IR 05000302/1988010

Insp Rept 50-302/88-10 on 880321-25.No Violations or Deviations Noted.Major Areas Inspected:Review of post- Refueling Startup Testing,Rcs Leakage Determination,Review of Local Leak Rate Testing & Verification of Containment

ML20151V461
Person / Time
Site:	Crystal River
Issue date:	04/19/1988
From:	Jape F, Scott Sparks NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20151V429	List: IR 05000302/1988010 ML20151V424
References
50-302-88-10, NUDOCS 8805030067
Download: ML20151V461 (10)

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UNITED STATES

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Report Nc.: 50-302/88-10 Licensee: Florida Power Corporation 3201 34th Street, South St. Petersburg, FL 33733 Docket No.: 50-302 License No.: DPR-72 Facility Name: ' Crystal River 3 Inspection Conducted: March 21-25, 1988 Inspector: b, d . bp d-d*00 S. E. Sparks j Date Signed Accompanying Personnel:

J. Jeiler Approved by: AM N F. Japa, Chief, Test Progran(V Seftion Date Signed Division of Reactor Safety SUMMARY Scope: This routine, unannounced inspection was in the areas of review of post-refueling startup testing, reactor coolant system leakage determination, review of local leak rate testing, and verification of containment integrit Results: No violations or deviations were identifie '

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REPORT DETAILS  !

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Licensee Employees  !

• J. ' Alberdo, ~ Assistant Director, fluclear Plant Operations

• P. D. Breedlove, Supervisor, Records Management

• Collins, Nuclear Safety and Reliability Superintendent- '

• J. Cooper, Nuclear Technical Support Superintendent

• G. H. Halnon, Nuclear Operations Tec ;

W. G. Neuman, Supervisor of ISI ,

• W. L. Rossfeld, Manager, Nuclear Compliance j

• S Williams, Nuclear Regulatory Specialist t

• E. Welch, Manager, Nuclear Electrical Engineering Services .

• C. A. Woody,' Reactor Engineer Other licensee employees contacted included engineers, technicians, operators, mechanics, and office personne '

NRC Resident Inspectors

"J. Tedrow, Resident Inspector T. Stetka, Senior Resident Inspector

• Attended exit interview Exit Interview The inspection scope and findings were summarized on March 25, 1988, with those persons indicated in paragraph 1 above. The inspector described the areas inspected and discussed in detail the inspection finding No dissenting comments were received from the license The following new items were identified during this inspection:

. Inspector Follow-up Item (IFI) 302/88-10-01: Verify licensee's revision to PT-114, Moderator Temperature Coefficient Determin6 tio IFI 302/88-10-02: Review licensee's evaluation as to the need to local leak rate test containment electrical penetration The license did identify some material as proprietary during this inspection but, this material is not included in this inspection repor . Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspectio "-

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l l Unresolved Items t i

Unresolved items were not identified during this inspectio l Reactor Coolant System Leak Rate Measurement - Unit 3(61728)

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The -licensee performed reactor coolant leakage measurements in accordance  !

-with Surveillance Procedure SP-317, RC System Water Inventory Balance, on March 23, 1988. The procedure requires that only starting and ending '

values be taken over an eight hour interval. The inspector reviewed the ,

procedure for technical adequacy, and verified the correction factors used for Reactor Coolant System (RCS) temperature and pressure changes. The inspector observed plant operators. during the performance of SP-31 Measurement sources for the various plant parameters were taken from [

recall points of the plant computer, and all leakages were determined by l hand calculations .and a four function calculator. The operators seemed '

knowledgeable about the procedur :

The measurements described above address the measurement of total 1.eakage j from the RCS. Leakage that is collected in the reactor coolant drain tank from reactor coolant pump seal leakoff, as well as tnat from measured ,

leaks such as valve packing, is defined as identified leakag The ;

allowable leakage of one gallon per minute is the difference between the  ;

measured total leakage and the identified leakag The microcomputer program RCSLK9 was used by the inspector for verific't-  !

