IR 05000440/1987006

Insp Rept 50-440/87-06 on 870408-10.No Violations or Deviations Noted.Major Areas Inspected:Completed Portions of Radiation Measurement & Chemical & Radiochemical Startup Tests

ML20209E409
Person / Time
Site:	Perry
Issue date:	04/22/1987
From:	Greger L, Miller D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20209E382	List: IR 05000440/1987006 ML20209E379
References
50-440-87-06, 50-440-87-6, NUDOCS 8704300043
Download: ML20209E409 (6)

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<,, U.S. NUCLEAR REGULATORY COMMISSION

REGION III

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Report No. 50-440/87006(DRSS)

Docket No. 50-440 License No. NPF-58 Licensee: Cleveland Electric Illuminating Company P.O. Box 5000 Cleveland, OH 44101 Facility Name: Perry Nuclear Power Plant, Unit 1 Inspection At: Perry Site, Perry, Ohio Inspection Conducted: April 8-10, 1987

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< Inspectors: D. E. Miller f/aa/87 Date Approved By: L hief 87

, Facilities Radiation Protection Date Section j

Inspection Summary Inspection on April 8-10, 1987 (Report No. 50-440/87006(DRSS)

! Areas Inspected: Routine unannounced inspection of completed portions of radiation measurement and chemical and radiochemical startup tests. Also i reviewed were a previous open item and progress made in completion of new contamination control related facilitie Results: No violations or deviations were identifie PDR ADOCK 05000440 0 PDR

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DETAILS Persons Contacted

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• G. Anderson, Unit Lead Engineer, ICS, Perry Plant Operations Department

• G. Dunn, Compliance Engineer, LCS, Perry Plant Technical Department (PPTD)

• D. Jones, Operations Engineer, LCS, PPTD

• J. Lausberg, Supervisor, OS&PU, Nuclear Quality Assurance Department

• C. Shuster, Manager, Nuclear Engineering Department

• F. Stead, Manager, PPTD W. McCoy, Health Physics Supervicor, RPS, PPTD

• T. McIntyre, Site Engineering Manager, GE

• F. Whitaker, Senior Health Physics Supervisor, RPS, PPTO r *S. Wojton, General Supervising Engineering, RPS, PPTD

• K. Connaughton, NRC Senior Resident Inspector The inspector also contacted several licensee technicians and supervisors.

, * Denotes those present at the exit meetin . General

This inspection, which began at 8:00 a.m. on April 8, 1987, was conducted to review radiation measurement and chemical and radiochemical startup tests. Also reviewed was a previous open item. Several tours of

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licensee facilities were made to review implementation of radiological controls and housekeeping. Postings, controls, and housekeeping appears adequat . Licensee Action on Previous Inspection Finding (0 pen)OpenItem(440/86031-01): Apparent need for additional health

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physics technicians. This matter is discussed in Section . Organization As discussed in Inspection Report No. 50-440/86031, it appeared that additional health physics technicians (permanent employees) will be neededforjobcoverageduringroutineoperations. Since then, a licensee representative has evaluated the need and recommended that 13 additional technician positions be filled; two of the 13 have since been filled. The licensee is seeking acceptable candidates to fill the additional position .

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The licensee has 23 contract technicians onsite to supplement the health physics staff; the contract technicians are covering outage radiological Jobs and aiding the staff health physics technicians in performance of routine surveys. Eighteen of the contract technician are ANSI N18.1-1971 qualified technician *

