ML18016A256
| ML18016A256 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 12/16/1997 |
| From: | Robinson W CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18016A258 | List: |
| References | |
| HNP-97-198, NUDOCS 9712230003 | |
| Download: ML18016A256 (14) | |
Text
{{#Wiki_filter:CATEGORY 1 REGULAT INFORMATION DISTRIBUTIO SYSTEM (RIDS) ACCESSIO?QNBR: 9712230003 DOC.DATE: 97/12/16 NOTARIZED: YES DOCKET FAC IL,:.5.C~-,4Q 0 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH.QA'Mh AUTHOR AFFILIATION ROBINSON,W.R. Carolina Power 6 Light Co. RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Application for .amend to license NPF-63,revising TS 4.7.1.2.1.a.2.a to change differential pressure S flow requirements of steam turbine-driven AFW pump to allow testing of pump at lower speed than is currently performed. A DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR j ENCL I SIZE: I + T TITLE: OR Submittal: General Distribution NOTES:Application for permit renewal filed. 05000400 G RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 1 ROONEY,V 1 1 INTERNAL: ACRS 1 1 F CENTE 01 1 1 NRR/DE/ECGB/A 1 1 NR 1 1 NRR/DRCH/HICB = 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRZB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS2 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D 0 E N NOTE TO ALL "RIDS" RECIPIENTS: PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL 13
l. 'U
, /
Carolina Power & Light Company William R. Robinson PO Box 165 Vice President New Hill NC 27562 Harris Nuclear Plant SERIAL: HNP-97-198 DEC 16 1997 10 CFR 50.90 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT AUXILIARYFEEDWATER SYSTEM SURVEILLANCEREQUIREMENTS
Dear Sir or Madam:
In accordance with the Code of Federal Regulations, Title 10, Part 50.90, Carolina Power &, Light Company (CP&L) requests a revision to the Technical Specifications (TS) for the Harris Nuclear Plant (HNP). The proposed amendment revises Auxiliary Feedwater System (AFS) Surveillance Requirements. Specifically, TS 4.7.1.2.1.a.2.a willbe revised to change the differential pressure and flow requirements of the steam turbine-driven Auxiliary Feedwater (AFW) pump to allow testing of the pump at a lower speed than is currently performed. Changing the test point parameters of the turbine-driven AFW pump is required because the current testing results in vibration levels that could result in early pump degradation. The proposed test point will demonstrate that pump performance is not degrading below the, previously established TS limits while allowing the surveillance to be performed at a speed that is less detrimental to the pump. Enclosure 1 provides a description of the proposed changes and the basis for the changes. details, in accordance with 10 CFR 50.91(a), the basis for CP8cL's determination that the proposed changes do not involve a significant hazards consideration. provides an environmental evaluation which demonstrates that the proposed amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental assessment is required for approval of this amendment request. QQ provides page change instructions for incorporating the proposed revisions provides the proposed Technical specification pages. 97i2230003 97i2ib ~ n IllI Ililll1)llI l)lllgl[[l\ 2 t 6 ~ PDR ADOCK 05000400 P PDR o4 t J btiearon Harris Road New Hill NC Tel 919 362-2502 Fax 919 362-2095
l'l Document Control Desk SERIAL: HNP-97-198 Page 2 CPS'equests that the proposed amendment be issued such that implementation willoccur within 60 days of issuance to allow time for orderly incorporation into copies of the Technical Specifications. Please refer any questions regarding this submittal to Mr. J. H. Eads at (919) 362-2646. Sincerely, AEC/aec
Enclosures:
- 1. Basis for Change Request
- 2. 10 CFR 50.92 Evaluation
- 3. Environmental Considerations
- 4. Page Change Instructions
- 5. Technical Specification Pages W. R. Robinson, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief; and the sources of his information are employees, contractors, and agents of Carolina Power & Light Company.
