IR 05000348/1993030

Insp Repts 50-348/93-30 & 50-364/93-30 on 931206-1210.No Violations or Deviations Noted.Major Areas Inspected: Process & Effluent Monitors,Post Accident Sampling Sys, Annual Radiological Environmental Operating Rept

ML20059G154
Person / Time
Site:	Farley
Issue date:	01/06/1994
From:	Decker T, Mcneil N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20059G149	List: IR 05000348/1993030 ML20059G144
References
50-348-93-30, 50-364-93-30, NUDOCS 9401240020
Download: ML20059G154 (10)

Text

. - . _ . . _ . . . _ - -- _. .

. ,

UNITED STATES

,#'in mac%> NUCLEAR REGULATORY COMMISSION p ' ' k REGloN 11

.r E 101 MARIETTA STREET. N.W., SUITE 2900 7, :: j ATLANTA, GEORGIA 303234199

\,

• /

3 0.119%

Report Nos: 50-348/93-30 and 50-364/93-30 Licensee: Alabama Power Company .

600 North 18th Street Birmingham, AL 35291-0400 Docket Nos.: 50-348 and 50-364 License Nos.: NPF-2 and NPF-8 Facility Name: Farley 1 and 2 Inspection Conducted: December,6-10, 1993 Inspector: N ' ' wY /b' , /~ / /D/

Date Signed N.~G. McNeill /1

// /, o Approved by: x _ //m , i', /l o i //t / h/

T. R. Decker, Chief Date' signed Radiological Effluents and Chemistry Section Radiological Protection and Emergency Preparedness Branch Division of Radiation Safety and Safeguards ,

I SUMMARY Scope: I This routine, announced inspection was conducted in the areas of process and effluent monitors, the Post Accident Sampling System, the Annual Radiological Environmental Operating Report and environmental sampling, Radiological Waste  :

'

Handling, the proposed Zinc Addition and Monitoring System, the Microbiologically Induced Corrosion program, and Previous Inspection finding Results:

The plant had a Microbiologically Induced Corrosion program in place and operational (Paragraph 2).

An Incident Report relative to effluent monitors and a Steam Generator leak was investigated and found to have been handled properly by the licensee (Paragraph 3).

The status of the Zinc Addition and Monitoring System was updated and a timetable for implementation was discussed (Paragraph 4).

The licensee had submitted an Annual Radiological Environmental Operating Report which detailed minimal impact on the environment surrounding the Farley Nuclear Plant. The inspector accompanied licensee personnel on an environmental sampling collection route (Paragraph 5).

9401240020 940107 PDR ADOCK 05000348 G PDR

. - - . _ . - _ . _ .. _ _ - _ - ._ _ .. .

,

,

The performance of the recently installed Liquid Radiological Waste handling system was discussed and trends in Solid Waste shipments were reviewed and .'

found to be within Technical Specifications and licensee guidelines for reducing the volume of wastes (Paragraph 6). '

'

The collection of a Post Accident Sampling System' liquid and ' gaseous' sample '

under simulated accident conditions was observed as part of a licensee exercise drill and found to meet all requirements (Paragraph 7).

Previous Inspection Items were closed out (Paragraph 8).

f e

i s

[

t

'

l l

i

.

. - .

._ _ - . _ . _ . . _ _ . .- .. ._

, ,

.

'

REPORT DETAILS Persons Contacted Licensee Employees  ;

• Bayne, Safety Audit and Engineering Review Auditor

• 0. Graves, Radwaste Supervisor ,

• R. Hamm, Engineer, Chemistry and Environmental -

R. Hill, General Manager - Nuclear Plant

• R. Livingston, Environmental Supervisor N. McGilvray, Nuclear Specialist I

• Mitchell, HP Superintendent

• C, Nesbitt, Manager Operations  ;

J. Osterholtz, Technical Manager

'

• L. Stinson, Assistant General Manager of Operations  :

G. Terry, Safety Audit and Engineering Review Auditor

• M. Willis, Chemistry Foreman

• R. Wood, Chemistry Supervisor Other licensee employees contacted during this inspection included engineers, operators, technicians, and administrative personne Nuclear Regulatory Commission j

• T. Ross, Senior Resident Inspector j

• Attended exit interview Acronyms and Initialisms used throughout this . report are listed in the ,

last paragrap . Microbiologically Induced Corrosion Program (84750)  ;

,

TS 3.4.8 specifies the chemistry control requirements for the reactor ;

coolant syste The inspector discussed with cognizant licensee personnel the continuing actions that_ the plant was taking in order to prevent' microbiological ,

attack of cooling water piping and heat exchangers by the plant service wate ,

Protection against ingress of corrodants from the plant cooling syste is discussed below: Service Water ,

The licensee indicated that the Service Water system is treate with two types of biocides'which are applied to plant cycles -1 operating at river water temperatures. Sodium hypochlorite is ;

added to the system for clam growth control. Chlorine dioxide.is l added as an additional biofouling inhibito The system is also chemically treated with a polyacrylic acid dispersan ,

i i

!

