ML19308D615

Tech Spec Change Request 14 Re Tech Specs 3.6 & 4.6,revising Surveillance Program for Monitoring Containment Dome

ML19308D615
Person / Time
Site:	Crystal River
Issue date:	11/23/1977
From:	FLORIDA POWER CORP.
To:
Shared Package
ML19308D614	List: ML19308D613 ML19308D615
References
TAC-13056, NUDOCS 8003050809
Download: ML19308D615 (7)

Text

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- Technical Sprcification Change Reouest No.14 Replace pages 3/4 6-9a, 3/4 6-9b, 3/4 6-9c, 3/4 6-9d and B 3/4 6-2 with the attached revised pages 3/4 6-Qa. 3/4 6-9b, 3/4 6-9c, 3/4 6-9d, 3/4 6-9e and B 3/4 6-2.

Procosed Change Revise Specification 4.6.1.6.4 to be Specification 4.6.1.6.5 and insert Specification 4.6.1.6.4 Containment Dome as per the attached pages.

Revise the final sentence of Bases Specification 3/4.6.1.6 to read: "The measurement of containment tendon lift off force, the visual and met-allurgical examinations of tendons, anchorages and liner, the measurement of dome elevation differences and cracks, the general visual inspection of the dome and the Type A leakage tests are sufficient to demonstrate this capability."

Reason for Proposed Change In accordance with Magraph 2.C.(8) of Amendment No.1 to the Crystal River Unit 3 Nuclear Generating Plant Facility Operating License No.

OPR-72, FPC submitted a proposed surveillance program for monitoring the containment #qee to detect any future delamination en May 10, 1977. The NRC subseq uatly approved the surveillance program on May 31, 1977 and requested that FPC submit changes to the Facility Operating License Appendix A Technical Specifications. This Change Request incorporates the approve.d surveillance program into the Technical Specifications.

Safety Analysis Justifying Proposed Change I Florida Power Corporation and the NRC have concluded that the proposed surveillance program for monitoring the containment dome (which provides .

a system for measuring the vertical movement of the dome and mapping of I crack widths and crack patterns) at periodic intervals can determine l that the condition of the structure is within acceptable limits. Therefore, the incorporation of this surevillance program into the CR #3 Technical Specifications does not involve an unreviewed safety question.

i 800sogg & f

. CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) .

4. 6. i . 6 '. 2 End Anchcraces and Adjacent Concrete Surfaces The structural integrity of tne end anchorages of all tencons inspected pursuant to Specification 4.6.1.6.1 and the adjacent concrete surfaces shall be demonstrated by cetermining through inspection that no apparent changes have occurred in the visual appearance of the end anchorage of the con-crete crack patterns adjacent to the end anchorages. Inspections of the concrete shall be performed during .the Type A containment leakage rate tests (reference Specification 4.6.1.2) while the containment is at the maximum test pressure.

4 . 6.1. 6 . 3 Containment Surfaces The structural integrity of the exposed accessible interice arc exterior-surfaces of the containment, including the liner plate, shall be determined during the shutdcwn for each Type A containment leakage rate test (reference Specification 4.6.1.2) by a visual inspection of these surfaces and verifying no apparent changes in appearance or other abncrmal degradation.

4.6.1.6.4 Containment Dcme The containment dece's structural integrity shall ba demonstrated at tne end of 1 year,18 months, 2 years, 3 years, 40 +10 months (coincident with the first periodic integrated containment leali rate test), and 5 years following the initial containment structural integrity test. The dome's structural integrity shall be demonstrated by:

a. Measuring the elevation difference of 7 dome survey points {l at the apex; 3 at a radius of =29 feet at azimuths 900, 215 and 3340, and 3 at a radius of =49 feet at azimuths 900, 2150 )

and 3340) and 3 benchmarks (on Ring Girder at azimuths 900, '

215o and 3340) along with respective azimuths. These elevation differences shall be ccmpared to the elevation differences estaM ished by the Baseline Survey. If the containment is in )

a normal operation / shutdown mode, the acceptable change in '

cnange in elevation differences will be based on consideration I of expected movement and survey accuracy coupled with an acceptalaie strain level for the radial reinforcement. Changes of a greater magnitude shall require an engineering evaluation.

If the containment is in a pressurized mode for a periodic containment integrated leak rate test, the acceptable changes in elevation differences will be similar to that for the initial containment structural integrity test applied to the elevation differences during the periodic centainment integrated leak rate test.

CRYSTAL RIVER - UNIT 3 3/4 6-9a

. CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)'

.b. Measuring crack widths and plotting crack patterns in the area of the dome 3 feet on either side of azimuths 1950 from the apex to the Ring Girder. Cracks wider than 0.010 inches will be plotted and cracks wider than 0.040 inches shall require an engineering evaluation. In addition, a general visual inspection of the entire dome surface area shall be performed.

4.6.1.6.5 Recorts Any abnormal degradation of the containment structure detected during the above. required tests and inspections shall be reported to the Commission pursuant to specification 6.9.1. This report shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedure, the tolerances on cracking, and the corrective actions taken.

l CRYSTAL RIVER - UNIT 3 3/4 6-9b l

r

. CONTAINMENT SYSTEMS

-~

BASES 3/4.6.1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that 1) the containment structure is prevented from exceeding its design negative pressure differential with respect to the outside atmosphere of 3.0 psig and 2) the containment peak pressure does not exceed the design pressure of 54.6 psig during LOCA conditions.

The maximum peak pressure obtained from a LOCA event is 49.6 psig. The limit of 3 psig for initial positive containment pressure will limit the total pressure to 52.6 psig which is less than the design pressure and is consistent with the safety analyses.

3/4.6.1.6 AIR TEMPERATURE The limitations on containment average air temperature ensure that the overall containment average air temperature does not exceed the initial temperature condition assumed in the accident analysis for a LOCA.

3/4.6.1.6 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the facility. Structural integrity is required to ensure that the containment will withstand the maximum pressure of 52.6 psig in the event of a LOCA. The measurement of containment tendon lift off force, the visual and metallurgical examinations of tendons, anchorages and liner, the measurement of dome elevation differences and cracks, the general visual inspection of the dome, and the Type A leakage tests are sufficient to demonstrate this capability.

CRYSTAL RIVER - UNIT 3 B 3/4 6-2

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