IR 05000413/1980004
| ML19323C187 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/27/1980 |
| From: | Maxwell G, Rausch J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19323C170 | List: |
| References | |
| 50-413-80-04, 50-413-80-4, 50-414-80-04, 50-414-80-4, NUDOCS 8005150116 | |
| Download: ML19323C187 (6) | |
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UNITE 3 STATES
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NUCLEAR REGULATORY COMMISSION
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3 560 Report Nos. 50-413/80-04 and 50-414/80-04 Licensee: Duke Power Company P. O. Box 33189 Charlotte, NC 28242 Facility Name:
Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 License Nos. CPPR-116, CPPR-117 Inspection at Catawba site near Rock Hill, South Carolina Inspector:
3 77-4 G. F. Maxwe
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Date Signed Approved by:
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W f - / 7 ' ['6 ausch,A/tingSectionChief,RCESBranch Date Signed SUMMARY Inspection on February 19-29, 1980 Areas Inspected This routine, resident inspection involved 50 inspector-hours on site inspecting in the areas of storage of reactor vessels, welding of safety related piping, preparation for and transporting of steam generators, review of inspection records, installation of Unit 2 reactor vessel and fire prevention / protection.
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Of the"six areas inspected, no items of noncompliance or deviations were identi-fied in five areas; one apparent item of noncompliance was found in one area (Deficiency-Failure to identify a nonconforming condition, paragraph 6.d).
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DETAILS 1.
Persons Contacted Licensee Employees
- R.
L. Dick, Vice-President of Construction
- D. G. Beam, Project Manager W. O. Henry, Quality Assurance Manager of Construction
- D. L. Freeze, Project Engineer
- R. A. Morgan, Senior QA Engineer
- E. C. Wall, General Superintendent
- L. R. Davison, Senior QC Engineer
- 0. W. Sealy, Technical Specialty Steam Production E. H. Lecroy, Night Superintendent T. W. Hullette, Engineering W. I. Reardon, Engineering C. M. Helton, Senior Site Safety Assistant R. David, Safety Engineer P. M. McLamb, Foreman l
J. N. Turner, QC Mechanical Superviosr C. Z. Bearden, QC Mechanical Inspector J. R. Hendricks, Senior Engineer Design Engineering Other Organizations Hartford Steam Boiler Inspection and Insurance Company
- J. W. Kosko, Authorized Nuclear Inspector (ANI)
- C. F. Toegel, ANI
- Attended exit interview (s)
2.
Exit Interview The: inspection scope and findings were summarized on February 22 and 29, 1980 with those persons indicated in paragraph I above.
3.
Licensee Action on Previous Inspection Findings
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Not inspected.
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4.
Unresolved Items
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Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve noncompliance or devia-j tions. A new unresolved item identified during this inspection is discussed
in paragraph 9.b.
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5.
Lifting and Transporting of Unit 2 Steam Generators J
c The inspector observed the transporting of steam generator no. 1924 a.
j for Loop 4.
The steam generator was placed onto the transporter and j
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secured according to the Provisions of Duke's Construction Procedure CP-198. All aspects of the transportating operation observed were in accordance with CP-198.
b.
The inspector observed the installation of the lifting trunnions for steam generator no. 1923 for loop 1, observed the torquing of the fastening and QC inspecting of the fastening bolts for the trunnion numbered "4a".
All aspects of the installation were observed to be in accordance with Duke's Construction Procedure CP-189 and Westinghouse Technical Manual No. CNM 1201-01-106 Section 4, paragraph 4.2.
The inspector also observed that the torque wrench (No. CA-5) which was used for fastening had been recently calibrated.
In the areas inspected no items of noncompliance or deviation were identified.
6.
Duke's Surveillance of the Unloading and Setting'of Unit 2 Steam Generators Nos. 1921 and 1922 The inspector examined Duke's Surveillance Report for the Unloading, a.
Transpotting and Setting of NSSS vessels (Steam Generators No. 1922-loop 2 and No. 1921-loop 3), dated 2-6-80; as a result the following were noted:
(1) The surveillance report indicated that steam generator No. 1922 has one of its hold down bolts stuck in the half in position.
