ML20235G571
| ML20235G571 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 02/14/1989 |
| From: | Mcneil S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235G573 | List: |
| References | |
| NUDOCS 8902230298 | |
| Download: ML20235G571 (8) | |
Text
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7590-01 UNITED STATES NilCLEAR REGULATORY COMMISSION BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE AND PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION AND OPPORTUNITY FOR HEARING The U. S. Nuclear Regulatory Commission (the Connission) is considering.
issuance of an amendment to Facility Operating License No. DPR-69, issued to the 8altimore Gas and Electric Company (the licensee), for operation of the Calvert Cliffs Nuclear Power Plant, Unit No. 2, located in Calvert County, Maryland.
The amendment would make the following changes in accordance with the licensee's application for amendment dated October 14, 1988:
1.
Modify Technical Specification (TS) Surveillance Requirement 4.7.8.1.c by extending the surveillance interval for snubber functional tests beyond the current maximum interval of 18 months plus 25%. This proposed extension would be for 54 days or prior to entry into Mode 4 following the Unit 2 Cycle 9 refueling outage, whichever comes first. This extension is a one-time request.
2.
Correct nomenclature errors in TS 3/4.7.8, " Snubbers."
3.
Delete an obsolete note in TS 4.7.8.1 which states that "The steam generator snubbers 2-63-11 through 2-63-26 need not be functionally tested until the refueling outage following June 30, 1985."
Before issuance of the proposed license amendment, the Commission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations.
8902230298 890214 l
DR ADOCK 05000318 PDC
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The Consnission has made a proposed determination that the amendment I
requested involves no significant hazards considerations. Under the Commission's regulations in 10 CFR 50.92, this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability of a new or different kind of accident from any 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 licensee evaluated the proposed changes against the standards in 10 CFR 50.9? and has determined that the amendment would not:
(1) involve a significant increase in the probability or consequences of an accident previously evaluated...
l Since 1978, the licensee has functionally tested 413 snubbers on Units 1 and 2, with only 3 test failures. This corr'esponds to a failure rate of approximately 0.7% over a period of greater than 10 years. The licensee is requesting, in Change 1, a surveillance interval extension of up to 54 days for snubber functional tests required by TS 4.7.8.1.c.
This extension is needed primarily for the snubbers required to be operable during cold shutdown and refueling operations, because the TS allowable surveillance interval (18 months plus 25%) expires at approximately the same date that Unit 2 is is scheduled to be shut down for refueling.
Due to the types of snubbers, those required for modes 5 and 6 only, and to the short length of the requested extension, the probability or consequences of any accidents previously evaluated would not increase significantly as a result of this proposed change to the snubber function test surveillance interval.
m.__
l Changes 2 and 3 are strictly administrative in nature in that they
- 1) correct several nomenclature errors in TS 3/4.7.8 (TS 4.7.8.1.b and 4.7.8.1.d were referred to as TS 4.7.8.b and 4.7.8.d in several places in the body of the TS) and 2) delete an obsolete note to TS 3/4.7.8 wMeh permitted the functional testing of several steam generator snubbers to be deferred until the refueling outage following June 30, 1985. Consequently, Changes 2 and 3 do not involve any increase in the probability or consequences of any previously evaluated accident.
(ii) create the possibility of a new or different type of accident from any accident previously evaluated...
4 Since these proposed changes do not alter any plant operations, other than the snubber functional test surveillance interval, maintenance requirements, or system design or functions, no possibility of creating a new or different l
I type of accident would result from the proposed changes.
(iii) involve a significant reduction in a margin of safety...
As the only consequence of this extension in the snubber function test surveillance interval is the very slight degradation in snubber functionality that might occur over this short period (54 days) with the plant in cold shutdown, the reduction in any margin of safety provided for the plant would not be significant.
No margins of safety are affected by the proposed administrative changes.
On March 6, 1986, the NRC published guidance in the-FEDERAL REGISTER (51 FR 7751) concerning examples of amendments that are not likely to involve a significant 1
4_
hazards consideration. Changes 2 and 3 are consistent with the example provided:
"(i) a purely administrative change to the Technical Specifications:
for example,...a change in nomenclature...."
l Based upon the above, the NRC staff proposes to determine that the changes requested to TS 3/4.7.8 " Snubbers," involves no significant hazards consideration.
By March 20, 1989, the licensee may file a request for a hearing with respect to issuance of the amendment to the subject facility operating license 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. Requests for a hearing and petitions for leave to intervene shall be filed in accordance with the Comission's " Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2.
