thorough and deeply

probing. Most of the findings were resolved during the audit period. In

discussions with cognizant licensee personnel, the inspector concluded

that there was a high level of management commitment to fully address all

findings.

No violations or deviations were identified.

5. RadioactiveLiquidWaste(84723)

Technical Specification 3/4.11.1 establishes upper limits for

concentrations of radioactive materials in liquid effluents.

The inspector reviewed selected release records from November 1986 to

February 1987. All releases reviewed were within technical specification

limits. The licensee has had good operational performance from the liquid

radwaste system since the last inspection in this area (50-416/86-09).

No violations or deviations were identified.

6. Radioactive Gaseous Waste and Gaseous Effluent Treatment Systems (84724)

Technical Specification 3/4.11.2 establishes upper limits for

concentrations of radioactive material in gaseous effluents.

The inspector selectively reviewed release records for the Radwaste

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Building, Turbine Building and Fuel Handling Area Ventilation Systems from

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October 1986 to February 1987. All releases reviewed were within

regulatory limits.

Technical Specifications 4.6.6.3 and 4.7.2 give surveillance requirements

for the Standby Gas Treatment System and the Control Room Emergency

Filtration System, respectively.

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The inspector selectively reviewed Operations and Maintenance records for

December 1986 ~ to February 1987. During discussions of the Surveillance -

Program, the inspector noted that it is conservatively implemented, with

l most surveillance scheduled well within regulatory requirements. j

{ The inspector selectively observed inspections and in-place leakage tests .

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of HEPA filters and charcoal adsorbers associated with the Standby Gas  ;

Treatment System,- the Control Room Emergency Ventilation Systems,

Containment Building Purge System, and the Containment Bu1_lding

Recirculation System performed by the licensee and contractor personnel.

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Activities observed were evaluated against the criteria of ANSI 510-1975,

i " Testing of Nuclear Air-cleaning Systems," and Regulatory Guide 1.52-1978, -

i " Design, Testing, and Maintenance Criteria for Post-Accident Engineered

Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption

Units of . Light-Water-Cooled Nuclear Power Plants. The licensee

demonstrated Technical Specification compliance and good utilization of

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contracts. During the . review of filter systems, the inspector noted

i several differential pressure and flow indicators that at times were.

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offscale. The inspector discussed this finding with licensee personnel.

] Cognizant licensee personnel acknowledged the . inspectors comments and

, stated that a design change request had been made for the differential

pressure indicators and agreed to evaluate _ the flow indicator by

l initiating a material nonconformance report. Other instances of offscale

l instrumentation had been brought to the attention of the licensee by the l

j resident inspector.

j No violations or deviations were identified.

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j 7. Radioactive Effluent Monitoring Instrumentation (92717, 84723, 84724)

] Technical Specification 3/4.3.7.1 establishes the minimum operability and i

j surveillance for radioactive liquid and gaseous process and effluent

stream monitoring instrumentation.

j The inspector selectively reviewed surveillance records for channel

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functional tests and channel calibrations including associated

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isolation / actuation signal circuits. During the inspection, the

i licensee's liquid effluent monitor was out of service in order to modify

l its flush water line in an attempt to reduce the background radiation for <~

! that monitor. The inspector discussed the problem with cognizant licensee

i personnel in regard to similar problems at other licensed facilities.

, The inspector discussed IE Infonnation Notice 86-42, " Improper Maintenance

! of Radiation Monitoring Systems," with cognizant licensee personnel. The

licensee has an independent verification program that addresses the types

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L of occurrences as described in the. information notice. The inspector -

! reviewed Procedure 01-S-06-29. " Independent Verification Program," Rev.1,

September-25,-1986. Procedural implementation should prevent similar

j occurrences.

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No violations or deviations were identified.

8. Post-AccidentSamplingSystem(PASS)(92701,84723,84724,84725)

The inspector observed portions of a PASS Training Module being conducted

during the inspection. Hands-on activities observed included Hot Lab

Set-up, grab sampling, and sample analysis. Training activities were

evaluated against established procedures, analytical techniques, and

general good practices. The training appeared to be effectively

implemented. The inspector noted that the Plant Chemist and an auditor

from Quality Assurance was in attendance.

The inspector reviewed modifications made on the PASS during the recent

refueling outage. The licensee installed flow instrumentation for air

sampling streams and upgraded heat tracing near the sampling statior.

