ML20211P955
| ML20211P955 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/09/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20211P953 | List: |
| References | |
| NUDOCS 9909140145 | |
| Download: ML20211P955 (5) | |
Text
IT a uc 21 UNITED STATES ye g
j NUCLEAR REGULATORY COMMISSION
't WASHINGTON, D.C. 20555 4001 3%...../
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.199 TO FACILITY OPERATING LICENSE NO. DPR-51 ENTERGY OPERATIONS. INC.
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ARKANSAS NUCLEAR ONE. UNIT NO.1 l
t DOCKET NO. 50-313 1.0' INTRODUCTION l
On January 7,1994, the Nuclear Regulatory Commission (NRC) published a proposed amendment to the regulations to incorporate by reference the 1992 Edition with the l
1992 Addenda of Subsections IWE and IWL of Section X1, Division 1 of the American Society j
.of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code). The final rule, Section 50.55a(g)(6)(ii)(B) of Title 10 of the Code of Federal Regulations (10 CFR), became effective on September 9,1996, and requires licensees to implement Subsections IWE and IWL, with specified modifications and limitations, by September 9,2001.
1 In its letter of April 9,1999, as supplemented by "0CAN079901, Application for Amends to Licenses DPR-51 & NPF-6 to Change TS & Subsequent Relief Request from Post Accident Sampling Requirements of NUREG-0737.TS Administrative Control requirements,[[NUREG" contains a listed "[" character as part of the property label and has therefore been classified as invalid. & RG 1.97,rev 3,affected|letter dated July 14,1999]], Entergy Operations, inc. (the licensee), submitted an amendment to the Technical Specifications (TSs) for Arkansas l
. Nuclear One, Unit 1 (ANO-1). The proposed changes revise the licensee's TS so that it i
conforms to the new regulatory requirements. The majority of the changes involve deletion of i
the existing requirements for tendon surveillance and substituting inspection in accordance with the requirements of the ASME Code,Section XI, Subsection IWL and 10 CFR 50.55a(g)(6)(ii)(B). The licensee has also proposed a change to the reporting requirements.
l The licensee's program incorporating Subsection IWE has not been completed and is not l
included in its submittal.
The "0CAN079901, Application for Amends to Licenses DPR-51 & NPF-6 to Change TS & Subsequent Relief Request from Post Accident Sampling Requirements of NUREG-0737.TS Administrative Control requirements,[[NUREG" contains a listed "[" character as part of the property label and has therefore been classified as invalid. & RG 1.97,rev 3,affected|July 14,1999, letter]] provided clarifying information that did not change the scope of the April 9,1999, application end the initial proposed no significant hazards consideration determination.
l The licensee proposes the following changes to its current TS:
l Change 1 The TS Table of Contents and Lists of Figures have been updated to reflect the j
' changes made to ANO-1 specifications relevant to the submittals.
I Change 2 Terminology used in TS 3.6.1, its action statement, and the Objective of Specification 3.6 have been revised to permit the inclusion of additional requirements beyond those defined in TS 1.7, " Reactor Building."
Enclosure 9909140145 990909 PDR ADOCK 05000313 P
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2 Change 3 -
The footer on Page 80 of the TSs has been modified to inform the user that several of the following pages have been deleted.
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. Change ~4 -
The specific surveillance criteria of TS 4.4.2 has been deleted from the specifications and incorporated in ANO-1's containment inspection program.
Change 5 Figures 4.4.2-1,4.4.2-2, and 4.4.2-3 have been deleted from the specifications 1
and relocated to ANO-1's containment inspection program.
Change 6 The requirements of TS S.12.5.a have been deleted. Reporting requirements associated with this program are incorporated in the containment inspection program.
Change 7 -
TS 6.12.4 has been added to the Administrative Controls section of the TSs. It
- states the reporting requirements associated with the ANO-1 containment inspection' program.
Change 8 The Bases for TS 3.6 have been revised to clarify the reactor building inspection evaluation requirements.
The adequacy of the proposed changes are discussed below.
. 2.0 EVALUATION Chance 1 The TS Table of Contents and Lists of Figures have been updated to reflect the changes made to ANO-1 specifications relevant to the submittals. These changes are editorial, consistent with j
the technical changes, and therefore, acceptable.
Chance 2 Terminology used in TS 3.6.1, its action statement, Objective of Specification 3.6, and its associated Bases, have been revised to permit the inclusion of additional requirements beyond those defined in TS 1.7," Reactor Building." The terminology of this section has been changed from." maintaining' reactor building integrity" to stating that the " reactor building shall be operable.". By doing this, the requirements of structural integrity are included in addition to the requirements of maintaining the integrity of the reactor building. This is acceptable because it clarifies the requirements of this section.
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Chance 3
- The footer on Page 80 of the TSs has been modified to inform the user that several of the following'pages have been deleted. This editorial change is acceptable, i
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' Chances 4 and 5 The' specific surveillance criteria of TS 4.4.2, including Figures 4.4.2-1,4.4.2-2, and 4.4.2-3, have been deleted from the specifications and incorporated into the ANO-1 containment -
inspection' program. Included in TS 4.4.2 are:
e TS 4.4.2.1, Tendon Surveillance i This specification requires testing of 21 tendons at 1,3,'and 5-year intervals.
