ML20127B216
| ML20127B216 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Calvert Cliffs |
| Issue date: | 02/03/1984 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20127A737 | List:
|
| References | |
| FOIA-84-794 NUDOCS 8402170240 | |
| Download: ML20127B216 (9) | |
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7590-01 46
.o3 h.h,44 UNITED STATES NUCLEAR REGULATORY COMMISSION
, f\\0 BALTIMORE GAS AND ELECTRIC COMPANY E 8 9
DOCKET N05. 50-317 AND 5--318
~ NOTICE OF CONSIDERATION OF ISSUANCE OF AMEN 0MENTS TO FACILITY OPERATING LICENSES AND PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION AND OPPORTUNITY FOR HEARING The U. S. Nuclear Regulatory Connission (the Conmission) is considering issuance of amendments to Facility Operating License Nos. DPR-53 and DPR-69, issued to Baltimo're Gas and Electric Company (the licensee), for operation of the Calvert Cliffs Units 1 and 2 located in Calvert County, Maryland.
The amendments would revise Limiting Conditions for Operation and Surveil-lance Recuirements for the Control Element Assembly (CEA) Position Indicator channels. These changes would allow expanded use of the " full-in" or " full-out" electrical limit switches to provide indication of CEA position in accordance with the licensee's application for amendment dated September 20, 1983.
Before issuance of the proposed license amendment, the Commission will l
have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Connission's regulations.
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The Commission has made a proposed determination that the amendment request involves no significant hazards consideration.
Onder the Commission's regulations in 10 CFR 50.92, this-means that operation of the facilities in accordance with the proposed amendments would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.
The Limiting Conditions for Operation and Surveillance Requirements for the the Control Element Assembly (CEA) Position Indicator Channels are ad-dressed in Calvert Cliffs Units 1 and 2 Technical Specification (TS) 3/4 1.3.3. At the present time, TS 3/4.1.3.3 allows partial " credit" for full-in or full-out CEA position indication in that, with one CEA position indicating channel per CEA group inoperable, reactor operation may continue provided that the affected CEA position is verified via the full-1,n or full-out electrical limit reed switches. -The proposed TS changes would allow expandeil credit for these electrical limit reed switches by (1) reorganizing TS 3.1.3.3 to incor-porate the full-in and full-out reed switch position indicating channels as one of three CEA position indicating means, (2) allow any CEA to have two of i
l threo operable CEA position indicating means, and (3) provide surveillance requirements in TS 4.1.3.3 for the two CEA position indicating means which are l
being utilized.
As indicated previously, three means of CEA position indication are provided.
Each control rod drive mechanism at Calvert Cliffs Units 1 and 2 is provided with
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a reed switch system which provides positive indication of control rod insertion The reed switch CEA position indication system utilizes a series of status.
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~ magnetically actuated reed switches, spaced at 2-inch intervals along the CEA housing and arranged with precision resistors in a voltage divider network, to provide voltage signals proportional to CEA position.
These signals are dis-played in bar chart form by a. cathode ray tube (CRT) on the main control board.
A logic cackage associated with the CRT provides redundant alarm functions.
A backup readout is provided which can be utilized to read the output of any reed switch voltage divider. The collection of position indicating reed switches for CEA is referred to as a reed switch position indicating channel.
In addition to the position indicating reed switches placed at 2-inch intervals, additional reed switches are located at the " full-out and " full-in" CEA positions.
These reed switches provide verification of full-out/ full-in status on a core mimic which is located on the main control panel.
The third means of CEA position'in-dication, referred to as " pulse counting" displays a numerical readout of the reouested CEA position. At the present time, TS 3.1.3.3 allows " credit" for the full-out or full-in reed switches.
Upon failure of up to one position indicating reed switch channel per CEA group, TS 3.1.3.3 allows power operation to continue provided that the positions of the associated CEAs are periodically verified via the full-out or full-in reed switches.
The Basis for TS 3.1.3.3 states, in part, "The. CEA " full-In" and " Full-Out" limits provide an additional independent means for detemining the CEA positions when the CEAs are at either their fully inserted or 'ully withdrawn positions. Therefore, the ACTION statements applicable to in-operable CEA position indicators permit continued operations when the positions of CEAs with inoperable position indicators can be verified by the " Full-In" or " Full-Out" limits."
The effect of the proposed TS change is to allow the position of any CEA, with an inoperable CEA position indicating channel, to be verified by the two remaining ocerable position indicating means.
The existing Bases for TS 3/4/1.3.3 O
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recognize all three CEA position indicating means, pulse counting, reed switch stacks, and full-in/ full-out electrical limits, to be acceptable means for CEA position indication.
The present restriction on use of the full-in/ full-out electrical limits to single CEA per CEA group,is unnecessary in that each CEA position is determined individually.
- Thus, the distinction with regard to CEA group is unnecessary in that each CEA, regardless of group assignment, is required to have at least two indepen-dent means of CEA po'sition indication.
Since each control rod is provided with rundant means of position indication, the margin of safety with regard to indication of accidentally misaligned control rods has not been reduced.
In addition, chapter 14 of the Calvert Cliffs FSAR considers a number of accidents that result from misaligned CEAs.
Since a high degree of certainty exists with regard to CEA position, neither the probability nor consequences of these accidents will increase.
In addition since no changes will be made to plant equipment design or operating. conditions no'new or different types of accidents will occur. Accordingly, the Commission proposes to determine that the procosed changes to TS 3/4.1.3.3 involve no significant hazards considera-tion.