Currently the licensee PASS capability is dependent on grab sampling. The

licensee plans to upgrade and reinstate online monitoring for chemistry

parameters when the required design / modifications can be made. Future

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modifications are also planned for obtaining grab samples for isotopic

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analysis. After reviewing the licensee capabilities to obtain samples

under accident conditions in regard to General Electric's technical

evaluations and the licensee procedures for core damage estimates, tie

e inspector concluded that the licensee is fully capable of implementing the

requirements of NUREG-0737.

Any modifications to the PASS will be reviewed during routine inspections.

(Closed)InspectorFollowupItem 50-416/86-09-01: Review and verification

testing of PASS engineering design changes.

No violations or deviations were identified.

9. Radiochemical Quality Assurance Program (84725)

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The inspector reviewed the licensee's radiochemical quality assurance

Guide 4.15, " Quality

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Assurance for Radiological Monitoring Programsprogram against the criteria giv

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Effluent Streams and the Environment." i

The inspector reviewed daily logs and calibration records for the ,

proportional counter, liquid scintillation system and gamma spectroscopy I

systems. The inspector also reviewed the results of laboratory l

intercomparisons of radioactive material measurements made between the

licensee and a reputable vendor laboratory. A high level of agreement

between the labs were noted.

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i No violations or deviations were identified,

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10. Confirmatory Measurements (84725)

Selected liquid and gaseous process streams were sampled with the

resultant samples analyzed by both the licensee's and NRC's RII Mobile

Laboratory gamma spectroscopy systems. The inspector provided a spiked

charcoal cartridge and a spiked particulate filter to the licensee to

ensure sufficient activity for valid comparisons for these geometries.

Other licensee geometries utilized in the comparison included a

4,300 milliliter gas marinelli, a one-liter liquid marinelli, and

14 milliliter gas vial. Comparisons of licensee and NRC results are given

in Table 1. The acceptance criteria is given in Attachment 1. All

measurements were in agreement. The inspector noted the relatively low

activity in plant systems reduced the overall number of comparisons. The

inspector also split a water sample spiked with' tritium with the licensee

to validate their ability to measure. The results are also given in Table

1 and show agreement.

No violations or deviations were identified.

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ATTACHMENT 1

CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS

This attachment provides criteria for comparing results of capability tests and

verification measurements. The criteria are based on an empirical relationship

which combines prior experience and the accuracy needs of this program.

In these criteria, the judgement limits are variable in relation to the

comparison of the NRC's value to its associated uncertainty. As that ratio,

referred to in this program as " Resolution," increases, the acceptability of a

licensee's measurements should be more selective. Conversely, poorer agreement-

must be considered acceptable as the resolution decreases. )

RATIO = LICENSEE VALUE

NRC REFERENCE VALUE

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Resolution Agreement

>4 0.4 - 2.5

4-7 0.5 - 2.0

8 - 15 0.6 - 1.66 ,

16 - 50 0.75 1.33 l

51 - 200 0.80 - 1.25

( 200 0.85 - 1.18

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TABLE 1

RESULTS OF CONFERMATORY MEASUREMENTS CONDUCTED AT

CRAND GULF NUCLEAR STATION

CONCENTRATION RATIO

SAMPLE ISOTOPE LICENSEE NAC RESOLUTION LICENSEE /NRC COMPARISON

Cha rcoa l Ca rt ridge cd-109 1.60 E-0 1.83 i .01 E-0 183 .87 Ag reemen t

(spiked) Co-57 3.53 E-2 3.89 i .04 E-2 97 .91 Ag reement

Detsctor 1 Ce-139 3.47 E-2 3.84 i .07 E-2 55 .90 Ag reemen t

Hg-203 8.27 E-2 7.93 i .57 E-2 14 1.04 Ag reement

Sn-113 7.15 E-2 7.80 i .57 E-2 49 .92 Ag reemen t

Cs-137 5.70 E-2 5.79 i .07 E-2 83 .98 Ag reement

Y-88 9.54 E-2 1.03 i .02 E-1 52 .93 Ag reement

Co-60 4.65 E-2 5.04 i .08 E-2 63 .92 Ag reement

Cha rcoa l Ca rt r i dge cd-109 1.72 E-0 1.832 1 .01 E-0 183 .94 Ag reement

(spiked) Co-57 3.81 E-2 3.89 i .04 E-2 97 .97 Ag reemen t

Detsctor 2 Ce-139 3.70 E-2 3.84 i .07 E-2 55 .96 Ag reement  ;