Per direction from Duke's Design Civil Engineering (verbally)
construction attempted to remove the " stuck bolt" by applying a 2000 ft/lb.
torque to the bolt; this effort proved unsuccessful.
(2)
10 CFR 50 Appendix B, Criterion XV, the Duke Power Company Catawba Nuclear Station FSAR Chapter 17.1 (and therefore the Duke Power Company Topical Report, DUKE-1 Amendment 3, Section 17.1.15) are
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not being met. These require that nonconforming nuclear safety-l related materials, parts or components be identified segregated or otherwise controlled in such a manner that the item will not be used, and will be reported to the department originating the specification in accordance with established procedures for
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review and ultimate disposion. The nonconforming condition identified in 6.a(1) involving the " stuck bolt" in Steam Generator No. 1922 was not reported to the department originating the specification in accordance with the established procedure Q-1, revision 12 titled " Control of Nonconforming Items".
Paragraph 4.1 of Procedure Q-1 states in part:
"Any person discovering a aonconforming it'em..~.shall initiate form Q-la...as soon as possible".
b.
The inspector discussed the above condition with the Duke Senior QA Engineer. He indicated that it is normal site practice to properly document nonconforming conditions and that part of the corrective action would be to review previously documented Duke QA Surveillance
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Reports to assure that similar conditions have not been overlooked by the QA department. Duke committed to documentation of this nonconfor-mance as required by procedure Q-1 revision 12.
c.
Subsequently the inspector was:
(1) Provided a copy of a nonconformancc report which properly documents the unsatisfactory condition, concerning che " stuck bolt"; providing compliance with procedure Q-1, revis4.on 12 paragraph 4.1 (2) Provided an attendance list showing that on February 22, 1980 that site QA personnel were reminded of the reporting requirements of Q-1.
(3) Assured by the Senior QA Engineer that previously documented surveillance reports have been " screened" and do not contain unsatisfactory conditions which have not been properly documented through the use of the Q-1A form.
d.
The inspector informed the licensee that this condition as identified on February 21, 1980 was an item of noncompliance (a deficiency);
however that since sufficient corrective action has been taken prior to the completion of this inspection a written response will not be required (413/80-04-01; 414/80-04-01).
Except as noted no items of noncompliance or deviation were idectified.
7.
Safety-Related Piping (Welding) - Unit I The inspector selected, for observation, a weld which was being repaired.
a.
The weld no. INS 56-11 is located in Unit 1 Containment Spray System; depicted on Duke drawing CNIN 556 revision 0.
The following was observed:
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(1) The work was conducted in accordance with a " weld data sheet".
(2) The required welding procedures were available for the welders
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use.
(3) The base metals, welding filler materials and gases were as specified.
(4) The welder's qualifications were current for the process being applied.
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(5) The shielding gas for the process being used was in accordance with the applicable welding procedure (L-252 revision 4).
b.
The inspector observed an "inprocess" weld being made on an auxiliary feedwater system subassembly. The weld joint, identified as ICA 117-2
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Class C, was identified on the " weld data" sheet as a butt weld on a 4" CS (P-1) pipe; the referenced drawing CN-1CA-117 also depicted the pipe as 4 inch CS, Class C. The inspector examined the records of the welders who were involved in making the weld and established that each had current qualifications for the process being used.
In the areas inspected no items of noncompliance or deviation were identified.
8.
Reactor Vessel Installation - Units 1 and 2 During the proceeding inspection period (week of February 11, 1980)
a.
the inspector observed that the reactor vessel for Unit I had its head not properly protected. Subsequently, the inspector observed that the vessel is now properly protected and that the new storage requirements for the vessel have been established.
b.
Reviewed the storage and maintenance inspection records for Unit 2 reactor vessel (head and "0" rings) and interviewed the responsible Duke QC mechanical inspector. The QC inspector demonstrated that he was cognizant of the applicable inspection requirements and the records indicate that the inspections have been conducted at the prescribed frequencies (per Duke form P-3A, revision 7, serial no. M-121, rev. O,
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sheet 1).
