ML19340A783
| ML19340A783 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 04/20/1977 |
| From: | Knop R, Shafer W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19340A782 | List: |
| References | |
| 50-010-77-06, 50-10-77-6, 50-237-77-06, 50-237-77-6, 50-249-77-06, NUDOCS 8009030825 | |
| Download: ML19340A783 (8) | |
See also: IR 05000010/1977006
Text
{{#Wiki_filter:. _ _ _ _ . ,. - . 4 UNITED STATES NUCLEAR REGUI.ATORY CO5!!!ISSION OFFICE OF INSPECTION AND ENFORCE!!ENT REGION III - . Report of Operations Inspection IE Inspection Report No. 050-010/77-06 IE Inspection Report No. 050-237/77-06 IE Inspection Report No. 050-249/77-06 Licensee: Commonwealth Edison Company P.O. Box 767 Chicago, IL 60690 Dresden Nuclear Power Station License No. DPR-2 Units 1, 2, and 3 License No. DPR-19 Morris, IL License No. DPR-25 Catego ry : C , Type of Licensee: BWR (GE) 200 & 800 MWe Type of Inspection: Routine Announced - Dates of Inspection: April 4-7, 1977 ,? C b* ' f lO"
- ) , {' / ,. y
Principal Inspector: W.'D Shafer I . /'- (Date) Accompanying Inspectors: None Other Accompanyfng Personnel: None -> " ' l C X / -r -{ / '//2/ 7 Reviewed By: R. C. Knop, Chief ' s Reactor Projects Section 1 (Date) ! . 1 ' g 8 0 0 9 0 !)0 ('~ 535 255-~ s . ,
. s- 1 . SUMMARY OF FINDINGS , 4 Inspection Summary Inspection April 4-7. 1977, (Unit 1, 77-06) (Unit 2, 77-06) (Unit 3, 77-06): Review of calibrationn (Units 2 and 3), IE Bulletine and Circulars (Units 1, A and 3), quality control functions (Units 1 and 3) and special Technical Specification report requirements (Units 2 and 3) . One item of noncompliance was identified, relating to calibration of undervoltage emergency bus relays on Units 2 and 3. Enforcement Items Infraction Contrary to Technical Specifications Section 4.2, calibration of the under voltage emergency bus relays were not accomplished during the refueling outages occurring in 1976 cc. Units 2 and 3. The licensee's Operation Analysis Department last calibrated these relays early in ,1975. (Paragraph 2.c, Report Details) Licensee Action on Previously Identified Enforcement Items None reviewed. _ Other Significant Items A. Systems and Components None. B. Facility Items (Plans and Procedures) None. C. Managerial Items None. D. Deviations None. E. Status of Previously Reported Unresolved Items None. , , -2- l
. _ _ _ . , Management Interview On April 7,1977, at the conclusion of the inspection, an interview was conducted with Mr. Stephetson, Plant Superintendent and other licensee ' ~ representatives. The int.pector stated the following: A. The calibration of :he under voltage emergency bus for Units 2 and 3 is required at ec.ch refueling outage. This calibration was not accomplished duriig the last Units 2 and 3 refueling outage and is an item of noncoe.pliance. The licensee sticed that the calibrations will be completed; Unit 3, prior to startup and Unit 2, at the next shutdown. , The inspector cautioned the licensee to make certain that the calibration is conducted in accordance with proper procedure, acceptance criteria and supervisory approval. B. All other areas of the inspection were discussed. (Paragraphs 3, 4, and 5, F.eport Details)
. . "M d' -3- ! r - .
_ - . . . . . . REPORT DCTAILS 1. Persons Contacted , B. Stephenson, Station Superintendent A. Rcberts, Assistant Superintendent B. Shelton, Administrative Assistant C. Sargent, Technical Staff Supervisor , D. Farrar, Assistant Technical Staff Supervisor i E. Budzichowski, Operating Engineer, Unit 1 N. Scott, Lead Operating Engineer R. Ragan, Operating Engineer, Unit 3 D. Adam, Radiation Chemistry Supervisor J. Dolter, Leading Nuclear Engineer J. Kolanowski, Operating Engineer, Unit 2 J. Reardanz, Quality Assurance Operations F. Paulikas, Quality Assurance Engineer D. Schildgren, Quality Assurance Engineer B. Saunders, Security R. Kyrouac, Quality Control Engineer R. Thomas, Instrument Foreman . R. Campbell, Instrument Foreman J. Eenigenburg, Maintoaance Engineer R. Coen, Quality Cor. trol Inspector F. Petrusich, Quality Control Inspector R. Nimmer, Engineer Assistant ~ R. Dyer, Engineer Assistant R. Falbo, Assistant Office Supervisor J. Martin, Engineer R. Mirochna, Engineer D. Maxwell, Engineer Assistant H. Waclaw, Engineer Assistant 2. Calibration of Instrumentation (Units 2 and 3) a. A review was conducted of the licensee's calibration program relating to Technical Specification identified calibration 4 requirements. The following instrument calibrations were reviewed: DIS 1600-10, Containment Pressure DIS 1700 /, Reactor Vent and Fuel Pool Alarms DIS 1500-3, Containment Spray Interlock .. -4- , I . I
y . . , 9 ,
DIS 1600-2, liigh Drywell Pressure Scram DIS 201-1, Reactor Pressure 600 psig Bypass Scram Protection . DIS 700-4, IRM Upscale and Inop Scram DIS 500-6, Condenser Low Vacuum (No Procedure available), Undervoltage Emergency Bus DIS 2300-7, Steam Tunnel High Temperature b. The review consisted of verifying established frequencies, use of proper procedures (including review and approval, acceptance criteria and detailed stepwise instructions), personnel quali- fications and the use of calibration instruments with proper certification to recognized standards. No concerns were identi- fled in this area. In reviewing the calibration requirements for the undervoltage c. emergency bus, the inspector determined that the licensee's Op'erational Analysis Department have calibrated these relays ' every two years; the last calibration having taken place in 1975. However, the licensee's Technical Specifications specify the . frequency for this calibration as each refueling outage. A refueling outage for Units 2 and 3 was conducted in 1976, however. - , the under voltage emergency bus calibration was not accomplished. , The inspector informed the licensee that failure to calibrate the above described instruments within :.he specified frequency is contrary to Technical Specifications Section 4.2 and is an item of noncompliance. The licensee acknowledged the noncompliance and stated that Unit 3 undervoltage emergency bus calibration will be accomplished prior to resumption of operation on April 10, 1977. The Unit 2 under- voltage relays will be calibrated at the next shutdown of greater than 36-hours duration. No other concerns were identified. 3. Review of Correspondence (Units 2 and 3) The following special reports, required by the licensee's Technical Specifications, were reviewed onsite to determine accuracy of the content. No significant concerns were identified, 103-77, B. B. Stephenson to J. C. Keppler, dated a. s. / 16, 1977, relating to inservice inspection of piping l l 1 -5- .: -