.97 Ag reemen t

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Hg-203 7.73 E-2 7.93 i .57 E-2 14

Sn-113 7.45 E-2 7.80 i .16 E-2 49 .96 Ag reement

Cs-137 5.58 E-2 5.79 i .07 E-2 83 .96 Ag reement

Y-88 9.30 E-2 1.03 i .02 E-1 52 .90 Agreement

Co-60 4.88 E-2 5.04 i .08 E-2 63 .97 Agreement

Charcoal Ca rtridge Cd-109 1.52 E-0 1.83 i .01 E-0 183 .83 Agreement

(spiked) Co-57 3.51 E-2 3.89 i .04 E-2 97 .90 Ag reement -

Detsctor 3 Ce-139 3.51 E-2 3.84 i .07 E-2 55 .91 Ag reement

Hg-203 8.11 E-2 7.93 i .57 E-2 14 1.02 Ag reemen t

Sn-113 7.23 E-2 7.80 i .16 E-2 49 .93 Ag reement

Cs-137 5.45 E-2 5.79 i .07 E-2 83 .94 Ag reement

Y-88 8.62 E-2 1.03 i .02 E-1 52 .84 Ag reemen t

Co-60 4.68 E-2 5.04 i .08 E-2 63 .93 Agreement

Charcoal Cartridge Cd-109 1.76 E-0 1.83 i .01.E-0 183 .96 Ag reement

(spiked) Co-57 3.72 E-2 3.89 i .04 E-2 97 .96 Ag reemen t

Detsctor 4 Ce-139 3.66 E-2 3.84 i .07 E-2 55 .95 Ag reemen t

Hg-203 6.47 E-2 7.93 i .57 E-2 14 .81 Ag reement

Sn-113 7.16 E-2 7.80 i .16 E-2 49 .92 Agreement

Cs-137 5.81 E-2 5.79 i .07 E-2 83 1.00 Agreement

Y-88 8.98 E-2 1.03 i .02 E-1 52 .87 Ag reement

Co-60 4.95 E-2 5.04 i .08 E-2 63 .98 Agreement

Particulate Filter Am-241 4.47 E-3 4.83 i .18 E-3 27 .93 Ag reement

(spiked) Cs-137 1.24 E-2 1.24 i .02 E-2 62 1.00 Ag reement

Detector 1 Co-60 8.74 E-3 8.07 i .24 E-3 34 1.08 Ag reement

Particulate Filter Am-241 5.94 E-3 4.83 i .18 E-3 27 1.22 Ag reement

(spiked) Cs-137 1.30 E-2 1.24 i .02 E-2 62 1.04 Ag reement i

Co-60 8.91 E-3 8.07 i .24 E-3 34 1.10 Ag reement

Detsctor 2

Particulate Filter Am-241 6.02 E-3 4.83 i .18 E-3 27 1.24 Ag reement

(spiked) Cs-137 1.28 E-2 1.24 i .02 E-2 62 1.03 Ag reement

Co-60 8.89 E-3 8.07 i .24 E-3 34 1.10 Ag reement

Detector 3

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TABLE 1 (cont'd)

