ML19319C996
| ML19319C996 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/17/1973 |
| From: | Kidd M, Murphy C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19319C980 | List: |
| References | |
| 50-302-73-12, NUDOCS 8003040926 | |
| Download: ML19319C996 (8) | |
See also: IR 05000302/1973012
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UNITED STATES - , q ATOMIC ENERGY COMMISSION - o eD- ! p$ i p DIRECTORATE OF REGULATORY OPERATIONS ! l gg acason n - sun e sie . e g 230 pe Acurmer sracer sontswest 8 ate o' , t y, _ ,, ,,9,,,,,,,,, AT 4. A NT A. GEoRG s A 30303 . . . RO Inspection Report No. 50-302/73-12 ' Licensee: Florida Power Corporation - 3201 34th Street, South P. O. Box 14042 - St. Petersburg, Florida 33733 Facility Name: Crystal River 3 Docket No.: 50-302 License No.: CPPR-51 Category: B1 Location: Crystal River, Florida Type of License: B&W, PWR, 2452 Mut O v Type of Inspection: Routine, Unannounced Dates of Inspection: December 5-7, 1973 Dates of Previous Inspection: October 24-26, 1973 Principal Inspector: M. S. Kidd, Reactot ',spector, Facilities Test and Startup Branch Accompanying InJpector: D. J. Burke, Reactor Inspector Facilities Test and Startup Branch Other Accompanying Personnel: C. E. Murphy, Chief Facili ies Test and Startup Branch Principal Inspector: /4 d'7/7J /
M. S. Kidd, Reactor Inspector, Facilities Test Dat'e and Styrtup Branch Reviewed by:f ( -f e- V /u? / /J C. E. Murphy, Chiet','Kac111 ties Test and Startup Branch Date
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. - .. . . ., , , RO Rpt. No. 50-302/73-12 -2- . SU) MARY OF FINDINGS , I. Enforcement Matters , ' A. Violations - None ' B. Safety Items - None , II. Licensee Action on Previously Identified Enforcement Matters Not applicable. ' III. New Unresolved Items , 73-12/1 Preoperational Test Program Controls A transition control document and a temporary test device centrol procedure have not been developed for the testing program. (Details I, paragraph-3) 73-12/2 Steam Generator and Pressurizer Safety Valves The steam generator and pressurizer safety valves preopera- . tional test procedures have not yet been defined. (Details 1 II, paragraph 2.d) IV. Status of Previously Identified Unresolved Items
73-10/1 Preoperational Environmental Monitoring Program No change in status. Li:.i.nsee personnel intend to revise the Unit 3 Final Safety Analysis Report (FSAR) such that it will describe the environmental monitoring program as implemented. (Details I, paragraph 2) < V. Unusual Occurrences ' None VI. Other Significant Findings { Project Status No significant preoperational testing has been started. Licensee perscnnel estimate that testing of safety related systems could begin .- _ _ __ _ - - - _ _. . .