If a request for a hearing or petition for leave to intervene is filed by the above date, the Commission 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 reouest and/or petition and the Secretary or the j
i designated Atomic Safety and Licensing Board will issue a notice of hearing j
1 cr an appropriate order.
As required by 10 CFR 2.714, a petition for leave to intervene shall set i
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 permitted with particular reference to the following factors:
(1) the nature
l
- of the petitioner'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 proceeding as to which petitioner wishes to intervene.
Any person who has 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 proceeding, a petitioner shall file a supplement to the petition to intervene, which must include a list of the contentions that are sought to be liticated 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 amendment under consideration. A petitioner whc 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 opportunity to participate fully in the conduct of the hearing, including the opportunity to present evidence and cross-examine witnesses.
__._.___1
If a hearing is requested, the Comission will make a final determination on the issue of no significant hazards consideration. The final determination will serve to decide when the hearing is held.
If the final determination is that the amendment reouested involves no significant hazards considerations, the Commission may issue the amendment and make it effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of the amendment.
If the final determination is that the amendment requested involves significant hazards considerations, any hearing held would take place before the issuance of any amendment.
Normally, the Commission will not issue the amendment until the expiration 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 facility, the Comission may issue the license amendment before the expiration of the 30-day notice period, provided that its final determination is that the amendment involves no significant hazards considerations. The final determination will consider all public and State coments received.
Should the Commission take this action, it will publish a notice of issuance and provide for opportunity for a hearing after issuance. The Comission expects that the need to take this action will occer very infrequently.
A request for a hearing or a petition for leave to intervene must be filed with the Secretary of the Comission, U. S. Nuclear Regulatory Comission, Washington, DC 20555, Attention:
Docketing and Service Brant.h,
____-_-__m_____________-__.m_2___________
I 1
or may be delivered to the Commission's Public Document Room, Gelman Building, 2120 L Street, N.W., Washington, DC, by the above date. Where petitions are l
filed during the last ten (10) days of the notice period, it is reouested that the petitioner promptly so infonn the Comission 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 message addressed to Robert A. Capra: 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 Office of the General Counsel, U. S. Nuclear Regulatory Commission, Washington, DC 20555, and to D. A. Prune, Jr.,
General Counsel, Baltimore Gas and Electric Company, P. O. Box 1475, Baltimore, Maryland 21203, attorney for the licensee.
Nontimely filings of petitions for leave to intervene, amended petitions, supplemental petitions and/or requests for hearing will not be entertained absent a determination by the Comission, 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 a late petition and/or request. That determination will be based upon a balancing of the factors specified in 10 CFR 2.714(a)(1)(1)-(v) and 2.714(d).
1
E e
- For further details with respect to this action, see the application for amendment which is available for public inspection at the Commission's Public Document Room, 2120 L Street, N.W., Washington, DC 20555, and at the Local Public Document Room, Calvert County Library, Prince Frederick, Maryland.
Dated at Rockville, Maryland, this 14th day of February 1989.
FOR THE NUCLEAR P.EGULATORY COMMISSION W
Scott Alexander McNeil, Project Manager Project Directorate I-1 Division of Reactor Projects I/II
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- PDI-l[V N M NAME. :CVogan n
- SMcNeil. r :RCapra DATE :2/\\W/89
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- P//4/89 i
OFFICIAL RECORD COPY l
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l February 14, 1989 I-LDocket No. 50-318 DISTRIBUTION Docket file NRC PDR i
l Local PDR DHagan l-Glainas ACRS(10)'
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l Mr. G. C. Creel GPA/PA BBoger l
P Vice President - Nuclear. Energy CVogan PDI-1 Rdg Baltimore Gas and Electric Company SMcNeil LTripp, RI Calvert Cliffs Nuclear Power Plant 4
MD Rtes. 2 and 4
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Post Office Box 1535 Lusby, Maryland 20657 t
j
Dear Mr. Creel:
l
SUBJECT:
CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO. 2 - NOTICE OF CONSIDERATIONOFISSUANCEOFAMENDMENT(TACNO.71025)
Enclosed is a copy of a " Notice of Proposed No Significant Hazards
)
1 Consideration Determination and Opportunity for Hearing" for your J
information. This Notice relates to your October 14, 1988 application which j
requested a one-time extension, beyond the currently allowed maximum surveillance interval of 18 months plus 25%, for conducting snubber functional tests specified in Technical Specification 4.7.8.1.c.
This proposed extension would be for 54 days or prior to entry into Mode 4 following the Unit 2 Cycle 9 refueling outage, whichever comes first. 'This Notice was published as an
" Individual Notice" rather than a "Bi-weekly Notice" to support your operation cycle and ensure a full 30-day notice period before issuance of any amendment.
]
Sincerely.
