ML20155J291
| ML20155J291 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 10/27/1998 |
| From: | Hagan J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9811120082 | |
| Download: ML20155J291 (4) | |
Text
....
. ~..
~. - _
Joseph J.Hagan Ves President A
Station Support
~*~
PECO NUCLEAR e= te c-ev 965 Chesterbrook Blvd A Unit of PECO Energy wayne.PA 19087-5691 610 640 6100 Fax 610 640 6376 October 27,1998 Docket No. 50-171 License No. DPR-12 U.S. Nuclear Regulatory Commission ATTN Document Control Desk Washington, DC 20555
SUBJECT:
Peach Bottom Atomic Power Station, Unit i Submittal of Revision 1 of the Updated Final Safety Analysis Report
Dear Sir:
In accordance with 10CFR50.71(e)(4) and 10CFR50.4(b)(6), this letter submits one original and ten copies of Revision 1 of the Updated Final Sateiy Analysis Report (UFSAR) for Peach Bottom Atomic Power Station (PBAPS), Unit 1. The enclosed copies are be!ng provided to the NRC with a page revision listing that identifies the latest revision date of all current pages in accordance with 10CFR50.71(e)(1). We have also provided page replacement instructions for incorporating Revision 1 intu the UFSAR. As required by 10CFR50.71(e)(5), each replacement page contains a bold vertical line in the margin adjacent to each area changed
.ilong with the date of the change.
As required by 10CFR50.71(e)(2)(i), I certify that to the best of my knowledge. Revision 1 to the PBAPS Unit 1 UFSAR accurately reflects information and analyses submitted to the NRC, or prepared pursuant to NRC requirements as described above. In addition, as required by 10CN150.71(e)(2)(ii), no changes under the provision of 10CFR50.59, but not previously submnted to tha NRC have been made.
If you have ery questions, or require further information, please contact us.
Very truly youns,
=
Enclosure cc: H. J. Miller, Administrator, Region 1, USNRC 0
l' il 9811120082 981027 7
PDR ADOCK 05000171 K
PDR M
2v.1
.; s
~
r w
Q PBAPS PEACH BOTTOM ATOMIC POWER STATION, Unit 1 UPDATED FINAL SAFETY ANALYSIS REPORT PAGE REPLACEMENT INSTRUCTIONS Revision 1,10/27/98 Remove Paae insert Paae Page Revision Listing Page Revision Listing Appendix 1, List of Licensing Documents Appendix 1, List of Licensing Documents License / Tech Specs License / Tech Specs License Pages 1 and 2 License Pages 1 and 2 Tech Spec Page 2 Tech Spec Page 2 Tech Spec Page 4 Tech Spec Page 4 NRC SERs NRC SERs Safety Evaluation Related to Amendment No. 9 O
O i
PBAPS l
PEACH BOTTOM ATOMIC POWER STATION, Unit 1 4
UPDATED FINAL SAFETY ANALYSIS REPORT PAGE REVISION LISTING
~
TITLE REVISION DATE Updated Final Safety Analysis Report 3/27/98 Appendix 1 Licensing Documents 1
10/27/98 d
License Reference Letters
'(3
()
November 24,1975 Letter to NRC 3/27/98 March 4,1987 Letter to NRC 3/27/98 December 16,1988 Letter to NRC 3/27/98
]
July 12,1989 Letter to NRC 3/27/98 j
August 23,1989 Letter to NRC 3/27/98 l
License / Technical Specifications Amendment No. 9 to License No. DPR-12 1
10/27/98 Technical Specifications (4 pages)
Page 1 3/27/98 l
Page 2 1
10/27/98 Page 3 3/27/98 Page 4 1
10/27/98 NRC SERs Safety Evaluation Supporting Amendment No. 7 3/27/98 Safety Evaluation Supporting Amendment No. 8 3/27/98 Safety Evaluation Supporting Amendment No. 9 1
10/27/98 Revision 1 O
OCT 2 71998
i t
- O i
APPENDIX 1 l
i i-i 1
i PEACH BOTTOM ATOMIC POWER STATION l
l UNIT 1 LICENSING DOCUMENTS O
Ucense Reference Letters PECO Letter to NRC 11/24/75 PECO Letter to NRC 3/4/87 PECO Letter to NRC 12/18/88 PECO Letter to NRC 7/12/89 i
PECO Letter to NRC 8/23/89 License / Technical Specifications License, DPR 12 9/14/98 l
Technical Specifications Page 1 11/3/94 Page 2 9/14/98 Page 3 11/3/94 Page 4 9/14/98 NRC SERs NRC Safety Evaluation Supporting Amendment No. 7 4/25/90 NRC Safety Evaluation Supporting Amendment No. 8 11/3/94 NRC Safety Evaluation Supporting Amendment No. 9 9/14/98-l Revision 1 t
Oti 2 71908
PECO ENERGY COMPANY Cl DOCKET NO. 50-171 LJ PEACH BOTTOM ATOMIC POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 9 1.icense No. DPR-12 1.
