IR 05000133/1987006

Insp Rept 50-133/87-06 on 871215-18.No Violations Noted. Major Areas Inspected:Actions on Previous Insp Findings, Mgt Organization & Controls,Radwaste Mgt,Transportation, Followup on IE Info Notices & Followup on LER

ML20148Q594
Person / Time
Site:	Humboldt Bay
Issue date:	01/12/1988
From:	Hooker C, Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20148Q578	List: IR 05000133/1987006
References
50-133-87-06, 50-133-87-6, NUDOCS 8802010144
Download: ML20148Q594 (7)

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l U. S. NUCLEAR REGULATORY COMMISSION l

REGION V

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Report No. 50-133/87-06 Docket No. 50-133 License No. DPR-7

Licensee: Pacific Gas and Electric Company j 77 Beale Street '

San Francisco, California 94106 Facility Name: Humboldt Bay Power Plant Unit 3 Inspection at: Eureka, California Inspection Conducted: December 15-18, 1987 Inspector: M4 .; A - //NMr C. A. Hooker, Radiati Specialist Date Signed Yl G. P. Yuhas, Chief

% ith Date Signed Facilities Radiological Protection Section Summary:

Inspection on Deceirber 15-18, 1987 (Report No. 50-133/87-06)

Areas Inspected: Routine unannovaced inspection of a facility in extended shutdown (preparation for SAFSTOR) including: actions on previous inspection findings; management organization and controls; radioactive waste management; transportt. tion; followup on IE Information Notices; followup on Licensee Event Report; and facility tour Inspection procedures addressed included 30703, 88005, 88035, 86721, 90712 and 9270 Results: Of the areas inspected, no violations or deviations were identifie k G

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DETAILS i Persons Contact,ed Pacific Gas and Electric Company (PG&E) Personnel

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R. T.' Nelson, Plant Manager

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• P. E. Rigney, Power Plant Engineer

• R. C. Parker, Senior Chemistry and Radiation Protection Engineer (SC&RPE)

• R. D. McKenna, Supervisor, Operations

• D. A. Peterson, Supervisor, Quality Control D. Richardson, Supervisor, Maintenance T. K. Tyler, Instrument and Electrical Foreman ,

• T. J. Williams, Environa, ental Coordinator '

• P. G. Rasmussen, Senior Power Production Engineer  ;

' Denotes those present at the exit meeting on December 18, 1987. Licensee Action on Previous Inspection Findings

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, (Closeo) Followup (50-133/87-02-01): This item involved movement of water ' rom the Spent Fuel Pool (SFP) liner gap into the French Drain (FD). The licensee determined that routine sampling of the FD increased differential pressure between the two systems. This resulted'in water leakage from the SFP liner gap into the FD. The inspector noted that the licensee had evaluated the situation and was preparing to install a FD

! sampling system that will keep the hydraulic pressure of the-FD above that of the SFP liner ga The inspector had no further questions '

regarding this matte No violations or deviations were identified.

3 Management Organization and Controls

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j The inspector reviewed the licensee's management organization and

controls to determine the licensee's compiiance with Technical l Specification (TS) requirements and licensee procedures, Organization and Staffing

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The licensee's organization and staffing has remained substantially '

unchanged since the last inspections in this area (50-133/86-03 and j 50-133/87-02). As of January 1987, the licensee had discontinued ;

the use of contract personnel for decontamination and waste i

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processing activities in preparation 70- SAFSTOR, since these .

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activities were essentially complete. The licensee had recognized !

that they were apparently understaffed with Radiation Protection .

Monitoring Technicians who also perform various duties associated [

with the operating non nuclear plants (Units 1 and 2). The licensee !

was in the process of acquiring an additional person in this are >

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Responsibilities and authority were adequately delineated in Nuclear

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Plant Administrative Procedure, NPAP.A-1, Plant Staff Oraanization and Responsibilities for Normal Operation Organization and staffing met TS requirements.under current plant condition ,

t No violations or deviations were identifie b. Procedure Controls Nuclear Plant Administrative Procedures, NPAP E-4, and NPAP E-4, Supplement No. 1, Procedures', delineates the licensee's procedure '

control program. Based on review of selected licensee procedures ,

and procedure history review system, the inspector determined that <

periodic (biennial) procedure reviews, new procedures, procedure  ;

changes were done pursuant to TS IX.D.f.1 and licensee procedure No violations or deviations were identifie c. Internal Reviews and Audits (IRA)

The inspector discussed the licensee's IRA program with licensee '

representatives, and reviewed the following procedures and ,

documents: i

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Procedures  ;

NPAP A-55, Random Weekend and Backshift Inspection *

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l NPAP C-10, Supplement No. 1, Housekeeping  ;

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Documents

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Monthly Housekeeping Inspection reports, July 29, 1987, through November 30, 198 j Plant Staff Review Committee (PSRC) Meeting Minutes for routine ,

monthly and special meetings, August 6, 1987, through November

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12, 1987.

