ML20199E719
| ML20199E719 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 01/29/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20199E694 | List: |
| References | |
| NUDOCS 9802020235 | |
| Download: ML20199E719 (3) | |
Text
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UNITED STATES i
e NUCLEAR REGULATOMY COMMISSION i
WA9HINGToN. D.c. 3000He01 1
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SAEEIY_EVALVATIONEY THilof_FICLDENUCLEAR_REACLT_OAREG.ULATION 1
- tELATED TO AMkNDMENT No. 99 TO FACILITY OoERATING LICENSE NO. NPF 37.
1 6hs;tpdENT NO M TO FACILITY QEE86I1NG U.GENAE.NO lff.:AR, i
S fitdQ M gliT A90
- PF 72.
AND AMSNDegygA 90 TO FACILITY OPERATING LICENSE NO. NPF 77 CoMucMyiEALTMDisORCOM2AMi BYR_ON STATION. UNIT NOS.1 AND 2 BRAIDWOOD STATION. UNIT NOS.1 AND 2 5
DOCKET NOS. STN 50-454. STN 50-455. STN 50 456 AND S~N 50-457 1.0 lNTRODUCTION By letter dated June 17,1997, as supplemented November 26,1997, and January 9,1998, Commonwealth Edison Company (Comed, the licensee) submitted a request to revise the Technical Specification (TG) surveillance requirements related to the containment vessel structural integrity for Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2. The November 26,1997, and January 9,1998, letters provided additional clarifying information that did not change the staff's initial proposed no significant hazards considerations tJetermination.
The contsinments of the four units are built of post tensioned prostressed concrete. The licensee proposed the revision to (1) comply with the new requirements to 10 CFR 50.55a published in the August 8,1996, Feders/ Register, which endorses the use of Subsection lWL of the 1992 Edition and the 1992 Addenda of the American Society of Mechanical Engineers i
(ASME) Code,Section XI, with five additional modifications specified in 10 CFR 50.55a(b)(2)(lx),
and (2) relocate the amended TS requirements to the Containment Vessel structural Integrity -
Program (CSVIP) and reference that praram in the affected limiting conditionr. for operation and bases. The CSVIP is under licensee control and gives the various requirements to be met. The proposed changes also include the addition of the CSVIP in the administrative controls section of the TS and the addition of a new section to the reporting requirements in the administrative controls section of the TR delinesting the necessary reports.
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2.0 BACKGROUND
Section 182a of the Atomic Energy Act (the Act) requires applicants for nuclear power plant operating licenses to include TS as part of the license. The Commission's mgulatory requirements related to the content of TS are set forth in 10 CFR 50.36. That regulation requires that tha TS include items in five specific cate9ories: (1) safety limits, limiting safety system settings and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; and (5) administrative controls, and states also that the m* 18E! N&
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Commission may include such additional TS as it Ands to be appropriate. However, the regulation does not specify the particular requirements to be included in a plant's TS.
l 10 CFR 50.36 6dentifies four ortleria to be used in determining whether a particular matter is j
required to be included in the TS, as follows: (1) installed instrumentation that it, used to detect, i
and indicate in the control room, a significant abnormal degredation of the reactor coolant j
pressure boundary; (2) a process variable, design feature, or operating restriction that is an initial
,ondition of a desigtwbasis sooident or transient analysis that either assumes the failure of or presents a challenge to the integetty of a fission product barrier; (3) a structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a desierkbasis sooident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier; and (4) a structure, system, or component which operating experience egrobabilistic safety assessment has shown to be significant to publ6c health and safety. As a resuN, existing TS requirements that fall within or satisfy any of these orlieria must be reteMed in the TS, while those TS requirements that do not fall within or satisfy these criteria may f a relocated to other licensee-controlled documents.
3.0 EVALUATION The staff has reviewed the proposed revision to the TS related to containment vessel structural integrity. The staff finds the elements contained in the revised TS to be acceptable due to the following requirements: (1) containment structural integrity will be maintained via the provision of proposed TS 4.6.1.6, (2) the CVSIP, including its frequency of inspection and acceptance 4
criteria, is in accordance with 10 CFR 50.55a(b)(2)(vi), and (3) abnormal degradation detected through the CVSIP will be reported to the NRC along with a statement of the corrective actions taken. The CVSIP should incorporate, in a suitable form, the guidance necessary for the i
licensee to perform the tendon surveillance and report the resuNs to the NRC. In accordance with the requirements of 10 CFR 50.55a(g)(6)(li)(B)(5), the CVSIP siements and the required documentation shall be maintained on site for NRC audit.
Comed proposed a change to the reporting requirements for abnormal degradation of the j
ooatainment structure that is detected during the swvel!!srcos. The current TS requires a report i
within 15 days if abnormal degradation is detected, while the proposed TS requires a report within 30 days. This change from 15 days to 30 days for notification does not affect the plant safety margins and is consistent with Section 5.6.9 of NUREG 1431, ' Standard Technical Specifications for Westinghouse Plants,' and the toporting requirements in 10 CFR 50.73.
Therefore, the staff finds this change acceptable.
The staff also concludes that the above-relocated requirements relating to the containment vessel structural integrity are not required to be in the TS under 10 CFR 50.36, and are not required to obviate the possibility of an abnormal situation or ovent giving rise to an immediate 4
threat to the public health and safety. Accordingly, the staff concludes that the proposed changes a o acceptable and that these requirements may be relocated from the TS to the CVSIP.
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4.0 STATE CONSULTATION
in accordance with the Commission's regulations, the lilinois State offlaial was notified of the proposed issuance of th6 emendmen'.s. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments chan0e a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and change surveillance requirements. Tht NRC staff has determined that the amendments involve no significant incrosse 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 pre 'lously issued a proposed finding that the amendments invol.e no signl@: ant hazards consideration, and there has been no public comment on such finding (62 FR 66397), Accordingly, the amendments meet the eligibility ortleria for categorical exclusion set foni;in 10 CFR 51.22(c)(9) These amendments also involve changes in recorditeeping, reporting, or administrative procedures or requirements.
Accordingly, with respect to these items, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10), Pursuant to 10 CFR 51,22(b), no environmental impact statement or environmental assessment need be prepared in connection w6th the issuance of the amendments.
6.0 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 amendments will nnt be inimical to the common defense and security or to the health and safety of the public, Principal Contributor: 'C. Tan S. Bailey Date: January 29, 1998
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