tion of reactor coolant system leakage measurements, and is described in NUREG-110 The parameter list is given in Attachment 1. A version of i RCSLK9 had to be modified due to the unique configuration of the plan The modification invalved compensation for the addition of 0.2 gallons per  :

minute flow rate into the reactor drain tank due to the reactor coolant pump seal standpipe flush water. The purpose of the standpipe flush is to preclude precipitation of boron around the standpipe and seals. The -

results of RCSLK9 are provided in Attachment 2, and demonstrate conformance to the lechnical Specification limit of less than 1 GPM  !

unidentified leakag The RCSLK9 results also agree well with licensee  ;

result '

l No violations or deviations were identifie . Post-Refueling Startup Ter.ing - Unit 3 (72700, 61708, 61710)  ; OP-210, Reactor Startup, performed January 8, 1988

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i Reactor criticality was accomplished in an orderly fashion by diluting to a specified boron concentratio'i, after which cottrol reds >

were withdrawn. Deboration of the RCS commenced to a precriticai

, concentration of 1955 ppmB. As required per procedure, two Estimated  ;

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Critical Position calculations were performed and were in close i agreement prior to reactor startup. Safety Rod groups were withdrawn

{ to their upper limit Regulating Rods were withdrawn until [

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criticality was achieve Estimated and actual critical rod positions were as follow:

Rod Group Estimated (% withdrawn) Actual (% withdrawn)

1-4 100 100 5 100 100 6 100 100 7 34 42 8 25 25 The actual boron concentration at the time of criticality was 1955 ppm b. PT-112, Hot Zero Power Regulating Rod Group Worth and Differential Boron Worth Measurement, performed January 9, 1988 r

l The inspector reviewed procedure PT-112 to determine conformance with I acceptance criteria. Predicted and measured rod group worths were as follows:

Rod Group Predicted Worth Measured Worth 5 1355 pcm 1401 pcm

6 927 pcm 832 pcm 7 881 pcm 838 pcm l

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5-7 3163 pcm 3071 pcm The acceptance criteria of less than or equal to 15% for groups 5, 6, and 7 individually, and less than or equal to 10% for groups 5-7 were satisfie The differential boron worth of control rod groups 5-7 was measured to be 7.8 pcm/ppmB. This agrees well with the predicted value of pcm/ppm PT-114, Moderator and Temperature Coefficients Determination at Hot Zero Power, performed January 9, 198 Procedure PT-114 calls for the determinat'on of the Moderator Temperature Coefficient (MTC) following a 5 degree heatup, a 10 degree cooldown, and again for a 5 degree heatup. The reported MTC for the cooldown was 3.76 pcm/F, which satisfies Technical Specification (TS) 3.1.1.3 requirement of less positive than pcm/F whenever thermal power is less than 95% of rated thermal powe Procedure PT-114, Revision 11, had been substantially revised per Interim Change I.C. #PT-114-5 in accordance with proper station administration procedure Most revisions were interim-to-become permanent changes and were made to 2/ lect TS changes, increase

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clarity, and provide more flexibilit However, the inspector did not agree with the following revisions to PT-114:

(1) Acceptance criteria 10.5 was deleted. This criteria requires that MTC's calculated for the two heatups be within plus or minus 2.0 pcm/F of the MTC calculated for the cooldow The purpose of this acceptance criteria is to provide additional technical validity for the reported MTC calculated during the cooldown. The MTC for the cooldown is the final reported value, and is usually more accurate because it is determined over a larger temperature chang (2) Also deleted from the latest version of PT-114 was acceptance criteria 10.6, which required independent verification and sign-off of the test result (3) In addition, the inspector noticed that the procedure did not req'uire the notification of the Nuclear Shift Supervisor if the acceptance criteria associated with TS's were not met. The failure to satisfy some of the stated acceptance criteria of PT-114 would result in a TS action statemen The inspector discussed the above items with licensee personnel, who agreed that they should be re-incorporated into PT-114. At the exit interview, management made a commitment to revise procedure PT-114 to re-incorporate acceptance criteria 10.5 and 10.6, as well as require the notification of the Nuclear Shift Supervisor and reference to the l appropriate TS if acceptance criteria were not met (IFI 302/88-10-01, i Verify licensee's revision to procedure PT-114, Moderator Temperature