Notary (S al) My commission expires: gO'IARY o~ca 5Qg c: Mr. J. B. Brady (NRC Senior Resident Inspector) Mr. Mel Fry (Acting Director, N.C. DEHNR) e+~ >UBL'I< c,g Mr. L. A. Reyes (NRC Regional Administrator, Region Il) Mr. V. L. Rooney (NRR Project Manager, HNP) +~,. ~ COO,o~ Ollglllllilll
Document Control Desk SERIAL: HNP-97-198 Page 3 l bc: Ms. D. B. Alexander Ms. W. C. Langston (PE&RAS File) Mr. T. C. Bell Mr. C. W. Martin (BNP) Mr. H. K. Chernoff (RNP) Mr. R. D. Martin Mr. B.H. Clark Mr. P. M. Odom (RNP) Mr. G. W. Davis Mr. W. S. Orser Mr. J. W. Donahue Mr. R. F. Saunders Mr. W. J. Dorman (BNP) Mr. D. L. Tibbitts Mr. W. J. Hindman Mr. C. A. VanDenburgh Mr. W. D. Johnson Nuclear Records Mr. R.M. Krich Licensing File File: H-X-0511
ENCLOSURE 1 TO SERIAL: HNP-97-198 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT AUXILIARYFEEDWATER SYSTEM SURVEILLANCEREQUIREMENTS BASIS FOR CHANGE RE UEST B~ack round The Auxiliary Feedwater System (AFS) supplies feedwater to the secondary side of the steam generators when the normal feedwater system is not available, thereby maintaining the heat sink capabilities of the steam generators. The system provides an alternate to the Feedwater System during startup, hot standby and cooldown. It also functions as an engineered safeguards system to prevent core damage in the event of transients such as loss of normal feedwater flow and steam line rupture. The system is designed to supply sufficient quantities of feedwater to achieve stable hot standby conditions and plant cooldown ifnecessary. The AFS consists of two 100 percent capacity, redundant motor-driven pumps and one 200 percent capacity steam turbine-driven pump. Each motor-driven pump is rated for 2940 feet of head at 450 gallons per minute (gpm), and the turbine-driven pump is rated for 2940 feet of head at 900 gpm. Surveillance requirements outlined in TS 4.7.1.2.1 demonstrate operability of the pumps on a periodic basis. TS 4.7.1.2.1.a.2 allows demonstrating that the turbine-driven pump satisfies performance requirements by either: a) verifying the pump develops a differential pressure of at least 1433 psid at a recirculation flow rate of at least 90 gpm when the secondary steam supply pressure is greater than 210 psig, or b) verifying the pump develops a differential pressure of at least 1400 psid at a flow rate of at least 430 gpm when the secondary steam supply pressure is greater than 280 psig. Conducting the recirculation flow test at 90 gpm requires operating the turbine-driven pump at 4100 rpm. It has been found that conducting the test at this pump speed and flow rate produces hydraulic instabilities resulting in higher than desired vibration levels. Although these vibration levels were not conclusively linked to the recent pump bearing failure (August 31, 1997), performing this surveillance as currently written may result in early degradation of the pump. Pro osed Chan e TS 4.7.1.2.1.a.2.a currently allows the turbine-driven Auxiliary Feedwater (~ pump to be demonstrated operable by verifying the pump develops a differential pressure that (when temperature-compensated to 70'F) is greater than or equal to 1433 psid at a recirculation flow of greater that or equal to 90 gpm (45 KPPH) when the secondary steam supply pressure is greater than 210 psig. To achieve these test parameters, the pump is run at 4100 rpm. The proposed change will allow the turbine-driven AFW pump to be demonstrated operable by verifying the pump develops a differential pressure that (when temperature-compensated to 70'F) is greater than or equal to 1167 psid at a recirculation flow of greater than or equal to 81 gpm (40.5 KPPH) when the secondary steam supply pressure is greater than 210 psig. This will allow the pump to be run at 3700 rpm, which has been determined to be less detrimental to the pump than 4100 rpm. Page El-1
ENCLOSURE 1 TO SERIAL: HNP-97-198 Basis The proposed change to TS 4.7.1.2.1.a.2.a is required because the current recirculation flow test parameters result in vibration levels that could result in early degradation of the turbine-driven AFW pump. Reducing the speed at which the turbine-driven AFW pump is run for operational surveillance testing from 4100 rpm to 3700 rpm will not affect the ability to detect pump degradation. In addition, test data obtained for the HNP turbine-driven AFW pump has shown reduced vibration at the lower pump speed of 3700 rpm. To determine the new surveillance criteria, the centrifugal pump affinity law was applied to data from the original pump curves which were used to establish