The U.S. Nuclear Regulatory Commission (NRC) has found that:
A.
The application for amendment by PECO Energy Company (the licensee) dated March 2,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and NRC regulations set forth in 10 CFR Chapter I; B.
The facility will be maintained in conformity with the application, the provisions of the Act, and regulations of the NRC; C.
There is reasonabla 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 NRC's regulations set forth in 10 CFR Chapter I;
(~]
D.
The licensee is technically and financially qualified to engage in the activities j
authorized by this amended license in accordance with the rules and regulations of the NRC; E.
The licensee has satisfied the applicable provisions of 10 CFR Part 140,
" Financial Protection Requirements and indemnity Agreements" of NRC's regulations:
F.
The issuance of this amendment will not be inimical to the common defense and secunty or to the health and safety of the public; G.
The issuance of this amendment is in accordance with 10 CFR Part 51 of NRC's regulations and all applicable requirements have been satisfied; and H.
The possession and storage of byproduct material as authorized by this amended license will be in accordance with NRC regulations in 10 CFR Part 30, including 10 CFR Section 30.33.
2.
Accordingly, the license is amended by changes to License No. DPR-12 and the Technical Specifications as indicated in the attachment to this license amendment and Facility Operating License No. DPR-12 is hereby amended to read as follows:
A.
This amended license applies to the Peach Bottom Atomic Power Station, Unit 1, a permanently shutdown, high temperature, gas cooled, demonstration power reactor, and associated equipment (the facility) owned by PECO Energy o
Company. The facility is located at the licensee's site in York County,
)
Pennsylvania, and is described in the application for renewal dated EHCLOSURE 1 OCT 2 71998
%2ajj O.h ')pf
l
'O November 24,1975, as revised March 4,1987, December 16,1988, July 12, V
1989, and August 23,1989.
B.
Subject to the coriditions and the requirements incorporated herein, the NRC hereby licenses the PECO Energy Company; (1)
Pursuant to Section 104(b) of the Act and 10 CFR Part 50, " Domestic" Licensing of Production and Utilization Facilities" to possess but not operate the facility.
(2)
Pursuant to the Act and 10 CFR Part 30," Rules of General Applicability to Domestic Licensing of Byproduct Material" to possess, but not to separate, such byproduct material as may have been produced by operation of the facility.
C.
This license shall be deemed to contain and be subject to the conditions specified in Part 20, Section 30.34 of Part 30, Section 50.59 of Part 50, i
10 CFR Chapter 1, and to all applicable previsions of the Act and to the rules, regulations, and orders of the NRC now or hereaiter in effect and is subjact to the additional conditions specified below:
(1)
PECO Energy Company shall not dismantle or dispose of the facility without prior approval of the NRC.
(2)
Technical Soecifications 0Q The Technical Specifications contained in Appendix A as revised through l
Amendment No. 9, are hereby incorporated in the license. The licensee shall maintain the facility in accordance with the Technical Specifications.
D.
This license amendment is effective as of the date of itt issuance and must be fully implemented no later than 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
\\
/N/ fW
/.
i John W. N. Hickey, Chief Low-Level Waste and Decommissioning Projects Branch Division of Waste Manamment i
Office of Nuclear Material Safety l
and Safeguards
Attachment:
Changes to the Technical Specifications Date of issuance: September 14,1998 l
001 2 7 1998 s
m
Appendix A Page 2 v.
Containment personnel access lock at Elevation
/^)
176'-6".
V vi.
Grating over southwest stairway leading from refueling floor of Containment to Containment lower levels.
vii.
Personnel door into Spent Fuel Pool Area-at "
Elevation 116'-0".
viii. Radwaste Room personnel door at Elevation 104'-
0".
2.
Employees of the Peach Bottom Atomic Power Station shall report to the Peach Bottom Plant Manager or his designated representative any observed indication of change in facility status as shown by smoke, fire, tornado, flood or attempted break-in and take any immediate action authorized.
3.
Administrative procedures shall be established for the notification and reporting of the following reportable events:
1.
The entrance of an unauthorized person (s) into the facility, ii.
A significant change in the radiation or contamination levels in the facility.
O
! j iii.
Effluent releases in excess of Specification 2.1(b)(8).
iv.