-j

__ _ _ _ - -_-_

.

The following procedure was reviewed to determine whether all parameters were being addressed:

-

FNP-0-CCP-708, Chemical-Radiochemical Control Procedure,

" Chemical Addition / Control of the . Service Water System,"

, Rev. 29, dated November 1993 Circulating Water The licensee indicated that the Circulating Water system is treated with two types of biocides, a disperr. ant, and with corrosion inhibitors. The system is treated with chlorine dioxide for biofouling and with a nonoxidizing quaternary amine for the additional biocidal action.. The application and frequency of these applications is tied to water temperature as in the Servic Water system. The system is. treated with a polyacrylic acid dispersant similar to that used in the Service Water system. The system is also treated with zinc chloride and an organophosphate .

as corrosion and scale prevention respectivel The following procedures were reviewed to determine whether all parameters were being addressed:

-

FNP-1-CCP-706, Chemical-Radiochemical Control Procedure,

" Chlorine Dioxide Addition to the Circulating Water System,"

Rev. 8, dated November 1993

-

FNP-0-CCP-301, Chemical-Radiochemical Control Procedure,

" Chemical Control of the Circulating Water System," Rev.16, dated November 1993 The procedures was found to cover all required aspects of a MIC ,

program in regards to chemical treatment.and frequency of applicatio Sewage and Sanitary Water The licensee performs regular chlorination of the Sewage and Sanitary water systems. The details of which are detailed in the ;

following procedure: l

'

-

FNP-1-CCP-710, Chemical-Radiochemical Control Procedure,

" Operation of the Sewage Treatment Plant Chlorinator and the Advance Series 1030 Chlorine Gas Detector," Rev. 2, dated November 1992 A review of the procedure and the system hardware did not indicate a problem with the system and it's operation.

I l

- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

.

I

.. ,

'

3 Cooling Towers ,

The licensee indicated that the coolingLtower are high pressure sprayed with a quaternary amine solution during scheduled outages as physical inspections reveal accumulations of algal / fungal growth on the wood. member structure Condenser Water Boxes The licensee representative indicated that the plant was continuing to control slime and bacteria by the use of the mechanical cleaning system which utilizes recyclable sponge balls to continuously clean the condenser tube inner surfaces and prevent foulin f A review of the MIC program at the facility indicated that the license was meeting all minimum requirements and that the licensee had in place an adequate monitoring and treatment progra No violations or deviations were identified. Effluent Monitors (84750)

TSs 3/4.3.3.1, 3/4.3.3.10, and 3/4.3.3.11 define the operation and surveillance requirements for monitors of radioactive (or potentially radioactive) streams. This instrumentation is provided to monitor.and control the releases of radioactive materials during normal- and abnorma plant conditions as well as effluents during routine effluent release Alarm / trip setpoints for the monitors are calculated in'accordance with the procedures PCP to ensure that the alarm / trip will occur prior to exceeding the limits in 10 CFR 20. The alarm / trip setpoints for the process monitors are specified in the TS An IR was received by the Resident Inspector and was reviewed by the inspector upon arrival at the site. The IR is discussed as follows:

• IR No. 2-93-283 " Process Monitor Alarm on Steam Generator Draining of Blowdown"~ ,

In this incident, the R-19 process monitor alarmed on the S/C blowdown system. The monitor alarmed during restart operations. No leakage occurred and the system was isolated. After the alarm, the generator was drained and the "2B" S/G was identified as potentially contaminate Samples were taken and showed an increase in both secondary side gros activity and the presence of boron. The radionuclides detected included Chromium-51 (4.70E-05 uti/mL), Manganese-54 (3.30E-06 uti/mL),- Cobalt-58 (3.40 uCi/mL), and Cobalt-60 (1.26E-05 uCi/ml). Based upon these findings, a primary to secondary leak was suspected to have occurred during S/G Tube and Plug repairs which were performed during the outag Subsequent analysis was to show that this was in fact the cause of the leakage and the resultant monitor alar ,

~__

.

