ML17157C116
| ML17157C116 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 12/09/1992 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17157C117 | List: |
| References | |
| NUDOCS 9212220414 | |
| Download: ML17157C116 (21) | |
Text
7590-01 U I E
ST T S
NUC AR R
GU TOR COMM S 0 P
NNS VAN POW AND GHT COM ANY A LEGHENY E
C RIC COOPERATIVE INC DOCKET NO. 50-388 NOTICE OF CONSIDERATION OF SSUANC OF AMENDMENT TO FACILITY OPERATING LICENSE PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION AND OPPORTUNIT FOR H AR NG The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment to Facility Operating License No. NPF-22 issued to Pennsylvania Power and Light Company and Allegheny Electric Cooperative, Inc.
(the licensees) for operation of the Susquehanna Steam Electric Station (SSES),
Unit 2, located in Salem Township, Pennsylvania.
The amendment would revise the Technical Specifications (TSs) to authorize operation of the Reactor Water Cleanup (RWCU) system in the current fuel cycle (Cycle 6) with the RWCU system non-regenerative heat exchanger discharge high temperature channel substituting for the inoperable
'B'WCU High Flow isolation trip channel.
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.
The Commission has made a proposed determination that the amendment request involves no significant hazards consideration.
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 or consequences o'f an accident previously 92i22204i4 92i209 PDR ADOC~ 050003~8 P.
PDR i
evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant f
reduction in a margin of safety.
As required by 10 CFR 50.91(a),
the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:
NO SIGNIFICANT HAZARDS CONSIDERATION 2.
This request does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The RWCU piping is carbon steel and is therefore resistant to IGSCC.
For one operating cycle, the probability of a RWCU line break coincident with a failure to isolate the RWCU containment penetration in the section of piping which depends on it for diversity has been determined to be very low (1. 1 E-6).
For the balance of the RWCU piping, operation without the inoperable RWCU high flow trip channel does not increase the probability of containment isolation malfunction as analyzed in the Susquehanna IPE [Individual Plant Examination].
With regard to consequences, other redundant and diverse means of break detection are available, and have been determined to be adequate to cover the range of potential break scenarios evaluated in the FSAR [Final Safety Analysis Report).
For the section of RWCU piping that is dependent on high flow for diversity, the combined protection of the OPERABLE 'A'hannel, the compensatory
- actions, and the Level 2 isolation will ensure that the consequences are bounded by previous FSAR evaluations.
A specific evaluation concluded that radiological consequences for RWCU pipe breaks outside of containment are within the bounds of the FSAR analysis for Hain Steamline Breaks outside of containment.
This request does not create the possibility of a new or different kind of accident from any previously evaluated.
Inoperability of an isolation channel can only affect the probability or consequences of analyzed events (a leak/break with subsequent failure to isolate).
It cannot create a new event.
3.
The proposed change does not involve a significant reduction in a margin of safety.
For the reasons described in I above, the 'B'igh flow trip channel can be inoperable for one cycle of operation.
Adequate diversity to operate the Susquehanna units has been determined to exist in the remaining OPERABLE trip channels and those channels have been determined to cover the complete range of analyzed break scenarios required.
The exception is the section of piping which depends on the High Flow function for diversity.
The probability of a line break of this piping coincident with a failure to isolate has been found to be sufficiently low for one cycle.
Given this low probability and the one for one replacement of the inoperable high flow channel with the non-'regenerative heat exchanger discharge high temperature channel which effectively provides the same leak detection capabilities, an acceptable level of RWCU isolation reliability continues to exist, and a significant reduction in safety margin will not occur.
The NRC staff has reviewed the licensee's analysis
- and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied.
Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration.
The Commission is seeking public comments on this proposed determination.
Any comments received within thirty (30) days after the date of publication of this notice 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.
Written comments may be submitted by mail to the Rules and Directives Review Branch, Division of Freedom of Information and Publications Services, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC
- 20555, and should cite the publication date and page number of this FEDERAL REGISTER notice.
Written comments may also be delivered to Room P-223, Phillips Building, 7920 Norfolk Avenue,
- Bethesda, Maryland, from 7:30 a.m'. to 4: 15 p.m.
Federal workdays.
Copies of written comments received may be examined at the NRC Public Document Room, the Gelman Building, 2120 L Street,
.NW., Washington, DC 20555.
The filing of requests for hearing and petitions for leave to intervene is discussed below.
By January 14, 1993 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 request for a hearing and a petition for leave to intervene.
Requests for a hearing and a petition 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.
Interested persons should consult a current copy of 10 CFR 2.714 which is available at the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC 20555 and at the local public document room located at Osterhout Free Library, Reference Department, 71 South Franklin Street, Wilkes-Barre, Pennsylvania 18701.