Water accumulation in the containment sump in excess of Specification 2.1(b)(9).
4 Security of the facility shall be included as a part of the Peach Bottom Atomic Power Station security plan.
5.
In the event of a Probable Maximum Flood, the personnel access door at elevation 116'-0" shall be opened in accordance with the Peach Bottom Atomic Power Station Units 2 and 3 flood procedures.
6.
If entry and/or work in the controlled area of the containment should be necessary, radiation level and airborne activity surveys shall be performed prior to beginning work and all work shall be performed under controls, as appropriate. to minimize the radiation exposure of personnel and to prevent the release of radioactivity to the environment.
7.
All radiation surveys. tests counting work radioactive effluent controls, and radiation exposure control measures shall be performed in accordance with written instructions and procedures that conform with the requirements of the Peach Bottom Atomic Power Station Units 2 and 3 radiation control procedures.
p
()
s Amendment No. 9 007 2 7 1993
, Appendix A Page 4 3.
The high efficiency ) articulate filter on the containment O
breather line shall ]e surveyed for activity, and the filter V
changed at least annually.
4 Inspect the accessible areas below ground level in the containment vessel for water accumulation.
Perform a radiological analysis if there is sufficient water accumulation to obtain a sample.
2.4 Reports (a)
An annual report shall be submitted to the Nuclear Regulatory Commission. Washington, DC 20555. describing the results of facility radiation surveys, a sumary of the quantities of radioactive effluents released, the status of the facility, and an evaluation of the performance of security and surveillance measures.
Include the results of the radiological analysis, along with an evaluation of the source of the water and corrective actions taken, for sampleable quantities of water accumulation in the containment vessel.
(b)
The NRC Regional Office'shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of discovery of. a reportable event (specification 2.1(b)(3)). and a written report pursuant to 10 CFR 50.73 shall be submitted to the Administrator of the Regional Office within 30 days.
O!
v OQ Amendment No. 9 OCT 2 71998,
W C*h
[*
i UNITED STATES g
}
NUCLEAR REEULATORY COMMISSION o,
WASHINGTON, D.C. *mana smi f3 9 *ew O
SAFETY EVALUATION BY OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS RELATED TO AMENDMENT NO. 9 TO FACILITY OPERATING LICENSE NO. DPR-12 PECO ENERGY COMPANY PEACH BOTTOM ATOMIC POWER STATION. UNIT 1 DOCKET NO. 50-171
1.0 INTRODUCTION
By letter dated March 2,1998 PECO Energy Company (PECO or the licensee) submitted a request for a change to the Peach Bottom Atomic Power Station Unit 1 (Peach Bottom 1)
Technical Specifications (TS) appended to Facility Operating License No. DPR-12. The requested changes would include requirements for corF.rol of effluents and annual reporting per 10 CFR 50.36a.
2.0 EVALUATION The final rule, dated July 29,1996, for Decommissioning of Nuclear Power Reactors, revised 10 CFR 50.36a to clarify applicability of this section to alllicensees of power reactors whether operating or not. As a result of the revision of 10 CFR 50.36a, PECO is required to have additional effluent TS for Peach Bottom 1. The licensee has requested to add requirements for control of effluents and annual reporting per 10 CFR 50.36a.
The proposed amendment includes a requirement to establish and follow procedures for the control of effluents. The proposed change involve adding a requirement in Section 2.1(b)(7) of the TS to ensure procedures are in place for effluent monitoring. The amendment also includes a requirement for an annual effluent report. This report would specify to the NRC the quantity of radioactive effluents released. The proposed change involve adding, to Section 2.4(a) of the TS, the annual reporting to the NRC of radioactive effluents released. The NRC staff finds this request acceptable.
l
3.0 STATE CONSULTATION
In accordance with the NRC regulations, the Pennsylvania State official was notified of the proposed issuance of the amendment. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes Peach Bottom 1 TS with respect to the administrative procedures or requirements. NRC staff has determined that the amendment involves no significant increase in the amounts, and no sigrificant change in the types, of any effluents that may be released of' site, and that there is no significant increase in individual or cumulative occupational radiation (n')
exposure. '..ie NRC staff has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding ENCLOSURE 2
&f $3'f} fg
2 O
(63 ER. 35994) on July 1,1998. 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 impad statement or environmental assessment need be prepared in connection wiu. taa issuar.ce of tne amenoment.
5.0 CONCLUSION
The NRC staff has concluded, based on the considerat!ons 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 NRC 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: S. Wu, NMSS/LLDP Date: September /9,1998 O
I I
O OCT 2 71S23
.