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Coefficient Determination), PT-111, Hot Zero Power, All Rods Out Critical Boron Test, performed January 9,1988 The inspector reviewed test results for the licensee's test to determine the critical RCS boron concentration at hot zero powe All necessary limitations, precautions, and prerequisites were me The measured value of 2033 ppm 8 was within plus or minus 50 ppmB of the predicted value, and thus satisfied the acceptance criteri SP-102, Control Rod Drop Time Tests, performed January 7, 1988 The inspector reviewed all safety and regulating rod drop times from the fully withdrawn position and subsequent power interruption to 3/4 insertion. All drop times satisfied TS 3.1.3.4 requirement of less than or equal to 1.66 second No violations or deviations were identifie _

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7. Determination of Reactor Shutdown Margin - Unit 3 (61707)

The inspector reviewed surveillance procedure SP-421, Reactivity Balance Calculations, for technical adequacy, compliance with procedural requiremento, and compliance with TS. The reported' shutdown margin of-3300 pcm atisfies the TS requirement of -1000 pc The inspector verified that. reactivity worth curves used in the determination of reactor shutdown margin were properly interpreted and were controlled document No violations-or deviations were identifie . Containment Local Leak Rate Program (61720) Documents Reviewed

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SP-179, "Containment Leakage Test - Type "B" and "C", Revision 25"

- SP-181, "Containment Air-Lock Test, Revision 19" Scope of Review The inspector reviewed the overall local leakage rate program to verify that procedures have been developed and implemented consistent with regulatory requirement The inspector reviewed the documents listed above for technical adequacy, for compliance with the regulatory requirements of Appendix J to 10 CFR 50, the Technical Specifications, and with applicable industry standard The inspector also held discussions with the licensee regarding the documentation of test results, the repair and retesting following failed tests, and the relationship of these items to the "As-Found" and "As-Lef t" conditions of containment as applied to Containment Integrated Leak Rate Test (CILRT) results.

, Findings l Based on the review of portions of the above procedures, the inspector concluded that the licensee had developed and implemented

procedures which address the essential elements of the local leak

! rate test regulatory requirements. However, the inspector noted that

- the licensee was not leak rate testing any containment electrical penetrations and nor did the licensee's Technical Specifications require electrical penetrations to be subject to Type B leak rate i test Paragraph II.G. of Appendix J to 10 CFR 50 require that Type l B tests be performed tc measure leakage across each pressure-

' containing or leakage limiting boundary of the primary reactor containment. The inspector expressed this concern of not leak rate testing electrical penetrations and requested information pertaining

to the design and installation of all types of containment electrical

penetrations found in the plan The licensee is currently l

evaluating tne need to local leak rate test containment eletrical

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I penetrations. At the exit interview, the licensee agreed to supply }

the requested information regarding containment electrica penetrations to the NRC for review. This matter was identified as:

IFl 302/88-10-02: Review licensee's evaluation as to the need to local leak rate test containment electrical penetration [

The inspector reviewed the local leak rate test results summary and discussed analysis of test results and the status of repairs and retests with the licensee. The inspector was satisfied with the - ,

licensee's understanding of the application of these results to the ,

"As-Found" and "As-Lef t" conditions of containment. The licensee ,

acknowledged the application of the results to the technical-  ;

specification overall leakage limits and to CILRT failure criteri The total allowable leakage rate for type B and C tests is 248,656

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SCCM (0.6 La). The results of type B and C tests conducted October through December 1987, during the last refueling outage,  :

showed that the "As-Found" leakage exceeded the 0.6 La valu The t

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"As-Left" value was 25,611.1 SCC Witnessing of local leak rate test performance va', performed by the-Resident Inspector and is oocumented in Inspection Report .