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(C' - R0 Rpt. No. 50-302/73-12 -3- 9 . around mid-January 1974. A few test procedures have been approved, all of Class III (non-safety 'related) category. The licensee esti- mate for fuel loading is November 1974. . .. VII. Management Interview F A management interview was held at the conclusion of the inspection December 7, 1973.- The following licensee representatives attended: Florida Power Corporation (FPC) Generation Construction Department C. E. Jackson - Crystal River Construction Superintendent ' Generation Engineering Dt_artment J. E. Barrett - Quality and Standards, Engineer II P. G. Davis, Jr. - Manager, Power Testing E. E. Froats - Manager, Nuclear Site Surveillance 0, R. W. Slater - Site Quality Engineer Production Department J. Alberdi - Nuc':1 ear Plant Superintendent D. W. Pedrick - Compliance Engineer W. P. Stewart - Assistant Nuclear Plant Superintendent Gilbert Associates, Incorporated (GAI) J. D. Green - Testing QA Coordinator A. The previously identified unresolved item regardir; ;he preoperational i environmental monitoring program was discussed. Details are given in ' Details I, paragraph 2. B. The new unresolved items in Section III were also discussed. Details, including management positions on them, are given in Details I, para- graph 2, and Details II, paragraph 2.d. % - . -, . _ , . . __. . . , . _ . _ _ _ . _ , _ - - . _ -
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' - . . ' - ~ - \\v/ RO Rpt. No. 50-302/73-12 I-l DETAILS I Prepared by: /.2/ 7/7j - M. S. Kidd', Reactor Inspector ' Dat'e . Facilities Test and Startup Branch Dates of Inspection: Decemb9r 5-7,1973 ~ - Reviewed by: [ M e :tb C. E. Murphy,rChief( Facilities -Test /Dade j and.Startup Branch - 1. Personnel Contacted
In addition to those listed in the management interview section'of the Summary of the report, tne following FPC persons were contacted: B. E. Hc'imes - Engineer, Generation Environmental and Regulatory Affairs M. H. Klineman - Director, Generation Quality and Standards D. W. East - Chemistry and Radiation Protection Engineer 2. Preoperational Environmental Monitoring Program . This unresolved item was initially discussed in R0 Report No. 50-302/73-10, ' - ' Details II, paragraph 2. The referenced report discussed certain changes to the FSAR which were needed in order that it describe the program as implemented. An example involves portions of the marine, marshland, freshwater, and terrestrial sampling programs which had been terminated. The FSAR does not speak to the early completion of. this sampling, rather it infers that the total program will continue until the operational pro- gram is begun. During the current inspection, licensee personnel stated that appropriate changes to the FSAR would be proposed to FPC management, and if approved, the changes would be submitted to the Directorate of Licensing on December 21, 1973. This matter was discussed during the management interview, at which time , the above plans were reaffirmed. The inspector stated that the item ! would rcmain open. 3. Preoperational Test Program Controls The organization and administrative controls for the Unit 3 preoperational i I test program were discussed in RO Report No. 50-302/73-10, Details I, paragraph 4. Areas of concern by RO, documented in the referenced report, were discussed again during the current inspection. It was found that (]g revisions to the Test Program Guide (TPG), and development of transition ( control and temporary test device control procedures had not yet been accomplished. .
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. , . I This subject was discussed during the management interview, .at which time the inspector stated that development of the aforementioned con- ~ trols for-testing would be carried as an unresolved item. A licenses representative stated that a draft of the transition control document , , would be available within thirty days and a draft of the temporary -{ test device control procedure within forty-five days. i '. 4. QA Program for Testing . I The QA program for the Unit 3 testing program consists of three levels; power testing personnel will perform quality control. (QC) functiuns regarding their work, GAI is to provide the independent QA audit, and Generation Quality and Standards personnel will provide quality sur- ' veillance (QS) . GAI has developed drafts of the QA procedures to be used. These are to become part of the GAI corporate QA manual which is currently being used in the construction phase at Crystal River 3.- In turn, the FPC corporate QA manual embraces the GAI manual as being part of the total quality program. The inspector performed a cursory review of the GAI QA documents and i discussed comments on them with GAI & FPC personnel. Comments included: a. Criteria for reaudits should be discussed. b. The training of QA persone_:1 shall be described, The checklist for review of test and/or operating procedures should c. be compared to Appendix C of Regulatory Guide 1.68 and ANSI N18.7 to verify that the checklist lists all the key elements of test and- operating procedures, respectively, enumerated in the referenced standards. 6 General agreement was reached on desired changes in the draft procedures. , J \\
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. y1 RO Rpt. No. 50-302/73-12 II-l