Successful completion of these tests allow decreasing the required number of tendons
~ tested per interval to nine. The licensee has completed testing of the 21 tendons at the 1,3, and 5-year intervals as evidenced by its letters of September 11,1975, October 4,1977, and August 22,1979. The remaining requirements of this specification were modified to comply with the requirements of Subsection IWL of the ASME Code,
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10 CFR 50.55a(g)(6)(ii)(B), and 50.55a(b)(2)(ix). These requirements are contained in ANO-1's containment inspection program.
The requirements of TS 4.4.2.1 have either been fulfilled or are redundant to the requirements contained in Subsection IWL,10 CFR 50.55a(g)(6)(ii)(B), and 50.55a(b)(2)(ix). Therefore, deletion of this specification is acceptable.
e TS 4.4.2.1.1, Lift Off This specification states that lift off readings shall be taken for all surveillance tendons.
This requirement is redundant to the requirements contained in Subssetion IWL,
'10 CFR 50.55a(g)(6)(ii)(B), and 50.55a(b)(2)(ix). Therefore, deletion of this specification
. is acceptable.
.TS 4.4.2.1.2, Wire inspection Testing e
This specification describes the required testing of wires from surveillance tendons and also the applicable anchor assemblies. This requirement is redundant to the requirements contained in Subsection lWL,10 CFR 50.55a(g)(6)(ii)(B), and 50.55a(b)(2)(ix). Therefore, deletion of this specification is acceptable.
TS 4.4.2.1.3, Acceptance Criteria, and Figures 4.4.2-1,'4.4.2-2, and 4.4.2-3 e
- In this specification, the acceptance criteria for reactor building post tensioning system is listed. Figures 4.4.2-1,4.4.2 2, and 4.4.2-3 are directly incorporated into the containment inspection program. The requirements of Subsection IWL and 10 CFR 50.55a(g)(6)(ii)(B) encompass the intent of this specifica. tion and provide greater detail in stating the acceptance criteria. Therefore, deletion of this TS is acceptable.
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TS 4.4.2.2, inspection Interval and Reports This specification describes the requirements for the inspection interval and states that a i
special report be submitted within 90 days from completion of the inspection. Both of these requirements are addressed in either Subsection lWL or IWA,10 CFR L
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. 50.55a(g)(6)(ii)(B), and 50.55a(b)(2)(ix). Because of the redundancy, deletion of this
- specification is acceptable.-
TS 4.4.2.3, End Anchorage Concrete Surveillance This specification describes the interval and locations for inspection of the end anchorages of the surveillance tendons and adjacent concrete surface. The requirements associated with this specification have been fulfilled and no longer pertain to current testing regulations. Therefore, deletion of the TS is acceptable.
TS 4.4.2.4, Liner Plate Surveillance This specification describes the examination of the liner plate prior to the initial pressure test. The requirement for liner plate surveillance is included in Subsection IWL, 10 CFR 50.55a(g)(6)(ii)(B), and 50.55a(b)(2)(ix). Therefore, deletion of the TS is acceptable.
Chanaes 6. 7. and 8 The licensee proposes to delete the requirements of TS 6.12.5.a,"Special Reports, Tendon Surveillance," and add the requirement, TS 6.12.4, " Reactor Building Inspection Report." TS 6.12.4 addresses the reporting requirements for the containment building inspection surveillance. The licensee proposes that degradations that exceed the acceptance criteria of 10 CFR 50.55a(b)(2)(ix) or Subsection IWL will be reported to the NRC within 30 days upon completion of the engineering evaluation. The Bases for TS 3.6 have been revised to require any resulting engineering evaluation be performed within 60 days of completion of the containment building inspection surveillance. The combination of TS 6.12.4 and the Bases to TS 3.6 will ensure that a report on the condition of the reactor building structure and any corrective actions that are required as a result of the inspection, is submitted to the NRC within 90 days. This is acceptable. However, approval of the proposed TS changes does not relieve the licensee of its responsibility to report, pursuant to 10 CFR 50.73(a)(2)(ii), any event or condition that results in the condition of the nuclear power plant being seriously degraded.
These conditions include serious degradation of the containment concrete structure, such as dome delamination, multi-wire or ancnor head failures, and widespread corrosion of the liner plate.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Arkansas State official wat utified of the proposed issuance of the amendment. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility j
component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no
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' significant hazards consideration, and there has been no public comment on such finding (64 FR 27320 dated May 19,1999). The amendment also changes recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and (c)(10). Pursuant to i
10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Approval of the proposed TS changes does not relieve the licensee of its responsibility to report, pursuant to 10 CFR 50.73(a)(2)(ii), any event or condition that results in the condition of the nuclear power plant being seriously degraded. These conditions include serious degradation of the containment concrete structure, such as dome delamination, multi-wire or anchor-head failures, and widespread corrosion of the liner plate.
Principal Contributor: M. Kotzalas Date: September 9, 1999
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