the existing TS surveillance criteria (Attachment to Enclosure 1). At 3700 rpm, this analysis results in a differential pressure of 1216 psid at a flow of 81 gpm. Degrading this differential pressure value by 4%, as described in the TS Bases, results in the revised differential pressure criterion of 1167 psid. Therefore, the proposed test parameters will demonstrate that pump performance has not degraded below the previously established TS limits while allowing the surveillance to be performed at a pump speed that is less likely to be detrimental to the pump. Conclusions TS 4.7.1.2.1.a.2.a as currently written, requires testing at a speed that could result in early degradation of the AFW turbine-driven pump. The proposed amendment willdemonstrate that pump performance is not degrading below the previously established TS limits while allowing the surveillance to be performed at a speed that is less detrimental to the pump. Page El-2
I c 'F~ oem ZDAJ4'o. 'i"' z'" ' ~MI(vh'+'gpetct ice. L'.g
-gpeOSt ~.'j'j$g-gg+grfSMv $ . - "-: 4tnattovpo.M..llkgiijpat';~
Pc@/'.+yP ~g-,7 gf,.gPjidfh',NOiTZS . 'vtvoe atolappcoximat ~ . Pvmp'4 OArant<<ed'ot'no
' I.j"Pg.A'~W: R6 ~a~ +tant coadit<on@ Capacity, head and cthcieacy ctvatv anleel ala based on sSop .lail aad vhcn"]uncited
.:id'pg -
.Pbp Q<7g,3f clear, cold 'tteA qatar at ~ tcntpeceluio, dt nol over
%'dtvvtaet, and not over IS'vchon lift.
oe
-..:-- -+QO -..-'.= "bye-v .-.-,:.AP.- -'PW.
~::~~
.-:
~
I
~ ~
..'654iilS w Jvt a'vc
'
eaaQIPb /A Pi'tl. 0 ~ w " ~ v, ~
. ~
"." ~-
ReiyW+Qdfg@me0'-;:
.-ggAz gg v'. o
@PAP'..+PC tfh~~ P SAhWN '
,M>'<<a apso>>fr>>ata. Mfa Ie'usia>>teed Qt ot CO>>drfroIQ Ctfraett71 g o>>a IN>>de>>de@jete>>e7 ra ear, l
BY,* p ig
.
-';.r -'-'><~+.g7. ~
'.4 ordaae <<e 4>>red'arrf chop taft, asd <<he>> haadt4vy tear. aotd, froth plater ~ I ~ ter>>peiatpra of >>ot dettleee ead aot oper IS'eelroa Ifft.
~
Id
~1 '
r
- 54 a 1
'
lr ~, 1 t
'
*~
~
ENCLOSURE 2 TO SERIAL: HNP-97-198 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT AUXILIARYFEEDWATER SYSTEM SURVEILLANCEREQUIREMENTS 10 CFR 50.92 EVALUATION The Commission has provided standards in 10 CFR 50.92(c) for determining whether a significant hazards consideration exists. A proposed amendment to an operating license for a facility involves no significant hazards consideration ifoperation of the facility in accordance with the proposed amendment would not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (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. Carolina Power 8r, Light Company has reviewed this proposed license amendment request and determined that its adoption would not involve a significant hazards determination. The bases for this determination are as follows: Pro osed Chan e TS 4.7.1.2.1.a.2.a currently allows the turbine-driven Auxiliary Feedwater (AFW) pump to be demonstrated operable by verifying the pump develops a differential pressure that (when temperature-compensated to 70'F) is greater than or equal to 1433 psid at a recirculation flow of greater that or equal to 90 gpm (45 KPPH) when the secondary steam supply pressure is greater than 210 psig. To achieve these test parameters, the pump is run at 4100 rpm. The proposed change will allow the turbine-driven AFW pump to be demonstrated operable by verifying the pump develops a differential pressure that (when temperature-compensated to 70'F) is greater than or equal to 1167 psid at a recirculatio'n flow of greater than or equal to 81 gpm (40.5 KPPH) when the secondary steam supply pressure is greater than 210 psig. This will allow the pump to be run at 3700 rpm, which has been determined to be less detrimental to the pump than 4100 rpm. Basis This change does not involve a significant hazards consideration for the following reasons:
- 1. The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
Changing the recirculation flow test parameters at which the turbine-driven AFW pump is tested will demonstrate pump operability while allowing the surveillance to be performed at a speed that is less detrimental to the pump. Appropriate testing will continue to ensure that the Auxiliary Feedwater System (AFS) is capable of performing its intended function. The proposed amendment will not introduce any new equipment or require existing equipment to function different from that previously evaluated in the Final Safety Analysis Report (FSAR) or TS. Therefore, the proposed change does not involve a Page E2-1
ENCLOSURE 2 TO SERIAL: HNP-97-198
'significant increase in the probability or consequences of an accident previously evaluated.
