ML20072G499
| ML20072G499 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/23/1983 |
| From: | Howe P CAROLINA POWER & LIGHT CO. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20072G502 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.1.1, TASK-1.A.1.3, TASK-2.E.4.1, TASK-2.E.4.2, TASK-2.K.3.03, TASK-2.K.3.13, TASK-2.K.3.15, TASK-2.K.3.19, TASK-2.K.3.22, TASK-2.K.3.27, TASK-2.K.3.45, TASK-TM GL-83-02, GL-83-2, LAP-83-227, NUDOCS 8306280524 | |
| Download: ML20072G499 (4) | |
Text
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SERIAL: LAP-83-227 Carolina Power & Light Company JUN 231983 Director of Nuclear Reactor Regulation Attention:
Mr. D. B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing United States Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 SUPPLEMENTAL REQUEST FOR LICENSE AMENDMENT NUREG-0737 TECHNCIAL SP9IFICATIONS
Dear Mr. Vassallo:
SUMMARY
In accordance with the Code of Federal Regulations, Title 10, Part 50 90 and Part 2.101, Carolina Power & Light Company (CP&L) hereby requests revisions to the Technical Specifications (TS) for the Brunswick Steam Electric Plant, Unit Nos. 1 and 2.
These revisions supersede our March 16, 1982 submittal concerning TS requirements for NUREG-0737 Item II.K.3 15.
DISCUSSION Generic Letter No. 83-02 dated January 10, 1983 requested all I
boiling water reactor licensees to submit proposed TS revisions for the NUREG-0737 items listed in Enclosure 1 of the letter. Carolina Power & Light Company has reviewed the guidance information for these NUREG-0737 requirements and has identified those items for which a TS is needed.
, provided herein discusses each NUREG-0737 item referenced in Generic Letter 83-02, including the CP&L action needed to resolve the item. provides CP&L's proposed TS revisions based on the model TS provided in Generic Letter 83-02.
Carolina Power & Light Company has revieued this request and determined that the proposed TS revisions involve no significant hazards i
consideration because the proposed changes constitute additional limitations and restrictions not presently included in the TS.
This is on of the examples of a request involving no significant hazards that is provided in the published Commission guidance (48 FR 14870) for the requirements in 10 CFR 50.92.
8306200524 830623 i
PDR ADOCK 05000324
(
P PDR 411 Fayetteville Street
- P. O. Box 1551
- Raleigh, N. C. 27602 I I
r D. B. Vassallo ADMINISTRATIVE INFORMATION Enclosed are revised TS pages for Brunswick-1 and Brunswick-2 with the changes indicated by vertical lines in the right-hand margins. Several of the enclosed TS pages supersede the same numbered pages provided in our March 16, 1982 request. Since this request relates to NUREG-0737 requirements and is a supplement to our March 16, 1982 request referenced above, we have determined that no additional license amendment fee is required.
Should you have any questions concerning this submittal, please contact our staff.
Very truly yours G.u P. W. Howe Vice President Brunswick Nuclear Project WRM/pgp (7001WRM)
Enclosures cc:
Mr. D. O. Myers (NRC-BSEP)
Mr. J. P. O'Reilly (NRC-RII)
Mr. S. D. MacKay (NRC)
Mr. Dayne H. Brown, Chief Radiation Protection Branch Division of Facility Services Department of Human Resources P. W. Howe, having been first duly sworn, did depose and say that the information contained herein is true and correct to his own personal knowledge or based upon information and belief.
QAAha.
A Notary'(Seal) l My commission expires: 3 00-97
o 9
ENCLOSURE 1 TO LAP-83-227
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Item 1: STA Training (NUREG-0737 Item I.A.1.1.3)
No action is required pending further Commission action.
Item 2: Limit Overtime (NUREG-0737 Item I.A.1 3)
By letters dated July 28, 1981 and December 10, 1982, CP&L submitted to the NRC Staff proposed revisions to Section 6, Administrative Controls, of the Technical Specifications (TS) for Brunswick-1 and Brunswick-2. At present, these proposed TS are under review and are being discussed with the Staff. In a subsequent letter, CP&L will submit revised proposed Administrative Controls TS that incorporate requirements for limiting plant staff overtime.