.. . - - - .. . . . and components within the primary pressure boundary which are outside the downstream containment isolation valvu. t b. Letter No. 104-77, B. B. Stephenson to J. G. Keppler, dated ~ February 16, 1977, concerning the five-year evaluation of the Dresden Unit 2 inservice inspection program. c. Letter No. 102-77, B. B. Stephenson to J. G. Keppler, dated February 12, 1977, relating to the evaluation of the Dresden Unit 2 main steam tunnel leak detection system. d. Letter No. 173-77, B. B. Stephenson to J. G. Keppler, dated
March 7, 1977, relating to Dresden Unit 2 leakage detection system. Letter No. 804-76, B. B. Stephenson to J. G. Kepoler, dated e. November 18, 1976, relating to secondary containment leak rate tests. f. Letter No . 790-76, B. S. Stephenson to ., . G. Keppler, dated i November 8, 1976, concerning the Dresden Unit 3 reactor coolant leakage detection system. . g. Letter No. 805-76, B. B. Stephenson to J. G. Keppler, dated November 15, 1976, relating to the Dresden Unit 3 main steam tunnel leak detection system. 4. Review of Bulletins and Circulars (Units 1, 2, and 3) ~ The inspector reviewed the licensee's response 1/ to IE Bulletin a. No. 76-07, 'trane Hoist Control - Circuit Modifications" to verify prompt reporting, dissemination of information and proper corrective action. Verification included record review and discussions with licensee personnel. No concerns were identified. The inspector reviewed the licensee's response 2/ to IE b. Circular No. 76-07, " Inadequate Performance by Reactor Operating and Support Staff." The following concerns were identified: (1) The licensee's response stated that station quality control personnel periodically survey operating and support staff activities. Through record review the inspector determined that while QC surveillance was conducted in 1976, no regular periodic surveillance program is now being accomplished. Two surveillances were condu' ted in 1976; one in July relat- ing to operations and one in 3ecember relating to fire protection. 1/ Letters, Abrell to Keppler, dated 8/13/76 and 1/19/77. 2/ Letter, Bolger to Keppler, dated 2/17/77. -6- p. . . f I
- -- - - - . . . .. The licensee stated that while no requirement exists to have the QC department conduct periodic surveillance, it is desirabic f rom a management viewpoint. A QC surveil- lance program will be established. ~ (2) A review of the licensee's security site access records indicated that upper levels of station management are not making random backshift visits to monitor station operations. The licensee stated that the lack of backshift monitoring was an oversight on the part of station management; it was assumed that the extra time spent on site by management personnel was adequate to satisfy the production department policy. Station management will begin to conduct random backshift and weekend visits to monitor operations and support staff activities. , 5. Quality Control (Units 1, 2, and 3) The inspector reviewed the licensee's quality control group to determi.ne the extent of compliance to the licensee's quality assur- ' ance program. The following areas were reviewed: a. Procedures: The quality control group does not operate under . internal procedures generated specifically for QC functions. Directions for the QC group are identifiable directly from the - licensee's quality procedures manual, administrative procedures and check lists. No significant concerns were identified. b. Training: The licensee has an ongoing program of formal training for QC personnel. The program elevates personnel to " test observer" status with respect to ultrasonic testing, mag particle testing and liquid penetrant testing. Actual testing is accomplished by qualified personnel. On the job training (0JT) for QC personnel is informal in that no records of OJT are maintained by direct supervision. The QC supervisor stated that new personnel a?e assigned work under the cognizance of a more experienced person until the supervisor feels that the new person has sufficient training, c. Safety Related Work Requests: A review was made of the quality control group interface with safety related work requests generated at the site. T'he inspector noted that many of the safety related work requests completed in 1976 were inadequately . - 7-
- - w. . . processed in that the QC group did not in all cases review and release the work as identified in Quality Procedure 3-52. A licensee represenative stated that this noncompliance had been identified by the quality control group and corrective action _ implemented as of January,1977. To verify this statement the ' iaspector reviewed selected work requests compl,cted 1977 and determined that a corrective program has been implemented. The licensce was informed the item of concern appears to have been identified and properly corrected, tio further action in this area will be required at this time. , .
6 a i ~8- (* ? 1 }}