- 2. The proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
Changing the recirculation flow test parameters at which the turbine-driven AFW pump is tested will demonstrate pump operability while allowing the surveillance to be performed at a speed that is less detrimental to the pump. Appropriate testing will continue to ensure that the AFS is capable of performing its intended function. The proposed amendment willnot introduce any new equipment or require existing equipment to function different from that previously evaluated in the Final Safety Analysis Report (FSAR) or TS. The proposed amendment will not create any new accident scenarios, because the change does not introduce any new single failures, adverse equipment or material interactions, or release paths. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. The proposed amendment does not involve a significant reduction in the margin of safety. Changing the recirculation flow test parameters at which the turbine-driven AFW pump is tested will demonstrate pump operability while allowing the surveillance to be performed at a speed that is less detrimental to the pump. Appropriate testing will continue to ensure that the AFS is capable of performing its intended function. Therefore, the proposed change does not involve a significant reduction in the margin of safety. Page E2-2
ENCLOSURE 3 TO SERIAL: HNP-97-198 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT AUXILIARYFEEDWATER SYSTEM SURVEILLANCEREQUIREMENTS ENVIRONMENTALCONSIDERATIONS 10 CFR 51.22(c)(9) provides criteria for licensing and regulatory actions eligible for categorical exclusion from performing an environmental assessment. A proposed amendment to an operating license for a facility requires no environmental assessment ifoperation of the facility in accordance with the proposed amendment would not: (1) involve a significant hazards consideration; (2) result in a significant change in the types or significant increase in the amounts of any effluents that may be released offsite; (3) result in a significant increase in individual or cumulative occupational radiation exposure. Carolina Power Ec Light Company has reviewed this request and determined that the proposed 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 needs to be prepared in connection with the issuance of the amendment. The basis for this determination is as follows: C" TS 4.7.1.2.1.a.2.a currently allows the turbine-driven Auxiliary Feedwater (AFW) pump to be demonstrated operable by verifying the pump develops a differential pressure that (when temperature-compensated to 70'F) is greater than or equal to 1433 psid at a recirculation flow of greater that or equal to 90 gpm (45 KPPH) when the secondary steam supply pressure is greater than 210 psig. To achieve these test parameters, the pump is run at 4100 rpm. The proposed change will allow the turbine-driven AFW pump to be demonstrated operable by verifying the pump develops a differential pressure that (when temperature-compensated to 70'F) is greater than or equal to 1167 psid at a recirculation flow of greater than or equal to 81 gpm (40.5 KPPH) when the secondary steam supply pressure is greater than 210 psig. This will allow the pump to be run at 3700 rpm, which has been determined to be less detrimental to the pump than 4100 rpm. Basis The change meets the eligibilitycriteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) for the following reasons:
- 1. As demonstrated in Enclosure 2, the proposed amendment does not involve a significant hazards consideration.
- 2. The proposed amendment does not result in a significant change in the types or increase in the amounts of any effluents that may be released offsite.
Page E3-1
ENCLOSURE 3 TO SERIAL: HNP-97-198
'The proposed change does not involve any new equipment or require existing systems to perform a different type of function than they are currently designed to perform. The change does not introduce any new effluents or increase the quantities of existing effluents. As such, the change cannot affect the types or amounts of any effluents that may be released offsite.
- 3. The proposed amendment does not result in a significant increase in individual or cumulative occupational radiation exposure.
The proposed change does not result in any physical plant changes or new surveillance which would require additional personnel entry into radiation controlled areas. Therefore, the amendment will not result in an increase in individual or cumulative occupational radiation exposure. Page E3-2}}