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 Commission or by the Chairman of the Atomic Safety and Licensing Board, 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 appropriate 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 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 which are sought to be litigated in the matter.
Each contention must consist of a specific statement of the issue of law or fact to be raised or controverted.
In addition, the petitioner shall provide a brief explanation of the bases of the contention and a concise statement of the alleged facts or expert opinion which support the contention and on which the petitioner intends to rely in proving the contention at the hearing.
The petitioner must also provide references to those specific sources and documents of which the petitioner is aware and on which the petitioner intends to rely to establish those facts or expert opinion.
petitioner must provide sufficient information to show that a
genuine dispute exists with the applicant on a material issue of law or fact.
Contentions shall be limited to matters within the scope of the amendment under consideration.
The contention must be one which, if proven, would entitle the petitioner to relief.
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 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 request involves no significant hazards consideration, the Commission may issue the amendment and make it immediately 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 request involves a
significant hazards consideration, 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.consideration.
The final determination will consider all public and State comments received.
Should the Commission take this action, it will publish in the FEOERAL REGISTER 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, Attention:
Docketing and Services
- Branch, or may be delivered to the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC
- 20555, 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 1-(800) 325-6000 (in Missouri l-(800) 342-6700).
The Western Union operator should be given Datagram Identification Number N1023 and the following message addressed to Charles L. Miller, Director, Project Directorate I-2, Division of Reactor Projects I/II:
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 Shaw,
- Pittman, Potts and Trowbridge, 2300 N Street NW., Washington, D.C.
- 20037, 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 presiding Atomic Safety and Licensing Board that the petition and/or request should be granted based upon a balancing of the factors specified in 10 CFR 2.714(a) (1) (i)-(v) and 2.714(d).
For further details with respect to this action, see the application for amendment dated November 30, 1992, which is available for public inspection at
the Commission's Public, Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC 20555 and at the local public document room located at Osterhout Free Library, Reference Department, 71 South Franklin Street, Wilkes-Barre, Pennsylvania 18701.
Dated at Rockville, Maryland, this 9gQ day of December 1992.
FOR THE NUCLEAR REGULATORY COMMISSION cg~g. N~
Charles L. Miller, Director Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
f UCFNSE AUTHORlTY FHE CC-October 29, 92 Mr. Harold W. Keiser Senior Vice President-Nuclear Pennsylvania Power and L'ight Company 2 North Ninth Street Allentown, Pennsylvania 18101
Dear Mr. Keiser:
SUBJECT:
SUPPRESSION POOL FILTER PUMP AND VALVE ISOLATION LOGIC CHANGES, SUS(UEHANNA STEAM ELECTRIC STATION, UNIT 2 (TAC NO. M84231)
The Commission has issued the enclosed Amendment No. 92 to Facility Operating License No. NPF-22 for the Susquehanna Steam Electric Station, Unit 2.
This amendment is in response to your letter dated August 7, 1992.
This amendment would make a change to the Susquehanna Steam Electric Station (SSES),
Unit 2 Technical Specifications that changes the isolation signal for suppression pool cleanup line valves HV-25766 and HV-25768 from reactor vessel low water level 3 (+13") or high drywell pressure to reactor vessel low water level 2 (-38") or high drywell pressure.
A copy of our Safety Evaluation is also enclosed.
Notice of Issuance will be included in the Commission's Biweekly feedera Re<eR ster Notice.
Enclosures:
l.
Amendment No. 92 to License No. NPF-22 2.
Safety Evaluation cc w/enclosures:
See next page Sincerely, Qrlglnal signed bg Richard J. Clark Richard J. Clark, Senior Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation DISTRIBUTION:
Docket File NRC
& Local PDRs PDI-2 Reading SVarga JCalvo CHiller MO'Brien(2)
RClark OGC
- DHagan, 3206 GHil 1 (4), Pl-22 Wanda Jones, 7103
- CGrimes, llE21 Tech Branch ACRS(10)
OPA OC/LFMB EWenzinger, RGN-I
- JWhite, RGN-I 4 2C
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ky*y4 Docket No. 50-388 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 October 29, 1992 Mr. Harold W. Keiser Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101
Dear Mr. Keiser:
SUBJECT:
SUPPRESSION POOL FILTER PUMP AND VALVE ISOLATION LOGIC CHANGES, SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 2 (TAC NO. M84231)
The Commission has issued the enclosed Amendment No. 92 to Facility Operating License No. NPF-22 for the Susquehanna Steam Electric Station, Unit 2.
This amendment is in response to your letter dated August 7, 1992.
This amendment would make a change to the Susquehanna Steam Electric Station (SSES),
Unit 2 Technical Specifications that changes the isolation signal for suppression pool cleanup line valves HV-25766 and HV-25768 from reactor vessel low water level 3 (+13") or high drywell pressure to reactor vessel low water level 2 (-38") or high drywell pressure.