ORIGINAL SIGNED BY Scott Alexander 3:Neil, Project Manager
)
Project Directorate I-1 j
Division of Reactor Projects I/Il
^
Enclosure:
Notice cc: See next page
[10/14/88 EXTENSIONREQUEST) s OFC :PDI-I
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NAME :CVogan Q
- SMcNeil:v
- RCapra ]
DATE : S/6/89
- a/l'4/89
- "L/ l L/89 UttICIAL Mt.LUKU LUPT
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Mr. G. C.. Creel Raltimore Gas & Electric Company Calvert Cliffs Nuclear Power Plant cc:
Mr. William T. Bowen, President Calvert County Board of Commissioners
. Prince Frederick, Maryland 20768 D. A. Brune, Esq.
General Counsel Baltimore Gas and Electric Company P. O. Box 1475 Baltimore, Maryland 21203 Mr. Jay E. Silberg,'Esq.
Shaw, Pittman, Potts and Trowbridge 1800 M Street, NW Washington, DC 20036 Mr. W. J. Lippold, General Supervisor Technical Services Engineering Calvert Cliffs Nuclear Power Plant MD Rts 2 1. a, P. O. Box 1535 Lusby, Maryland 20657 Resident Inspector
'c/o U.S. Nuclear Regulatory Commission P. O. Box.437 Lusby, Maryland 20657 Department of Natural Resources Energy Administration, Power Plant Siting Program ATTN: Mr. T. Magette Tawes State Office Building Annapolis, Maryland 21204 Regional Administrator, Region I U.S. Nuclear Regulatory Comission 475 Allendale Road King of Prussia, Pennsylvania 19406 I
7590-01 UNITED STATES NtlCLEAR REGULATORY COMMISSION BALTIMOPE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE AND PROPOSED NO SIGNIFICANT HAZARDS C0NSIDERATION DETERMINATION AND OPPORTUNITY FOR HEARING The U. S. Nuclear' Regulatory Commission (the Commission) is considering i
issuance of an amendment to Facility Operating License No..DPR-69, issued to the Baltimore Gas and Electric Company (the licensee), for operation of the Calvert Cliffs Nuclear Power Plant, Unit No. 2, located in Calvert County, Maryland.
The amendment would make the following changes in accordance with the licensee's application for amendment dated October 14, 1988:
l
.1.
Modify Technical Specification (TS) Surveillance Requirement 4.7.8.1.c by
{
1 extending the surveillance interval for snubber functional tests beyond the current maximum interval of 18 months plus 25%. This proposed
]
extension would be for 54 days or prior to entry into Mode 4 following the Unit 2 Cycle 9 refueling outage, whichever comes first. This extension is a one-time request.
2.
Correct nomenclature errors in TS ?/4.7.8, " Snubbers."
3.
Delete an obsolete note in TS 4.7.8.1 which states that "The steam generator snub'bers 2-63-11 through 2-63-26 need not be functionally tested until the refueling outage following June 30, 1985."
Before issuance of the proposed license amendment, the Commission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations.
?!D;23O M
. The Coumission has made a proposed determination that the amendment requested, involves no significant hazards considerations. Under the Comission's regulations in 10 CFR 50.92, this means that operation of the fac11 Ey in accordance with the proposed amendment would not (1) involve a significant increase in the probability of a new or different kind of accident from any 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 licensee evaluated the proposed changes against the st6ndards in 10 CFR 50.9? and has determined that the amendment would not:
(1) involve a significant increase in the probability or consequences of an accident previously evaluated...
Since 1978, the licensee has functionally tested 413 snubbers on Units 1 and 2, with only 3 test failures. This corr'esponds to a failure rate of approximately 0.7% over a period of greater than 10 years. The licensee is requesting, in Change 1, a surveillance interval extension of up to 54 days for snubber functional tests required by TS 4.7.8.1.c.
This extension is needed primarily for the snubbers required to be operable during cold shutdown I
and refueling operations, because the TS allowable surveillance interval (18 months plus 25%) expires at approximately the same date that Unit 2 is is scheduled to be shut down for refueling.
Due to the types of snubbers, those required for modes 5 and 6 only, and to the short length of the requested extension, the probability or consequences of any accidents previously evaluated would not increase significantly as a result of this proposed change to the snubber function test surveillance interval.
l
4 4 Changes 2 and 3 are strictly administrative in nature in that they
- 1) correct several nomenclature errors in TS 3/4.7.8 (TS 4.7.8.1.b and 4.7.8.1.d were referred to as TS 4.7.8.b and 4.7.8.d in several places in the body of.
the.TS) and 2) delete an obsolete note to TS 3/4.7.8 which permitted the functional testing of several steam generator snubbers to be deferred until the refueling outage following June 30, 1985. Consequently, Changes 2 and 3 do not involve any increase in the probability or consequences of any previously evaluated accident.