No violations or deviations were identifie . Startup Test STI-D21-002, Radiation Measurements FSAR Section 14.2.12.2.2 states that radiation measurements will be made throughout the plant prior to fuel load, subsequent to fuel load during reactor heatup, and at nominal power levels of 20-25, 60, and 100 percent of rated powe Also, surve Reactor Water Cleanup (RWCU)ys are to be performed before and aftersystem r of the startup neutron sources through the inclined fuel transfer syste Sets of radiation measurements were made throughout the plant before fuel load and at initial criticality (zero power). These measurements were made during mid-198 Gamma radiation measurements were made in general access areas and at 203 pre-established survey points. Neutron radiation measurements were made at selected survey points on the outer wall of containment. As expected, all area measurements were less than mR/hr gamma and 0.5 mrem /hr neutron (minimum sensitivities). No abnormalities were identifie A third set of radiation measurements (of six scheduled) were made during November 1986 after reactor operating pressure was achieved; core power was about three percent. Gamma radiation measurements were made in general access areas and at the pre-established survey points; neutron measurements were made at selected survey points on the outer walls of the drywell and containment. All areas measured were less than or equal

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to 0.2 mR/hr gamma and 0.5 mrem /hr neutron with the exception of the RWCU rooms. The maximum gamma reading in RWCU Room "A" was 1.2 mR/hr, and 0.8 mR/hr is RWCU Room "B". The survey results were compared with expected values; no measurement results were considered anomalou The fourth set of radiation measurements were performed on February 25, 1987, with the core power at about 20 percent and electrical power at

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160 MW Gamma radiation measurements were made in general areas and at l the pre-established survey points; neutron measurements were made at the l outer walls of containment. All areas measured were less than or equal I to 0.2 mR/hr gamma and 0.5 mrem /hr neutron with the exception of RWCU

Rooms "A" and "B" (15 and 18 mR/hr gamma respectively), and the Reactor l Sample Station Area (0.6 mR/hr gamma). The results of the survey

measurements were compared with the maximum predicted radiation exposure l rates presented in FSAR Figures 12.3-1 through 12.3-8. In all cases the

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measured valves were well below the FSAR maximum value Cn March 1, 1987, a test was performed to identify any potential area

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that could have elevated radiation levels during RWCU spent resin

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transfer. Health physics personnel performed radiological surveys in l

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accessible areas adjacent to RWCU resin transfer piping before, during, and after a resin transfer. No unexpected radiation levels were identified; all areas were properly poste Prior to initial fuel loading, a test to determine the adequacy of shielding at accessible locations adjacent to the Inclined Fuel Transfer System (IFTS) was performe Fourteen " pins" about 19-inches long, each containing 118 curies of antimony-124, were used as the radiation sourc The pins, arranged symmetrically around the circumference of a seven-inch diameter storage basket, produced an exposure rate of about 1400 R/hr at one meter in air. The source was lowered in stages through the IFTS while radiation surveys were performed in accessible areas adjacent to the IFTS and the source. No shielding problems were identified during the test. The licensee plans to perform a similar set of radiation surveys during the first refueling outage while an irradiated fuel bundle is being transferred from the reactor building to the fuel handling building. Control of access to locked rooms containing IFTS components is discussed in Section The radiation measurement commitments of FSAR Section 14.2.12.2.2 have been satisfactorily completed except for future measurements to be made at nominal rated power levels of 60 and 100 percent. These measurements will be reviewed during future performance of routine inspection module No violations or deviations were identifie . Access to Inclined Fuel Transfer System (IFTS) Components There are shielded rooms in which portions of the IFTS are expose Access to these rooms is through one doorway. An outer shielded door is posted with an instructional sign that states, "Potentiall Lethal Radiation Fields Possible During Transfer of Irradiated Fuel.y' An inner gate is locked and posted as a potential High Radiation Area. Control of access to the rooms is provided by an electrical interlock system (series circuit) which is designed to deny access when power is supplied to the IFTS. There is a keylock switch on the Unit Supervisor's Console and a keylock switch on the Master Relay Panel in the fuel building; these switches must be in the position which shuts off power to the IFTS before the access door can be opened by a key assigned to the Plant Health Physicist. Control of the keys and operation of the IFTS is presented in Procedure No. OM3A:50I-F42 " Inclined Fuel Transfer System, Unit 1."