A copy of our Safety Evaluation is also enclosed.
Notice of Issuance will be included in the Commission's Biweekly ~Federa
~Re ister Notice.
Sincerely,
Enclosures:
l.
Amendment No. 92 to License No. NPF-22 2.
Safety Evaluation cc w/enclosures:
See next page R
ark, Senior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Mr. Harold W. Keiser Pennsylvania Power
& Light Company Susquehanna Steam Electric Station, Units 1
& 2 CC:
Jay Silberg, Esq.
- Shaw, Pittman, Potts
& Trowbridge 2300 N Street N.W.
Washington, D.C.
20037 Bryan A. Snapp, Esq.
Assistant Corporate Counsel Pennsylvania Power
& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. J.
M. Kenny Licensing Group Supervisor Pennsylvania Power
& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Scott Barber Senior Resident Inspector U.
S. Nuclear Regulatory Commission P.O.
Box 35 Berwick, Pennsylvania 18603-0035 Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection Resources Commonwealth of Pennsylvania P. 0.
Box 2063 Harrisburg, Pennsylvania 17120 Mr, Jesse C. Tilton, III Allegheny Elec. Cooperative, Inc.
212 Locust Street P.O.
Box 1266 Harrisburg, Pennsylvania 17108-1266 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Mr. Harold G. Stanley Superintendent of Plant Susquehanna Steam Electric Station Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Herbert D. Woodeshick Special Office of the President Pennsylvania Power and Light Company Rural Route 1,
Box 1797 Berwick, Pennsylvania 18603 Mr. Robert G.
Byram Vice President-Nuclear Operations Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101
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0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 PENNSYLVANIA POWER 5 LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NO. 50-388 SUS UEHANNA STEAM ELECTRIC STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 92 License No.
NPF-22 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by the Pennsylvania Power 8I Light Company, dated August 7,
- 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-22 is hereby amended to read as follows:
(2) Technical S ecificat'ons a
d E vironmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 92 and the Environmental Protection Plan con-tained in Appendix B, are hereby incorporated in the license.
PPKL shall operate the facility in accordance with the Technical Specifica-tions and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and is to be implemented within 30 days after its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 29, 1992 Charles L. Miller, Director Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
TTAC M NT TO LICENS AMENDMEN NO.
FACILITY OPERATING LICENSE NO.
NPF-22 DOCKET NO. 50-388 Replace the following pages of the Appendix A Technical Specifications with enclosed pages.
The revised page is identified by Amendment number and contains vertical lines indicating the area of change.
The overleaf page is provided to maintain document completeness.*
REMOVE 3/4 6-21 3/4 6-22 INSERT 3/4 6-21*
3/4 6-22
4
TABLE 3. 6. 3-1 (Continued)
PRIMARY CONTAINMENT ISOLATION VALVES MAXIMUM ISOLATION TIME Seconds VALVE FUNCTION ANO NUM8ER Automatic Isolation Valves (Continued)
Containment Atmos here Sam le ISOLATION( )
SIGNAL Sl<a>
SV-25734 A,B SV-25736 A
SV-25736 8
Sv-25740 A,B Sv-25742 A,B Sv-25750 A,B SV-25752 A,B SV-25774 A,B Sv-25776 A
Sv-25776 B
SV-25780 A,B SV-25782 A,B N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A B,Y B,Y B,Y B,Y B,Y B,Y B,Y B,Y B,Y B,Y B,Y B,Y SV-25737 SV-25738 SV-25767 SV-25789 Reactor Coolant Sam le HV-243F019 HV-243F020 Li uid Radwaste Hv-26108 A1, A2 HV-26116 A1,A2 RHR -
Su ressfon Pool
~C' lI Hv-251F028 A,B CS T~st(b)(C)
HV-252F015 A,B HPCI Suction
~
Hv-255F042 N/A N/A N/A N/A 15 15 90 60 90 B,Y,R B,Y,R B,Y,R B,Y,R B,C B,C B,Z B,Z X,Z X,Z L,LB SUSQUEHANNA - UNIT 2 3/4 6-21 Amen~nt No. 59 NOV 3 NS
PRIMARY ONTAINMENT ISOLATION VALVES Valve Function and Number AUToMAnc IsoLATIDN VALYEs (CDNTINUED)
Maximum Isolation Time (Seconds) isolation Signal(s)
SUPPRESSION POOL CLEANUP( I HV-25766 HV-25768 HPCI VACUUM BREAKER HV-'255F075 HV-255F079 RCIC VACUUM BREAKER HV-249F062 HV-249F084 TIP BALL VALVES I I C51'-J004"A B,C D E CONTAINMENT RADIATION DETECTION SYSTEM SV-'257100;A','B'V-257101 A,B
'.'.-'"... SY-257102 A,B-SV-257103 A,B
':..;;;, SV-257104',
SV-257105 SV-257106 '
SV-257107 b.