(ii) create the possibility of a new or different type of accident from any accident previously evaluated...
Since these proposed changes do not alter any plant operations, other than the snubber functional test surveillance interval, maintenance requirements, or system design or functions, no possibility of creating a new or different type of accident would result from the proposed changes.
(iii) involve a significant reduction in a margin of safety...
As the only consequence of this extension in the snubber function test surveillance interval is the very slight degradation in snubber functionality that might occur over this short period (54 days) with the plant in cold shutdown, the reduction in any margin of safety provided for the plant would not be significant.
No margins of safety are affected by the proposed administrative changes.
On March 6, 1986, the NRC published guidance in the FEDERAL REGISTER (51 FR 7751) concerning examples of amendments that are not likely to involve a significant 1
a i hazards consideration. Changes 2 and 3 are consistent with the example provided:
"(1) a purely administrative change to the Technical Specifications:
for example,
...a change in nomenclature...."
Based upon the above, the NRC staff proposes to determine that the changes requested to TS 3/4.7.8, " Snubbers," involves no significant hazards consideration.
By March 20, 1989, the licensee may file a request for a hearing with respect to issuance of the amendment to the subject facility operating license 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. Requests 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 CFR Part 2.
If a request for a hearing or petition for leave to intervene is filed by the above date, the Commission 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 reouest and/or petition and the Secretary or the designated Atomic Safety and Licensing Board will issue a notice of hearing or an appNoriate order.
As required by 10 CFR 2.714, 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 permitted with particular reference to the following factors:
(1) the nature
of the petitioner'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 proceeding as to which petitioner wishes to intervene. Any person who has 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 proceeding, a petitioner shall file a supplement to the petition to intervene, which must include a list of the contentions that are sought to be litioated in the matter, and the bases for each contention set forth with reascnable specificity. Contentions shall be limited to matters within the scope of the amendment 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 es a party.
Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intorvene, and have the opportunity to participate fully in the conduct of the hearing, including the opportunity 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 determination will serve to decide when the hearing is held.
If the final determination is that the amendment reauested involves no significant hazards considerations, the Commission may issue the amendment and make it effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of the amendment.
If the final determination is that the amendment requested involves significant hazards considerations, any hearing held would take place before the issuance of any amendment.
Normally, the Commission will not issue the amendment until the expiration 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 facility, the Commission may issue the license amendment before the expiration of the 30-day notice period, provided that its final determination is that the amendment involves no significant hazards considerations. The final determination will consider all public and State comeents 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 request for a hearing or a petition for leave to intervene must be filed with the Secretary of the Commission, U. S. Nuclear Regulatory Commission, Washington, DC 20555, Attenti~n: Docketing and Service Branch.
o
& or may be delivered to the Comission's Public Document Room., Gelman Building, 2120 s Street, N.W., Washington, DC, by the above date. Where petitions are 1
filed during the last ten (10) days of the notice period, it is reouested that the petitioner promptly so inform the Comission 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 message addressed to Robert A. Capra: petitioner's name and telephone number; date petition was mailed; plant name; asid publication date and page number of this FEDERAL REGISTER notice. A copy of the petition should also be sent to the Office of the General Counsel, U. S. Nuclear Regulatory Commission, Washington, DC 20555, and to D. A. Prune, Jr.,
General Counsel, Baltimore Gas and Electric Company, P. O. Box 1475, Baltimore, Maryland 21203, attorney for the licensee.
Nontimely filings of petitions for leave to intervene, amended petitions, supplemental petitions and/or requests for hearing will 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 a late petition and/or request. That determination will be based upon a balancing of the factors specified in 10 CFR 2.714(a)(1)(i)-(v) and 2.714(d).
4 1
o
' For further details with respect to this action, see the application for amendment which is available for public inspection at the Commission's Public
]
Document Room, 2120 L Street, N.W., Washington, DC 20555, and at the Local Public Document Room, Calvert County Library, Prince Frederick, Maryland.
Dated at Rockville, Maryland, this 14th day of February 1989.
FOR THE NUCLEAR REGULATORY COMMISSION N
Scott Alexander McNeil, Project Manager Project Directorate I-1 Division of Reactor Projects I/II-So
- PDI-li W-UFC :PDI.1
- PDI.1 NAME :CVogant#
- SMcNeil. r :RCapra DATE :2/\\4/89
- ?//V /89
- P//tV/8 OFFICIAL RECORD COPY