. OI DETAILS II Prepared by: M e4 (_ /2 - /7 - 23 D. p. Burke, Reactor Inspector Date Facilities Test and Startup Branch Dates of Inspection: Decembe 4-7, 1 73 - Reviewed by: / 7/h3 ' , C. E. Murphy,(Ch1 % F/ 111 ties- / Date Test and Startup Br'nch ' a ! 1. Individuals Contacted Florida Power Corporation (FPC) J. Alberdi - Nuclear Plant Superintendent P. G. Davis - Manager, Power Testing - . E. E. Froats - Supervisor, Quality and Standards 2. Preoperational Test Program As part of the preop test program review, the inspector compared FPC's index of test guides and preop test procedures against those required ' by Regulatory Guide 1.68. The following items were discussed with licensee personnel to resolve questions the inspector had concerning the program. In general, the inspector found that the licensee intends to satisfy the requirements of Regulatory Guide 1.68; specific comments by the inspector included: The lack of sys tem cleaning and flushing procedures in the program. a. FPC is currently using the " Criteria for cleaning and flushing of water filled and gas filled systems" (CC-1) document for cleaning and flushing, which does not go through the reviews and approvals that test guides or procedures require. A licensee representative stated that various system cleaning and flushing procedures will be developed, and that Table I in CC-1 will define the systems to be covered. System cleaning and flushing responsibilities have recently been transferred from the construction to the power testing group, so these procedures are in the early stages of development. b. There have been some preliminary cleaning and flushings and partial hydrotests on a few systems (demineralized water, condenser circu~ lating water system) under CC-1 and the test guides. The inspector questioned if this work would be done .over again if the test proce- dures, when issued, required it; or if the data already obtained ~ could be transferred to the new test procedure data sheets. The licensee representatives stated that CC-1 and test guide data may be attached to the test procedure as prerequisites to the procedure tests, but that the cleaning and flushing and hydro test procedures ' will be performed as required. If some of the work is redundant, as in partial and full-system hydrotests, then the work will in fact be repeated. . - .
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. c. 'Another requirement that did not appear in the test index was the Vibration Test Program. A licensee representative stated that a l vibrational test program in accordance with Regulatory Guide 1.20 I is under development and should be completed by March 1,1973.. - -1 d. The steam generator and pressurizer safety valves preop tests have not been fully defined. Licensee personnel are using Test Guide 44, ' " Pressure Relieving Devices" at present, but are undecided as to the extent of pre- and post-installation tests they will perform on the safety valves, since most of the valves are factory calibrated and ' require special testing equipment for functional testing. A licensee representative stated that the procedures will be defined when the extent of testing necessary is determined. This item will remain open. e. Since FPC decided to install Main Steam Isolation Valves (MSIV's), a licensee representative stated that preop test. procedure 27180, " Steam Supply System Turbine Stop Valves Leak Test" was deleted and 600320, " Steam Supply System Safety Valves Leak Test" was added to the test index. The representative went on to say that, in addition to 600320, a procedure will be written to operationally test the MSIV's as required. f. The procedure for testing the Auxiliary (temporary) Startup Instru- mentation for neutron response, etc. was not identified in the test index. Licensee personnel stated that they would provide for instrumentation response checks, etc. in a section of the initial fuel loading procedure, 150240. g. The vent and drain system tests in 200150, "RC System Vent and Drain Functional Test" have not been generated yet, but s licensee representative stated that they will check to see that the proce- dures identify integrity as well as instrumentation tests and that the auxiliary systems are covered as well. The tests typically verify that the vents and drains are connected and operate properly and that they will contain the system radioactive gases and fluids. h. A few of the preop procedures and test guides were reviewed and the inspector commented that occasionally, cover sheet approvals were not dated. Licensee personnel stated that they will change the procedure cover sheet to provide for the dates alongside the signatures required and will also provide for the signature of the' Plant Review Connittee (representative) so there is no question of j their review for system Class I or II procedures. The inspector i mentioned in passing, that distributing the approved test procedures on green tint paper may create some duplicating problems. During the exit management interview, licensee representatives re- affirmed their intentions to examine and/or resolve the items dis- s cussed above. Item 4, the safety valves preop tests will be carried j as an unresolved item since the scope and method of testing the valves has not been determined. . - . . . -- .-. - - _ - - -
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. . Florida Power Corporation . Crystal niver 3 DEC J B 1973 .
RO Inspection Report No. 50-302/73-12
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