MANUALISOLATION VAI.VES MSIV-LCS Bleed Valve
- HV-'239F001."'B,"F;K,P.
FEEDWATERI )
HV-'241F032 A,B'WCU RETURN HV-'241
&2='"'CIC INJECTION HV-249F013';.
2-49-020 35 30 15 15 10'0
-N/A" N/A N/A N/A N/A.
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B,Z
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SUSQUEHANNA - UNIT 2 3/4 6-22 Amendment No. 92
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0y*~4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVA UATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT 0.92 TO FACILITY OPERATING LICENSE NO. NPF-22 PENNSYLVANIA POWER 5 LIGHT COMPANY GHENY ELECTR C COOPERATIVE INC.
SUS UEHANNA STEAM ELECTRIC STATION UNIT 2 DOCKET NO. 50-388
- 1. 0 INTRODUCTION By letter dated August 7, 1992, the Pennsylvania Power and Light Company and Allegheny Electric Cooperative, Inc. (the licensees) submitted a request for changes to the Susquehanna Steam Electric Station (SSES),
Unit 2, Technical Specifications (TS).
The requested changes would revise the
- SSES, Unit 2, TS to change the isolation signal for suppression pool cleanup line valves HV-25766 and HV-25768 from reactor vessel low water level 3 (+13") or high drywell pressure to reactor vessel low water level 2 (-38") or high drywell pressure.
The suppr ession pool is used to absorb the energy released during a Loss of Coolant Accident (LOCA) or safety/relief valve (SRV) operation, and to serve as a source of water for the Emergency Core Cooling Systems (ECCS).
Since pool water may be introduced into the reactor vessel, the capability to maintain or improve water quality is provided by a cleanup line.
This line is utilized to transfer water from the pool to the condenser hotwell where it can be filtered by passing through the condensate demineralizers.
The cleanup line may also be used to lower the suppression pool water level.
This change is being proposed by the licensee to increase the likelihood that the cleanup line will remain available (unisolated) for suppression pool level control following plant transients.
This is accomplished by increasing the margin between reactor vessel water levels during normal operation and the water level that results in isolation of the cleanup line.
The licensee indicates that this change will also reduce operator burden during plant cooldown by eliminating the need to repeatedly reset the isolation logic should additional isolations of the cleanup line occur.
2.0 EVALUATION The safety functions of the cleanup line are to automatically isolate, following a LOCA inside containment to limit radiological releases, and to provide the capability to manually isolate following a pipe break outside containment to prevent a loss of water from the suppression pool.
The safety
function of the suppression pool is to provide a source of water for ECCS and to absorb energy released during a
The SSES Final Safety Analysis Report (FSAR), Chapters 6
8 15 and the Design Assessment Report were reviewed by the licensee to determine the effect of changing the isolation signal on the transient and accident analysis.
The licensee states that applicable containment analyses were not affected because these analyses are already based on a level 2 cleanup line isolation.
The licensee further states that the design basis radiological release analysis remains bounded because this analysis is independent of the isolation signal used.
The licensee also indicated that after the construction of SSES was completed, General Electric Company (GE) specified the design requirement for isolation of the cleanup line as reactor vessel low water level 2 or high drywell
'ressure
(
Reference:
GE Specification No. 22A7239, Nuclear Steam Supply Shutoff System).
Since the proposed modification changes the isolation signal from level 3 to level 2, the design requirement remains satisfied and the safety function of automatic isolation following a LOCA is not impacted.
In addition, the hardware used for the level 2 signal is identical in design,
- material, and construction to that used for level 3.
Because the modification only changes the automatic isolation signal, manual isolation is unaffected.
As a positive impact on plant operation due to the proposed
- change, the licensee indicates that the increase in availability of the cleanup line allows the plant operator to reduce pool water levels should they increase over the high level setpoint.
Lower pool water levels result in lower loadings to the suppression pool structure and submerged components in the pool during a
Based on the above discussion, the licensee's statements in the submittal that the applicable containment analyses in the FSAR will not be affected due to the proposed change in the TS, and also that the design basis radiological release analysis remains
- bounded, the staff finds the change acceptable.
3.0 STATE CONSULTATIO In accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendment.
The State official had no comments.
4.0 ENVIRONMENT L CONSIDE TION The amendment changes a requirement with respect to installation or use of a facility 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 radiatioa exposure.
The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (57 FR 40218).
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 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.
Principal Contributor:
M. Razzaque pate:
October 29, 1992