50-302/87-3 Within the areas inspected, no violations or deviations were j identifie ,

9. Verification of Containment Integrity (61715)  ; Records Reviewed f

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SP-341, "Monthly Containment Integrity Check, Revision 20"

- SP-181, "Containment Air Lock Test, Revision 19"

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SP-300, "Operating Daily Surveillance Log, Revision 97"

- SP-347, "ECCS and Boration Systems Flow Path, Revision 35" f Scope of Review The inspector reviewed all records from the above TS required  !

surveillance procedures since the plant started up from the past i refueling outage in early January 1988. Records from SP-341 were  !

reviewed to verify the proper alignment of isolation valves and blind flanges for all primary containment penetrations per TS requirement .

4.6.1.1.a. Records from SP-181 were reviewed to verify the i'

operability of each containment air lock per TS requirement 4.6. Records from SP-300 were reviewed to verify the licensee's operation [

within the required containment pressure and temperature limits per l I

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TS requirement 4.6.1.4 and 4.6.1.5, Records from SP-347 were reviewed to verify the proper alignment of each valve in the flow path of the containment spray system per TS requirement 4.6.2. The inspector also accompanied the Resident Inspector in a walkdown

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! of the Reactor Building Spray System to verify that the component lineup was in accordance with license requirements for system l operability and that the system drawing correctly reflect "as-built" l plant condition Findings l The inspector's review of the above records found no instances where required Technical Specification surveillances were not performed at the appropriate interval . Also, no concerns were identified as a j result of the safety system walkdown with the. Resident Inspecto In summary, within the scope of this inspection, the inspector found reasonable assurance that the licensee was maintaining and implementing procedures to ensure containment integrit Within the areas inspected, no violation or deviations were identifie Attachments: Parameter List RCS Leak Rate

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ATTACHMENT 1 PARAMETER LIST Unit Identification:

Plant Name CRYSTAL RIVER Unit Number 3 Docket Number 50-302 Nuclear Steam System Supplier Babcock & Wilcox Vessel and Piping:

Volume 10579 cubic feet Pressurizer:

Level Units inches Temperature Compensated yes Nominal Level 180 inches Volume Below Nominal Level 800 cubic feet Volume Above Nominal level 702 cubic feet Calibration Curve Slope 3.207 cubic feet per inch Upper Level Limit 320 inches Lower Level Limit 0 inches Relief Drain Tank Makeup Tank:

Level Units inches Calibration Curve Slope 256.6 pounds per inch Upper Level Limit 120 inches Lower Level Li'.iit 0 inches Geometric Method Available No Drain Tank:

Level Units inches Calibration Curve Slope 288.5 pounds per inch Upper Level Limit 140 inches Lower Level Limit 75 inches Geometric Method Available No

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w ATTACHMENT 2 NRC INDEPENDENT MEASUREMENTS PROGRAM REACTOR COOLING SYSTEM LEAK RATES STATION: CRYSTAL RIVER TEST DATE: MARCH 23,1988 UNIT: 3 START TIME: 0300 DOCKET: 50-302 DURATION: 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> TEST DATA System Parameters Initial Final Pressure, psia 2157 2162 T Ave, degrees F 57 .6 L Water Levels Pressurizer, inches 204 20 Makeup Tank, inches 62.48 6 Drain Tank, inches 120.03 12 Water Charged = 205 gal Watar Drained = 0 gal l

TEST RESULTS Change in Water Inventory in pounds:

l Vessel & Piping -274 Drain Tank (1) 1318 Pressurizer 20 Makeup Tank (1) 5 Less: Water Charged 1706 Plus: Water Drained 0 Cooling System -1954 Leak Rates in gpm (3):

Gross 0.49

• Identified 0.13 Unidentified 0.36 (1) Determined from tank calibration curv (2) Determined form tank dimension (3) The density used for converting inventory change to leak rate vas 62.31 pounds / cubic foot based on standard conditions

Identified leak 3ge compensated for 0.2 GPM standpipe flush wate . _

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