ML20059C079

Notice of Violation from Insp on 931108-12.Violations Noted: Surveillance Procedure SP-182,rev 10, Reactor Bldg Structural Integrity Surveillance Program Not Implemented as Described

ML20059C079
Person / Time
Site:	Crystal River
Issue date:	12/10/1993
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20059C073	List: IR 05000302/1993027 ML20059C071 ML20059C079
References
50-302-93-27, NUDOCS 9401040358
Download: ML20059C079 (3)

Text

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ENCLOSURE 1 NOTICE OF VIOLATION Florida Power Corporation Docket No.: 50-302 Crystal River 3 License No.: DPR-72 During an NRC inspection conducted on November 8 - 12, 1993, violations of NRC requirements were identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C the violations are listed below:

A. Technical Specification 6.8.1.C requires that written procedures shall be established and implemented covering surveillance and test activities of safety related equipment.

Contrary to the above, observation of the fifth tendon surveillance inspection activities on November 9,1993, and review of quality records documenting performance of tendon surveillance inspection on November 10 and 12, 1993, disclosed that surveillance procedure SP-182, Revision 10, Reactor Building Structural Integrity Surveillance Program, was not implemented as described below:

1. Paragraph 3.2.7.a of SP-182, specifies the method, to be used to determine lift-off, is by the insertion of two (2) thin feeler gages (0.010 inch), located about 180 degrees apart between the bearing plate and the shim.

Contrary to this requirement, the liftoff determination was made '

using only one feeler gage, 0.030 inches thick, between the >

bearing plate and shim.

2. Paragraph 3.7.2.9 of SP-182, under initial conditions, requires verification that references listed in Section 2.0 of procedure SP-182 are available for use.

Contrary to this requirement, no verification was performed to verify that Reference number 2.2.2, procedure QAP-19, was available for use. Procedure QAP-19 was canceled in May, 1993, five months prior to the start of the fifth tendon surveillance.

3. Paragraph 3.7.2.13.1 of SP-182, under initial conditions, requires recording equipment and measuring devices, identification numbers and calibration due dates be recorded on Enclosure 32 of SP-182, prior to start of tendon surveillance inspections. Enclosure 32 is Data Sheet 18, Equipment Record.  ;

Contrary to this requirement, the equipment and measuring devices i used for performance of the tendon surveillance were not recorded j on Enclosure 32 prior to the start of the tendon surveillance. i i

9401040358 931210 "

PDR G ADOCK 05000302 PDR ,

4 Florida Power Corporation 2 Docket No.: 50-302 l Crystal River 3 License No.: DPR-72 i l

4. Paragraph 4.1.4.1 and 4.2.4.1 cf SP-182 requires visual inspection of the bulk filler grease used for tendon corrosiem protection, per Enclosure 4 of SP-182. Paragraph 4.1.4.2 and 4.2.4.2 of ,

SP-182 requires completion of Enclosure 16 to SP-182 (Data Sheet 3) to document inspection of the bulk filler grease.

Contrary to this requirement, the bulk filler (grease) inspection was not performed and documented on Enclosure 16 for tendon numbers 0215, 46H29, and 61V14.

5. Paragraph 3.2.4 and 3.2.5 of SP-182 define requirements for inspection " Hold Points". These requirements require inspection and acceptance of the work by the Nuclear Quality Control Inspector, and documentation of the completed inspection on Hold Point Sign Off Sheets, Enclosure 38 or 39 of SP-182. Paragraph .

4.1.7.4 specifies an inspection " Hold Point", which requires the Quality Control inspector to witness installation of new 0-rings in the end cap flanges. The hold point inspection is required to -<

be documented by signing off Step 4.1.7.4 on Enclosure 38.

Contrary to this requirement, the quality control inspector did not witness installation of the new 0-ring on November 10, 1993 in the end cap for the shop end of tendon D215. The inspector signed Step 4.1.7.4 on Enclosure 38 although he did not inspect the new 0-ring installation for this tendon.

6. Paragraph 3.2.4 of SP-182, defines procedure " Hold Points" as identifying steps beyond which work shall not proceed until an inspection is performed and the work is determined to be accepted by the Nuclear Quality Control Inspector. Paragraphs 4.1.7.5 and

' 4.2.7.5 of SP-182 specified a procedure " Hold Point" which requires checking for voids in the bulk filler in the trumpets.

Contrary to this requirement, the work required by paragraphs 4.1.7.5 and 4.2.7.5 was not completed or inspected. Work was permitted to proceed beyond this work step even though the work had not been performed or inspected for tendon numbers 61V14, 0215 and 46H29. *

7. Paragraph 4.7.10 specifies an inspection " Hold Point" for inspecting the bearing plate gasket bearing surfaces to assure that they are clean, smooth, and free of loose mill scale, rust, dirt, etc., prior to installation of the permanent end cap. The ,

" Hold Point" inspection is documented by signing Step 4.1.7.10 on Enclosure 38. ,

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Florida Power Corporation 3 Docket No.: 50-302 Crystal River 3 License No.: DPR-72 Contrary to this requirement, the Nuclear Quality Control inspcctor did not inspect the bearing plate gasket bearing surfaces prior to installation of the permanent grease cap for the shop end of tendon D215. The QC inspector signed Step 4.1.7.10 on Enclosure 38 when in point of fact he did not perform the required inspection.

This is a Severity Level IV violation (Supplement 1)

B. Technical Specification 4.6.1.6.1 requires that the containment tendons' structural integrity be demonstrated by performance of a tendon surveillance program at the end of one, three, and five years following the initial containment Structural Integrity Test, and at five year intervals thereafter. The initial SIT was performed in November,1976, therefore, the fifth containment building tendon surveillance inspection was required to be completed by the end of the 15th year following the initial SIT, which was November,1991. Inclusion of a maximum allowable surveillance extension of 25 percent in accordance with TS 4.02, required the fifth containment building tendon surveillance to be performed by January, 1993.

Contrary to the above, the fifth containment building tendon surveillance, conducted in November 1993, was not performed within the required inspection interval.

This is a Severity Level IV violation (Supplement.1)).

Pursuant to the provisions of 10 CFR 2.201, Florida Power Corporation is hereby required to submit a written statement or explanation to the U.S. {

Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C. l 20555 with a copy to the Regional Administrator, Region II, and a copy to the  !

NRC Resident Inspector at the facility that is the subject of this Notice, l within 30 days of the date of the letter transmitting this Notice of Violation '

(Notice). This reply should be clearly marked as a " Reply to a Notice of Violation" and should include for each violation: (1) the reason for the  !

violation, or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved. If an adequate reply is not received within the time specified in this Notice, an order or Demand for Information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.

Dated at Atlanta, Georgia this loth day of December 1993