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Random Weekend and Backshif t Supervisory Inspection Data Sheet f i reports, July 30, 1987, through November 12, 198 Based on the above reviews and discussions, the inspector determined that the licensee's audits were effective in ider.tifying and

reporting deficiencies to management. Appropriate corrective l l actions were generally timely and effective. QC audits and i

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inspections were adequately delineated in plant procedures and l

conducted with prepared checklist !

No violations or deviations were identifie ,

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d. Quality Assurance Program (QAP)

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The licensee's current QAP, established pursuant to the criteria outlined in 10 CFR 50, Appendix B, is described in PG&E's QA Manual which is'a corporate level document. QA audits to verify that Humboldt Bay Power Plant implements the QAP requirements are performed by PG&E's Corporate QA Department. Inspection Report N /87-05 describes the most recent QA audit of HBP ,

With respect to HBPP's proposed SAFSTOR operations, the licnesee has

developed and submitted a Custodial SAFSTOR Facility Quality Assurance Plan to the NRC and is described in the Commission's Safety rvaluation Report, dated April 29, 1987. During this

, inspecti.n the inspector reivewed a draft QA Manual (QAM) for HBPP's

- Unit 3 SAFSTOR operation '

Based on the reviews and discussions during this inspection, and observations during previous inspections, the inspector determined that the licensee has effectively implemented their existing QAP, and has established a program that should be effective during SAFSTOR operation During the inspection the inspector also noted that on December 15, 1987, a member from PG&E's Corporate QA staff provided on-site training on the licensee's Quality Problem Reporting (QPR) syste The training was conducted to provide an understanding of the licensee's QPR system and their responsibilities for identifying and resolving quality problem No violations or deviations were identifie ,

4. Radioactive Waste Management

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The inspector reviewed the licensee's radioactive liquid and airborne

, effluent control programs, ano solid radioactive waste activities to ensure compliances with 10 CFR Part 20, TS requirements, and

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recommendations outlined in various industry standard Audits Inspection Report No. 50-133/87-05 describes the last QA audit performed for these area !

No violations or deviations were identified, L Radioactive Liquid Effluent Control Inspection Report No. 50-133/87-02 describes previous inspection efforts related to this are j

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Ouring this inspection the inspector examined radioactive liquid '

waste discharges to the outfall canal from October 22 through

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December 14, 1987. The licensee had made four discharges during

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this period. The inspector verified by manual calculations thc MPC J values for batch release no. 87-25. No errors or anomalies were note i f

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The inspector reviewed records of tests and calibration data for the liquid radwaste sump high level alarm and pump start switches, and-the liquid radwaste vent monito Calibrations and tests were noted to have been conducted in accordance to licensee procedures and at the required frequenc Calibration of the liquid radwaste effluent monitor and problems associated with background radiation were described in Inspection Report No. 50-133/87-05. As of this inspection, the licensee had not resolved this matter, and was noted as an open item (50-133/87-05-01) in the previous inspection. The licensee was considering relocating the effluent monitor to-lower background area within the facilit TS VIII.B.1. limits the licensee's liquid radwaste inventory to 10,000 Ci. The licensee's current inventory was noted to be about 8.0 C No unmonitored release paths were identified. Radioactive liquid discharges were noted to be less than the limits specified in 10 CFR