4

+

While the Resident Inspectors are reviewing this matter from the ;

standpoint of weld integrity and S/G tube performance, there appears to have been no violations of TSs in the areas of effluents or process monitors performance. In fact, the incident revealed a good response in the process monitors to isolate and identify a potential leakage pathwa ,

No violations or deviations were identified. Plant Water Chemistry and Zinc Addition and Monitoring Sy, tem (ZAMS)

(84750)

The inspector discussed the continuing plans that the licensee was $

pursuing for the proposed zinc injection system. As was discussed in the previous inspection (50-348, 364/93-12), the system incorporates the hardware to inject zinc borate into the Primary RCS and to monitor the concentration of zinc in the syste ,

.

The potential benefits of the system are listed as: reduced corrosion rates of most materials of construction, reduction of both initiation and propagation of PWSCC in Alloy 600 and other primary system materials, and reduced radiation levels due to reduced corrosion product transport. The possible problems associated with Zinc-65 radioactivity, as experienced in BWRs, are addressed in the proposal. The lesser i radiological hazards of the Zinc-65 as opposed to the Cobalt-60 and Cobalt-58 are key to the reduction of potential radiological hazard .

The licensee has continued plans to install the ZAMS and has completed some minor modifications during RF9 to accept the skid mounted syste Electrical taps and demineralized water lin s for feeding into the charging pumps were installed during the outage. The equipment on the skid at present is expected to include. a batching tank, an on-line zinc analyzer with input to the control room as well as at the skid panel, and the injector mechanis The licensee expects delivery of the equipment in mid-February 199 Tentatively, the plant expects to be able to begin actual chemical addition in March 1994. The licensee is currently collecting baseline data of radiation monitoring on system loops and in situ gamma analyse The licensee will also perform eddy current testing to assess S/G PWSC i At the present time all preparations have been completed to accept the ZAMS and begin chemical addition in early 199 No violations or deviations were identifie i

.

.

5 Annual Radiological Environmental Operating Report (84750)

TS 6.9.1.6 requires that the Annual Radiological Environmental Operating Report be submitted prior to May 1 of the year following the Annual i Radiological Environmental Operating Report. TS 6.9.1.6 also states format and content requirements for the Annual Radiological Environmental Operating Repor The FNP Environmental Monitoring Program is designed to detect the effects, if any, of plant operation on environmental radiation levels by monitoring airborne, waterborne, ingestion, and direct radiation pathways in the area surrounding the plant site. Indicator sampling stations are located where detection of the radiological effects of the plant's operation would be most likely, where the samples collected should provide-a significant indication of potential dose to man, and where an adequate comparison of predicted radiological levels might be made with measured levels. Control stations are located where radiological levels are not expected to be significantly influenced by '

plant operation, i.e., at background locations. An environmental impact assessment of plant operation is made from the radiological measurements at the sampling station The inspector accompanied licensee personnel on a weekly sample collection route. The samples collected included particulate air filter and iodine cartridge samples collected onsite. The inspector also visited water and vegetation collection site The inspector observed the collection, labeling, and instrument calibration associated with the. ;

sample collections. No problems were identified with any of the i procedures observe t The inspector concluded that the licensee had a good program in place to detect the effects of radiological effluents, direct radiation, etc. due >

to plant operationi and that those operations had caused minimum impact to the environment and virtually no dose to the general publi No violations or deviatius were identifie . Radwaste Processing System (84750)

10 CFR 71.5(a) requires that each licensee who transfers licensed l material outside the confines of its plant or other place of use, or who delivers licensed material to a carrier for transport, shall comply with the applicable requirements of the regulations-appropriate to the mode of transport of the DOT in 49 CFR, Parts 170 through 18 Pursuant to these requirements, the inspector reviewed the licensee's I activities affiliated with these requirements, to determine whether the licensee effectively processes, packages, and stores radioactive nterial !

!

. . . . . -- - _ _ _ _ ,

.