Item 3: Dedicated Hydrogen Penetrations (NUREG-0737 Item II.E.4.1)
By letter dated March 11, 1982, CP&L notified the NRC that the company intended to seek an exemption from the requirements of 10 CFR 50.44(c)(3)(ii) and was deferring the implementation of dedicated hydrogen penetrations at the Brunswick Plant pending Commission action on the exemption request. The exemption was submitted and is supported by CP&L's letters dated October 11, 1982 and March 16, 1983 Since this exemption request is still under review by the NRC Staff, CP&L does not intend to initiate action on TS for dedicated hydrogen penetrations at this time pending Commission action on the exemption request.
Item 4:
Containment Pressure Setpoint (NUREG-0737 Item II.E.4.2.5)
No further action is required by the Staff.
Item 5: Containment Purge Valves (NUREG-0737 Item II.E.4.2.6) i Further NRC action is being handled on a plant-specific basis. No action is required.
I Item 6: Radiation Signal on Purge Valves (NUREG-0737 Item II.E.4.2 7) i No action is required pending further Staff review.
Item 7: Reportirg SV and RV Failures and Challenges (NUREG-0737 Item II.K.3 3) l By letters dated July 28, 1981 and December 10, 1982, CP&L submitted to the l
NRC Staff proposed revisions to Section 6, Administrative Controls, of the TS for Brunswick-1 anc Brunswick-2. At present, these proposed TS are under review and are being discussed with the Staff.
In a subsequent letter, CP&L will submit revised proposed Administrative Controls TS that incorporate l
requirements for reporting relief valve and safety valve failures and challenges.
I i
Item 8: RCIC Restart and RCIC Suction (NUREG-0737 Items II.K.3.13 and II.K.3.22)
Attached (Enclosure 2) are proposed TS changes to incorporate requirements relating to RCIC restart and RCIC suction switchover. The RCIC system is provided to assure adequate core cooling in the event of reactor isolation from its primary heat sink and the loss of feedwater flow to the reactor vessel without requiring actuation of any of the emergency core cooling system equipment. The RCIC system is actuated on a low-low reactor vessel water level (low level 2) signal and by manual initiation.
In the standby readiness mode, the RCIC pump suction is aligned to the condensate storage tank (CST) with the suppression pool as a redundant source of water. On low CST level, the RCIC pump suction automatically transfers to the suppression pool. RCIC system operation will continue, unless tripped, until a reactor vessel high water level signal is received. This signal results in the closure of the F045 RCIC steam supply valve, returning the system to the standby readiness mode. This allows the RCIC system to automatically restart on the receipt of a subsequent low-low reactor vessel water level signal.
Item 9: Isolation of HPCI and RCIC Modification (NUREG-0737 Item II.K.3.15)
By letter dated March 16, 1982, CP&L submitted to the NRC Staff proposed TS revisions for Brunswick-1 and Brunswick-2 addressing requirements for a time delay relay modification to be incorporated in the steam line break detection circuitry of the HPCI and RCIC Systems. However, based on the model TS guidance provided in Generic Letter 83-02 (January 10, 1983), CP&L has revised its TS request. The new proposed TS pages are enclosed.
Carolina Power &
Light Company's submittal dated December 31, 1980 to Mr. D. G. Eisenhut concerning post-TMI requirements and Enclosure 1 of CP&L's letter dated March 16, 1982 provides the technical basis for the proposed TS revisions.
Item 10: Interlock on Recirculation Pump Loops (NUREG-0737 Item II.K.3.19)
The Brunswick Plant is a BWR-4 plant equipped with jet pumps; therefore, this item is not applicable and no further action is required.
Item 11: Common Reference Level (NUREG-0737 Item II.K.3.27)
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Technical Specification changes to incorporate a common reactor vessel reference water leyel have already been reviewed and approved by the NRC Staff as Amendment No. 52 for Brunswick-1 and Amendment No. 77 for Brunswick-2. No further action is required.
Item I?:
Manual Depressurization (NUREG-0737 Item II.K.3.45)
No further action is required by the Staff.
(7001WRMpgp)
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