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Part 20, Appendix B, Table II. Column Operation and sampling analysis were conducted in accordance with TS VIII. No violations or deviations were identified, c. Airborne Effluents Inspection Report No. 50-133/87-02 describes previous inspection efforts related to this are Weekly plant stack samples from June 30, 1987, through December 1, 1987 were examined. Quarterly vent grab samples of the hot chem lab, hot shop and liquid radwaste building for 1987 were also examine All sample data indicated that sample results were well below the 10 CFR Part 20, Appendix B, Table II, Column 1, limit No unmonitored release paths were identifie Weekly source checks and alarm tests of the stack effluent monitoring system, monthly calibration of the Refueling Building isolation monitors, and quarterly stack air sampler flow rate calibration and airflow alarm tests were examined. The calibrations, source checks and tests were noted to have been conducted in accordance to TS requirements and licensee procedure The inspector noted that the licensee had not performed the annual calibration of the stack monitoring system as required by TS.VII.B.2., which was due on October 23, 1987. However, the licenseo was aware of this matter and had initiated a Nuclear Plant Problem Report on December 14, 1987, to ensure that the system would be calibrated within the 25% allowance (TS.IX.14).

During review of licensee calibration and test procedures, and discussions with cognizant licensee representatives, the inspector observed that the licensee had no program to determine the accuracy

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of the indicated stack flow rate. In about 1980 (actual dates could not be verified during this inspection), major system modifications had been completed to increase the stack flow rate (one fan operating) from 12,500 cfm to about 43,000 cfm. The current indicated. flow rate is about 38,500 cfm and is an important parameter in determining radioactive airborne effluent release This matter was discussed with the SC&RPE who acknowledged the inspector's observation At the exit meeting on December 18, 1987, the inspector further expressed concerns regarding the lack of calibration and/or test programs to verify the accuracy of indicated stack flow rate. The licensee acknowledged the inspector's observations. The licensee's actions regarding this matter will be examined in a subsequent inspection (50-133/87-06-01, Open).

No violations or deviations were identifie Radioactive Solid Waste The licensee had not disposed of any radioactive solid waste since the last inspection of this area (50-133/86-03). The inspector also noted no changes in the licensee's solid waste progra TS.VIII.B.2. limits the licensee's inventory of solid waste to 50,000 Ci. The licensee's correct inventory was about 57 Ci of solid waste (resins) in the resin disposal tank, and about 2.0 Ci in assorted waste containers awaiting future shipment for disposa No violations or deviations were identifie . Transportation of Radioactive Materials The inspector reviewed the licensee's radioactive material transportation programs for compliance with the requirements of 10 CFR Parts 20, 70, and 71 and 49 CFR Parts 171 through 178, Audits The last QA audit of this area was discussed in Inspection Report No. 50-133/87-0 No violations or deviations were identified, Shipments The licensee had made one shipment of radioactive material since the last inspection in this area (50-133/87-03).

This shipment involved the licensee's transfer of their nominal Ci PuBe instrument calibration source to an authorized recipient, Shipment No. 554, on November 11, 198 _ _ _ _ _ _ _ _ _ _ - .

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Based on review of the shipping documentation for this shipment, the

' inspector determined that QC check lists were properly delineated and had been appropriately checked off. The documentation also indicated that the licensee had shipped and transferred the PuBe source pursuant to regulatory requirements and licensee procedure No violations or deviations were identifie . Information Notices The inspector verified that the licensee had received, reviewed and was taking or had completed action on IE Information Notices Nos. 87-31, 87-32, 87-43, 87-45, 87-47 and 87-5 No violations or deviations were identifie . Licensee Event Report (LER)

Based on an in-office review and on-site discussions, LER No. 87-002-00, Activation of the Gas Treatment System, was closed out by the inspecto The LER was reviewed for event description, root cause, corrective actions taken, generic applicability and timeliness of reportin No violations or deviations were identified.

l 8. Facility Tours The inspector toured various radiologically controlled areas of Unit 3 making independent radiation measurements with an NRC R0-2 portable ion chamber S/N 4042 due for calibration February 5, 198 Inspection Report No. 50-133/87-05 described poor housekeeping practices '

in the licensee's hot shop. During this inspection, the inspector observed that the licensee had made a great improvement in this are Housekeeping practices were generally good in all areas toure In addition, the inspector observed that all radiation areas and high radiation areas were posted as required by 10 CFR Part 20, and access controls were consistent with TS requirement No violations or deviations were identifie . Exit Interview The inspector met with the licensee representatives denoted in paragraph 1 at the conclusion of the inspection on December 18, 1987. The scope and findings of the inspection were summarize The inspector informed the licensee representau ves that no violations or deviations were identifie _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___-