Observed no visible signs of damage to the head and noted that the closures were properly intact.
Observed the transferring of Unit 2 reactor vessel by the use of the c.
jacking frame onto the vessel transporter, all of the transferring and securing operations appeared to be in accordance with Duke's Construction Procedure CP-198, revision 1.
d.
Observed the seating of two of the four Unit 2 reactor vessel support shoes onto their supports. Observed the presence of a Duke QC mechanical inspector, who was verifying that a proper seating occurred.
e.
On February 28, 1980 the inspector observed that Westinghouse personnel directed site personnel in the installation of Unit 2 reactor vessel
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lifting head, the vessel was then transported into Unit 2 reactor
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building.
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In the areas inspected no items of noncompliance or deviations were identified.
9.
Fire Prevention / Protection - Units 1 and 2
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l a.
The inspector examine'd the most recent records relative to implementation of Duke's procedure CP-37, revision 3 and interviewed the senior site safety assistant and others; as a result noted.
(1) The training sessions are not being held on a conthly basis for the members of the fire brigade; a requirement of Duke's procedure CP-37, revision 3 paragraph 7.3.A.
The inspector was informed i
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that since the project has attained a new insurance company that
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the practice of conducting monthly training sessions has not occurred and that present plans include revising CP-37 to require quarterly training sessions instead. The records indicate that a training sessions was held on November 13, 1979 and it was preceeded by another training session on July 31, 1979.
(2) The weekly inspections on the QA records vault Fenwan Halon 1301 fire supression system has not been conducted since November 9, 1979, as required per Duke's procedure CP-37, revision 3 paragraph 9.1.
A and procedure SQAP-1A titled " Site QA Procedure SQAP-1 i
Honitoring of Fire Supression System Pressure Guages" (approved 6-7-78).
The inspector also noted that a quarterly check of the Halon system pressure was conducted on 12-27-79.
The quarterly
inspection required checking the pressure to assure that it was less than 325 pounds at 70 degrees F, checking hardware tightness, visual inspection and testing the system alarms. The weekly inspection required checking the system pressure to determine whether or not it has varied significantly (+ 20 pounds).
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(3) The weekly inspection of the fire main and hydrant valves have not been conducted; a requirement of Duke's procedure CP-37, revision 3, paragraph 9.1.B.
The inspector informed the licensee that they had failed to follow work and inspection instructions for fire protection and prevention as com-mitted to by Duke's Topical Report, Regulatory Guide 1.39, ANSI 45.2.3 and Duke's construction procedure C-37.
Although the inspections and training required by procedure C-37 are not considered safety related during the construction phase, adherence will be emphasized as the plant nears the operational phase.
b.
Prior to and during the exit interview, on February 29, 1980 the Senior QA Engineer informed the inspector that the following steps of corrective action have been initiated for resolving the above listed unsatisfactory conditions:
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(1) Construction Procedure CP-37 has been revised to reflect the current inspection practices approved by Duke's Fire Protection
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Insurance Company, i.e., inspection and training will be preformed to new frequencies.
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(2) Inspections _of the, fire suppression system for the QA vault have been re-assigned to the technical group and will be performed on the frequency specified in procedure SQAP-1A.
(3) In order to assure compliance with these above two commitments; QA will initiate a Strveillance checklist for Duke's Fire Protection
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-6-e Program which will include construction plant requirements as defined in ANSI N45.2.3.
The implementation date for this check-list will be March 15, 1980.
This item will be an unresolved item and identified as 413/414/80-04-02,
" Failure to follow work and inspection instructions for fire protection and prevention".
The inspector, accompanied by the senior safety assistant toured c.
various site. Work areas; inspected the contents of one of the portable fire trailers and observed satisfactory operation of one of the site fire hydrants; some of the conditions which were observed included:
(1) Adequate control combustible forms, form lumber, and scaffolding.
(2) Adequate control of flammable liquids.
(3) Fire extinguishers were located sufficiently close to areas in which cutting and welding operations were occurring.
(4) Fire extinguishers displayed current inspection indications.
In the areas inspected no items of noncomplian. or deviations were identified.
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