During review of the procedure and observation of the Unit Supervisor's Console, the inspector noted that the keylock switch labelling and the description of key control /use in the procedure were confusinc. The apparent need to clarify the procedure and switch labelling w ue discussed at the exit meeting (0 pen Item No. 50-440/87006-01).

l After performance of shielding testing of the IFTS discussed in Section 5, a recommendation was made that a remote reading ratemeter be l

procured and installed in the IFTS Valve Room in containment; the ratemeter is to be located outside the access door. The ratemeter would

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O provide external evidence of the radiological hazard inside the valve room. The licensee's evaluation and followup of the recommendation will be reviewed during a future inspection (0 pen Item No. 50-440/87006-02).

No violations or deviations were identified.

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7. Startup Test STI-P35-001, Chemical and Radiochemical FSAR Section 14.2.12.2.1 states that various chemical and radiochemical tests will be performed prior to fuel load, prior to heatup, during heatup, and during power ascension; data is to be collected from the reactor water, condensate, feedwater, control rod drive water, condensate demineralizer, reactor water cleanup, main steam, and liquid and gaseous radwaste system The purpose for testing the chemical and r.tdiochemical parameters is to verify that chemical parameters of various fluid filled systems meet acceptable limits and to determine adequacy of plant sampling procedures and eguipment, analytical procedures and equipment, and sampling and

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handling techniques. Additional objectives for these tests are to evaluate fuel performance and condenser integrity, demonstrate proper steam separator-dryer operation, and to check calibration of certain process instrumentatio The inspector reviewed the results of tests performed prior to fuel load,

prior to heatup, and during heatup. The recuired testing was performed; all results were within the limits specifiec.in the technical specification During March 1987, chemical and radiochemical tests were performed with the core power at 30 percent and electrical generation at 290 MW Appropriate chemical and radiochemical testing of the reactor water cleanup, feedwater, CRD water, condensate, off gas, and liquid radwaste fluids were performed. All results were within specifications. No abnormalities were identified during testin The results of future testing during power ascension will be reviewed

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during later performance of routine inspection module No violations or deviations were identifie . Facilities and Equipment Newly constructed facilities and needs for additional facilities are

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discussed in Inspection Report No. 50-440/86031. The inspector cursorily reviewed progress made in construction of selected new facilities during this inspection. Construction progress for these selected

facilities is described below

• Permanent relocation of the sorting monitor to the radwaste building room where the reverse osmosis equipment had been installed has not been accomplished. Construction of radwaste compaction

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facilities awaits relocation of the sorting monito .-- - , . - - . - - - . -. -- ---, _ _- - - -.- - - .- -

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• A building to provide additional short-term storage space for packaged radwaste and laundry awaiting transport has not yet been constructe * Construction of the tool decontamination facility in the intermediate building has not begun. According to a licensee ',

representative, bids for construction are being receive * Other than the tool storage area previously described, few permanent storage areas exist for larger contaminated equipment / materials waich will be retained for reuse; there apparently are no firm plans to provide such storage area The inspector discussed with the licensee during the inspection and at the exit meeting the apparent need to expedite construction of the tool decontamination facility and to evaluate the need to establish additional permanent storage areas for contaminated equipment and materials (0 pen Item No. 440/87006-03).

No violations or deviations were identifie . Exit Meeting The inspector met with licensee representatives (denoted in Section 1) at the conclusion of the inspection on April 10, 1987. The inspector summarized the scope and findings of the inspection. The inspector also discussed the likely information content of the inspection report with regard to documents or processes reviewed by the inspector during the inspection. The licensee identified no such documents / processes as proprietary. In response to certain items discussed by the inspector, the licensee: Stated that Procedure No. 0M3A: S01-F42 would be reviewed to oetermine if a revision is needed (Section 6). Acknowledged the inspector's comment concerning the apparent need to expedite construction of the tool decontamination facility and establish storage areas for contaminated materials (Section 8).

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