RESULTS OF CONFlRMATORY MEASUREMENTS CONDUCTED AT

CRANC GULF NUCLEAR STATION

CONCENTRATION RATIO

SAMPLE LICENSEE LEC RESOLUTION LICENSEE /NRC COMPARISON

_lSOTOPE

Particulate Filter Am-241 4.07 E-3 4.83 i .18 E-3 27 .84 Ag reement

(spiked) Cs-137 1.30 E-2 1.24 i .02 E-2 62 1.05 Ag reement

Detector 4 Co-60 9.17 E-3 8.07 .24 E-3 34 1.13 Ag reemen t

One Li te r Ma ri ne l l i C r-51 2.88 E-2 2.74 i .05 E-2 55 1.05 Agreement

( resctor coolant) As-76 9.29 E-4 7.18 i .75 E-4 10 1.29 Ag reemen t

Detector 1

One Liter Marinelli C r-51 2.87 E-2 2.74 .05 E-2 55 1.05 Agreement

( retctor coolant) As-76 9.72 E-4 7.18 i .75 E-4 10 1.35 Ag reement

Dettctor 2

One Liter Marinelli C r-51 2.82 E-2 2.74 i .05 E-2 55 1.03 Agreement

( reretor coolant) As-76 9.26 E-4 7.18 i .75 E-4 10 1.29 Ag reement

Detector 3

One Liter Marinelli C r-51 2.89 E-2 2.74 i .05 E-2 55 1.05 Ag reement

10 1.37 Ag reement

( resctor coolant) As-76 9.85 E-4 7.18 i .75 E-4

Dettctor 4

G1s Vial (ortgas) Kr-85m 4.05 E-3 4.42 i .30 E-3 15 .92 Ag reemen t

Det:ctor i Kr-88 1.30 E-2 1.39 i .13 E-2 11 .94 Ag reemen t

Xe-135 1.22 E-2 1.38 i .05 E-2 28 .88 Ag reemen t

Xe-138 3.18 E-1 3.10 i .09 E-1 34 1.03 Agreement

Kr-87 2.60 E-2 2.60 t .12 E-2 22 1.00 Ag reemen t

Xe-135m 7.46 E-2 7.20 i .23 E-2 31 1.04 Agreement

Css Vial (offgas) K r-85m 4.00 E-3 4.42 i .30 E-3 15 .90 Ag reemen t

Detector 2 Kr-88 1.22 E-2 1.39 i .13 E-2 11 .88 Agreement

Xe-135 1.24 E-2 1.38 i .05 E-2 28 .90 Agreement

Xe-138 2.80 E-1 3.10 i .09 E-1 34 .90 Ag reement

K r-87 2.12 E-2 2.60 .12 E-2 22 .82 Ag reemen t .

Xe-135m 6.45 E-2 7.20 i .23 E-2 31 .90 Ag reement

C2s Vial (offgas) K r-85m 3.69 E-3 4.42 i .30 E-3 15 .83 Agreement

Dettctor 4 K r-88 1.23 E-2 1.39 i .13 E-2 11 .88 Ag reemen t

Xe-135 1.22 E-2 1.38 i .05 E-2 28 .88 Ag reement

Xc-138 2.82 E-1 3.10 i .09 E-1 34 .91 Ag reement

K r-87 2.19 E-2 2.60 i .12 E-2 22 .84 Ag reement

Xe-135m 8.25 E-2 7.20 i .23 E-2 31 1.15 Ag reement

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TABLE

A 1 (cont'd)

RESULTS of CONflRMATORY MEASUREMENTS CONDUCTED AT

CRAND GULF NUCLEAR STATION

CONCENTRATION RATIO'- -

SAMF?J J SOTO PE LICENSEE NRC de 30Lt3110N LICENSEff_NHg C0bpQJiGP(

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4300 ml Ma r s ne l l i Vr-85m 2.92 r.-4 3.09 i .',2 E-4 10 .95 Ag reemen t --

Offgas Detector 4 Xo-1 M 8.60 E-4 9.04 i .50 r-h 18 .95 Ag ree ment

y Xe-136 2.04 E-2 2.0? i . 08 t,- 2 2'2- 1.01 Agreement

Ag reemen t

K r-87 1.63 F-3 1.82 1 .12 E-3 15 ' .90

Xe-135m 5.99 T-3 4.81 i .26 E-3 19 .1.25 Ag reemen t

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4300 ml Ma ri ew i l l K r- 85c. 2.86 E-b 3.09 i .32 E-4 10 .93 Agreement

Of fes . Le6ector 2 Xe-135- 8.36 E-4 7,04 i .50 E-4 18 .92 Ag reement

(spikod) Xe-138 2.04 E-2 # 02 i .08 E-2 25 1.01 Ag reemen t ,

K r-8 7 1.73 E-3 1.52 i .12 E-? 15 .95 Ag reemant

Xe-115*. 5.00 E-3 4.81 i .26 E , 19 1.04 Ag reemen t

4300 mi % rinelli e:r-05m 2.93 E-4 3.09 i .37 -4 10 .95 Ag reec.en t

Offgas Detector 3 X t,'- 13 5 9.05 E.'t 9.04 i .' E-4 18 1.00 ' Alj reemen t

25 .73

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(spiked) Xe-138 1.48 E-2 E..'t 38 E-2 * D i sac reement

kr-87 1.55 F-3 <* 12 E-3 15 .85 Ag reemen t

s Xe-135m 5.46 E-3 ..d* .26 E-3 19 1.1 t; s Ag reement

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T ri t e 99 Sp i f,e .

H-3 1.90 E-2 2.1 i i .01 E-2 213 . 89 ' r.greement ,

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