The Commission is seeking public comments on this proposed determination.
Any ccmments received within 30 days after the date of publication of this notice l
will be considered in making any final determination.
The Commission will-not normally make a final determination unless it receives a request for a hearing.
Ccmments should be addressed to the Secretary of the Commission, U.S.
Muc' ear Regulatory Commission, Washington, D.C.
20555,' Attn:
Docketing and Service Branch.
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By March 12,1984
, the licensee may file a request for a hearing with respect to issuance o.f the amendments to the subject facility operating licenses and any person whose interest may be affected by this proceeding and who wishes to participate as a party in the proceeding must file a written petition'for leave to intervene.
Request for a hearing and petitions for leave to intervene shall be filed in accordance with the Commission's " Rules of Practice for Domestic Licensing Proceedings" in 10 CFil Part 2.
If a request for a hearing or petition for leave to intervene is filed by the above date, the Comission or an Atomic Safety and Licensing Board, designated by the Comission or by the Chairman of the Atomic Safety and Licensing Board Panel, will rule on the request and/or petition and the Secretary or the designated Atomic Safety and Licensing Board will issue a notice of hearing or an appro-priate order.
As required by 10 CFR 92.714, a ' petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, and how that interest may be affected by the results of-the proceeding.
The petition should specifically explain the reasons why intervention should be pemitted with particular reference to the following factors: '(1)'the nature of the cetitioner's right under the Act to be made a party to the proceeding; (2) the nature and extent of. the petitioner's property, financial, or other interest in the proceeding; and (3) the possible effect of any order which may be entered in the proceeding on the petitioner's interest.
The petition should also identify the specific aspect (s) of the subject matter of the croceedino as to which petitioner wishes to intervene.
Any person who has 9
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i 4 filed a petition for leave to intervene or who has been admitted as a party may amend the petition without requesting leave of the Board up to fifteen (15) days prior to the first prehearing conference scheduled in.the proceeding, but such an amended petition must satisfy the specificity requirements described above.
Not later than' fifteen (15) days prior to the first prehearing conference scheduled in the preceeding, a petitioner shall file a supplement to the petition to intervene which must include a list of the contentions which are sought to be litigated in the matter, and the bases for each contention set forth with reasonable specificity. Contentions shall be limited to matters within the scope of the ' amendments under consideration. A petitioner who fails to file such a supplement which satisfies these requirements with respect to at least one contention will not-be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the cocortunity to participate fully in the conduct of the hearing, including the ooportunity to present evidence and cross-examine witnesses.
If a hearing is requested, the Commission will make a final determination on the issue of no significant hazards consideration. ' The final determina-tion will serve to decide when the hearino is held.
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. If the final determination is that the amendment request involves no significant hazards consideration, the Commission may issue the amendments and make them effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of the amendments.
If the final determination is that the amendment involve a significant' nazards 'onsideration, any hearing held would take place before the issuance c
of the amendment.
Normally, the Commission will not issue the amendments until the expir-ation of the 30-day notice period.
However, should circumstances change during the notice period such that failure to act in a timely way would result, for example, in derating or shutdown of the facilities, the Commission may issue the license amendments before the expiration of the 30-day notice period, provided that its final determination is that the amendments involve no significant hazards consideration.
The final determination will consider all oublic and State comments, received.
Should the Commission take this action, it will publish a notice of issuance and provide for opportunity for a hearing after issuance.
The Commission expects that the need to take this action will occur very infrequently.
A recuest for a hearing or a petition for leave to intervene must be
'iled with the Secretary of the Commission, U.S. Nuclear Regulatory Commission,
' Washington, D.C.
20555, Attention:
Docketing and Service Branch, or may be delivered to the Commission's Public Document Room,1717 H Street, N.W.
Washington, D.C., by the above date.
Where petitions are filed during the last ten (10) days of.the notice period, it is requested that the petitioner promptly so inform the Commission by a toll-free telephone call to Western Union at (800) 325-6000 (in Missouri (800) 342-6700).
The Western Union operator should be given Datagram Identification Number 3737 and the following nessage addressed to Mr. J. Miller:
petitioner's name and telephone number; date petition was mailed; plant name; and publication date and page number of this FEDERAL REGISTER notice. A copy of the petition should also'be sent to the Executive Legal Director, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, and to George F. Trowbridge, Esq., Shaw, Pittman, Potts, and Trowbridge 1800 M Street, N.W., Washington, DC. 20036, attorney for the licensee.
Nontimely filings of petitions for leave to intervene, amended petitions, sucolerental petitions and/or requests for hearing wf11 not be entertained absent a determination by the Commission, the presiding officer or the Atomic Safety and Licensing Board designated to rule on the petition and/or request, that the petitioner has made a substantial showing of good cause for the granting of late petition and/or request.
That determination will be based uoan a balancing of the factors specified in 10 CFR 2.714(a)(1)'(i)-(v) and 2.714(d).
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9 For further details with respect to this action, see the September 20, 1983 application for amendment which is available for public inspection at the Commission's Public Document Room, 1717 H Street, N.W., Washington, D.C.,
and at the CalVert County Library, Prince Frederick, Maryland.
Dated. at Bethesda, Maryland this 3rd day, of February,1984.
FOR THE NUCLEAR REGULATORY COMMISSION
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'/James R. Miller,. Chief Operating Reactors Branch #3 Division of Licensing
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