ML20006D671
| ML20006D671 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 01/11/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20006D669 | List: |
| References | |
| NUDOCS 9002140215 | |
| Download: ML20006D671 (5) | |
Text
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NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D. C. 20555
%,,,,,]SAFETYEVALUATIONBYTHE.0FFICE.0FNUCLEAR.REACTORREGULATIO i
BALTINORE-GAS AND. ELECTRIC. COMPANY t&
CALVERT. CLIFFS NUCLEAR. POWER. PLANT.. UNITS 1 AND.2 l
00CKET NOS. 50-317 and.50-318 SECOND. TEN-YEAR. INTERVAL. INSERVICE. INSPECTION PROGRAM. PLAN-
1.0 INTRODUCTION
TechnicalSpecification(TS)4.0.5forCalvertCliffsNuclearPowerPlant, Units 1 and 2, states that the surveillance requirements for Inservice Inspection and Testing of the American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel-C. ode Class 1, 2, and 3 components shall be applicable as follows:
Inservice Inspection of ASME Code Class 1., 2, and 3 components shall be performed in accordance with Section XI of the ASME Code andapplicableAddendaasrequiredby10CFR50.55a(g),exceptwherespecific 1
written relief has been granted by the Comission purusant to 10 CFR 50.55a(g)(6)(1)..
' Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (includingsupports)shallmeettherequirements,exceptthedesignand.
access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI, " Rules for Inservice Inspection of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations L
require that-inservice examination of components and system pressure tests-
. conducted during the second ten-year interval shall comply with the L
requirements in the latest edition and addenda of Section XI of the ASME Code incorporated ty reference in 10 CFR 50.55a(b) on the date twelve months prior to the start of the 120-month inspection interval, subject to the limitations
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and modifications listed therein. The components (including supports) may meet the requirements set forth in subsequent editions and addenda of the ASME Code incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein.
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,n' l Pursuant to-10 CFR 50.55a(g)(5), if the licensee determines that conformance with an examination requirement of Section XI of the ASME Code is not practical for his facility, information shall be submitted to the Comission l
in support of that determination and a request made for relief from the ASME I
Code requirement. After evaluation of the determination, pursuant to I'
10 CFR 50.55a(g)(6)(1), the Comission may grant relief and may impose alternative requirements that are determined to be authorized by law, will' not endanger life or property or the comon defense and security, and are
-otherwise in the public interest, giving due consideration to the burden upon.
the licensee that could result if the requirements were imposed.
l The Licensee, Baltimore Gas and Electric Company, has prepared the Calvert i
Cliffs Nuclear Power Plant, Units 1 and 2, Second Ten-Year Interval Inservice l-Inspection (ISI) Program Plan to meet the requirements of the 1983 Edition, Sumer 1983 Addenda of Section XI of the ASME Boiler and Pressure Vessel Code, e> cept.that the extent of examination for Code Class 2 piping welds has been determined by ASME Code Case N-408 as allowed by Regulatory Guide 1.147. The staff, with technical assistance from its Contractor, the Idaho National l
Engineering Laboratory (INEL), has evaluated the Second Ten-Year Interval
. Inservice Inspection Program Plan, additional information related to the Program Plan, and the request for relief from certain ASME Code requirements determined to be impractical for Calvert Cliffs Nuclear Power Plant, Units 1 and 2, during the second inspection interval. This evaluation was provided in the Technical Evaluation Report EGG-MS-8403 dated July 1989.
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2.0 EVALUATION The ISI Program Plan has been evaluated for (a) application of the correct Section XI Code edition and addenda, (b) compliance with examination and test requirements of Section XI, (c) acceptability of the examination
-sample, (d) compliance with prior ISI commitments made by the Licensee, (e) correctness of the application of system or component examination exclusion criteria, and (f) adequate information in support of requests for relief from impractical Section XI Code requirements. The staff has determined that the Licensee's ISI Program Plan reflects compliance with the requirements listed above. However, it is noted-that the Containment Spray and Shutdown Cooling systems, including the associated integrally. welded attachments,'have been exempted from surface and volumetric examinations based on the wall thickness criteria contained in Code Case N-408.
Paragraph 10 CFR 50.55a(b)(2)(iv) requires that ASME Code Class 2 piping welds in the Residual Heat Removal, Emergency Core Cooling and Containment lieat Removal-systems be 1
examined. These systems shall not be completely exempted from inservice volumetric and surface examination based on Section XI exclusion criteria contained in IWC-1220 or in Code Case N-408. The Licensee must perform an examination of a sample of the Class 2 piping welds in the above mentioned systems which have been exempted from surface and volumetric examinations based on the wall thickness criteria in Code Case N-408.
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The information provide by the Licensee in support of requests for relief from requirements determined to be impractical has been evaluated and the bases for granting relief from those requirements are documented in the attached INEL Technical Evaluation Report EGG-MS-8403. We concur with the findings and recommendations contained in the subject report. Table 1 presents a surrrnary of the reliefs requested and the status of the requests as determined by the staff.
3.0 CONCLUSION
The staff concludes that the Calvert Cliffs Nuclear Power Plant, Units 1 and 2, Second Ten-Year Interval inservice Inspection Program Plan with the additional information provided and the specific written relief constitutes the basis for compliance with 10 CFR 50.55a(g) and TS 4.0.5 and is therefore acceptable. However, it is required that the licensee upgrade the Program Plan to include volumetric and surface examinations of a representative sampling of Class 2 piping welds in the Containment Spray.and Shutdown Cooling systems.
Additionally, based on the review summarized herein, the staff concludes that the reliefs granted and the alternative examinations imposed through this document provide reasonable assurance that the acceptable level of quality and i
safety intended by the ASME Code will be satisfied.
The staff has determir:9d L
that the requirement associated with the reliefs requested are impractical to l
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perform _and, pursuant to 10 CFR 50.55a(g)(6)(i), that granting these reliefs L
is authorized by law and will not endanger life or property or the connon defense and security and is otherwise in the public interest considering the v
burden:that could result if the requirements were imposed on the facility.
Principal Contributor:
G. Johnson Dated:
January 11, 1990
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