'

The inspector followed up on the performance of the new CNSI Pressurized-Demineralyzer System which was installed in March 1993. This system utilizes a chemical treatment process called polyelectrolyte injection in the influent stream. The system also incorporates a four vessel arrangement with different functions performed by the vessels. The first two act as a deep bed charcoal filter, the third acts as a mixed bed organic resin filter, and the fourth as an additional resin or ion  ;

specific resin as needed. The licensee has found that the top sluice capabilities of the upper portion of the charcoal bed has greatly increased the life of the medi The licensee stated that the current system will be utilized throughout the Unit 1 planned Refueling Outage of March to.May 1994. The licensee will decide upon a permanent system to be installed by June 199 The inspector concluded that the licensee is taking a proactive and deliberate approach to radwaste handling and processin ,

No violations or deviations were identifie . Post Accident Sampling System NUREG-0737, Criterion 2a provides specifications for the establishment ~

of onsite radiological analysis capabilities to provide quantification of noble gases, iodines, and non-volatile radionuclides in the reactor coolant system and containment atmospher TS 6.8.3.d outlines the requirements and functions which must be performed by the PAS The inspector observed collection of PASS samples which were collected as part of the licensee's Emergency Drill on December 8, 1994. Gaseous and liquid PASS samples were collected and analyzed by plant personnel under simulated accident conditions. This required technicians to fully dress out in anticontamination suits and full-face respirators and transport the simulated highly radioactive samples to the Primary Laboratory for analysis. The inspector also observed the HP personnel as they assisted in the collection, handling, and monitoring of all phases of the exercis The inspector reviewed the following procedures which were used in the exercise:

- FNP-0-CCP-1300, " Chemical-Radiochemical Control Procedure, l Chemistry and Environmental Activities During a Radiological '

Accident," Rev. 20, dated November 1993

-

FNP-0-EIP-30, " Emergency Plan Implementing Procedure, Post Accident Core Damage Assessment," Rev. 10, dated January 1991 l

I l

. 4

- FNP-0-EIP-20, " Emergency Plan Implementing Procedure, Chemistry and Environmental Support to the Emergency Plan," Rev. 4, dated May 1991 As part of the exercise the inspector observed the briefing that the PASS team received prior to entry and the discussion of responsibilities and duties to be performed by each member of the team. The briefing included discussion of the hazards and possible problems to-be encountered during the exercise. The briefing and discussions were thorough and covered conditions as the exercise scenario required.

l The inspector also observed tl, actual collection of several gaseous samples in syringes and the collection of the liquid sample. The 1 technicians followed the procedures closely and exercised precautions to I handle the simulated highly radioactive samples. The samples were  !

transported in the lead shielded cart assembly and were taken to the Primary Laboratory for analysis. The liquid sample was analyzed for pH, boron, chloride, and gamma radionuclides. The gaseous samples were analyzed for hydrogen, oxygen, and gamma radionuclide The inspector determined from the observations and review of the applicable procedures that the licensee was able to demonstrate operation of the PASS adequately to meet all requirement No violations or deviations were identifie . Previous Inspection Findings (Closed) VIO 50-348/50-364-93-12-01: Misidentification of Radioisotopes in a Liquid Waste Release Permi This incident was described in an IR (IR No. 1/93/97) which described the release of a No. 2 Liquid Waste Monitor Tank on April 15, 1993. The violation detailed several problems with the analytical system and computer software used to produce these liquid and/or gaseous release permits. These problems were also identified in the procedure utilized and the training personnel received on these system During the previous inspection, the licensee had convened a special Task Force to review the procedure and make recommendations to prevent recurrence of this issue. The results of the Task Force are in large part for the closure of this findin Individuals qualified to perform Release Permits were coached on the factors that led to the violation, procedural changes were implemented to improve the use of SRAN (Sample Reanalysis) in gas sample analysis, and standardized checklists were added to the Release Permit which require signoff to ensure the Permit is applicable and complet Based upon these corrective actions the item is close _ _ - _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

. . . - _ _ _ _. -.

. -.

8 Exit Interview  ;

The inspection scope and results were summarized on December 10, 1993, ,

with those persons indicated in Paragraph 1. The inspector described the areas inspected and discussed the inspection results, including likely informational content of the inspection report with regard to documents and/or processes reviewed during the inspection. The licensee did not identify any such documents or processes as proprietar Dissenting comments were not received from the license . Acronyms nd Initialisms BWR - Boill.1 Water Reactor >

CFR - Code of Federal Regulations 00T - Department of Transportation .

FNP - Farley Nuclear Plant HP - Health Physics IR - Incident Report MIC - Microbiological 1y_ Induced Corrosion PASS - Post Accident Sampling System ,

PCP - Process Control Program PWSCC - Primary Water Stress Corrosion Cracking RCS - Reactor Coolant System REV. - Revision RF9 - Refueling Outage Number 9 S/G - Steam Generator TS - Technical Specification VIO - Violation ,

ZAMS - Zinc Addition and Monitoring System  ;

,

t t

e s

'

M E

- -