ML20205N031

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Forwards Records of Coordination from Util That Provide Requested Clarification & Corrections Re Util 870303 Tech Spec Change Request Concerning Trip Setpoint & MSIV Leakage Control Sys
ML20205N031
Person / Time
Site: Clinton Constellation icon.png
Issue date: 03/26/1987
From: Siegel B
Office of Nuclear Reactor Regulation
To: Butler W
Office of Nuclear Reactor Regulation
References
NUDOCS 8704020564
Download: ML20205N031 (7)
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March 26, 1987 Docket No.: S0-461 MEMORANDUM FOR: Walter R. Butler, Director BWR Project Directorate No. 4 EL TgN

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Division of BWR Licensing NRC PDR LPDR FROM: Byron L. Siegel, Project Manager PD#4 Reading BWR Project Directorate No. 4 BSiegel/LKintner Division of BWR Licensing M0'Brien

SUBJECT:

ADDITIONAL INFORMATION RELATED TO FULL-POWER OPERATING LICENSETECHNICALSPECIFICATIONCHANGES(TS)

In a submittal dated March 3, 1987 Illinois Power Company (IP) requested: 1)a TS change related to the trip setpoint and allowable setpoint value for the reactor vessel low pressure instrumentation (LPCS and LPCI injection valve pressure); 2) a TS change related to the MSIV leakage control system; and

3) a TS change related to a table notation for the gaseous effluent monitoring instrumentation. The staff requested clarification regarding the analytical limit used in determining the setpoint changes and the potential effects on the ECCS analyses for item 1 and corrections to proposed TS for items 2 and 3.

Enclosed are records of coordination from IP that provide the requested clarification and corrections.

Dessut sened by Byron L. Siegel, Project Manager.

BWR Project Directorate No. 4 Division of BWR Licensing -

Enclosure:

As stated cc w/ enclosure: D. Katze PDf4/PM BSieoel:ca 03/f/87 8704020564 870326 PDR ADOCK 05000461 P PDR

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Docket No.: 50-461 MEMORANDUM FOR: Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing FROM: Byron L. Siegel, Project Manager BWR Project Directorate No. 4 Division of BWR Licensing

SUBJECT:

ADDITIONAL INFORMATION RELATED TO FULL-POWER OPERATING LICENSE TECHNICAL SPECIFICATION CHANGES (TS)

In a submittal dated March 3, 1987 Illinois Power Company (IP) requested: 1) a TS change related to the trip setpoint and allowable setpoint value for the reactor vessel low pressure instrumentation (LPCS and LPCI injection valve pressure); 2) a TS change related to the MSIV leakage control system; and

3) a TS change related to a table notation for the gaseous effluent monitoring instrumentation. The staff requested clarification regarding the analytical limit used in determining the setpoint changes and the potential effects on the ECCS analyses for item 1 and corrections to proposed TS for items 2 and 3.

Enclosed are records of coordination from IP that provide the requested clarification and corrections.

Au ron L. Siegel, Project Manager BWR Project Directorate No. 4 Division of BWR Licensing

Enclosure:

As stated cc w/ enclosure: D. Katze

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~'< Y-204371 Prepared by: . F. Phares, V-920 Date March 5, 1987 Copies to: F. A. Spangenberg, E- File Code L30-87 (03-05 )-6 J. D. Weaver, V-920 Retention Code 8E.110 6 P. J. Telthorst, V-920 Record Type 1A.165 ,

M ieg'e17CNRC" Class of Record 0 J. C. Hunsicker Quality of Record NS RECORD OF COORDINATION pj Type: Meeting X Telecon Other:

Date: March 5, 1987 Time: 0845

Participants:

D. Katze, B. L. Siegel, R. F. Phares

Subject:

Channes to CPS-TS re, U-600848 dated 3/3/87 Summarv Letter U-600848 Attachment page 5 of 23 presented changes to the CPS-TS. Mr. D.

Katze of NRC was concerned about changes to the analytical limit and the potential effects on the ECCS analysis.

I responded based on the 10CFR50.59 evaluation that this higher tolerance to radiation is required because of GE's revised setpoint methodology program. GE's past nethodology, for these transmitters and their associated trip units, based the setpoint on the LPCI system being required within 15 minutes of a I.0CA (Design Basis Event). At 15 minutes into the event, the integrated radiation dose, to the transmitter, is nowhere near the point that transmitter inaccuracy would cause LPCI misoperation. The revised methodology uses a more conservative basis for determining the setpoint by assuming a complete release'of fission products from a full-life core at time equal zero post-LOCA.

The upper analytical limit for setpoint determination is to prevent overpressurization of LPCI piping. The lower analytical limit is set to be consistent with the ECCS analysis in that LPCI will initiate in sufficient time to prevent core damage. This concern was analyzed for and found to be consistent with the CPS-Specific ECCS analysis.

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. , . - . . _ . _ ...f-.. . . . 1 GENERAL $ ELECTRIC NUCLEAA ENERGY PROJECTS DM510N GENE #AL ELECTRIC COMDANY e CUNTON PO%ER STATION e P.O BOX 675 e CLINTON, ILLINOIS 61797 * (917) 935-5344 March 10,, 1987 GSI-065-87 To: J. Hunsicker V-928

Subject:

Setpoint Methodology Program: Change in Analytical Limit for Reactor Pressure Vessel - Low (LPCS and LPCI Injection Valve Permissive)

General Electric's Plant Performance Engineering Component assessed the impact of the updated analytical limits on the clinton LOCA analysis for subject valve permissive and has determined that, for the Design Basis Accident - recirculation -

suction line break with LPCI D/G failure (Reference Clinton FSAR Table 6.3-3), PCT will increase by 34 degrees F and the oxidation fraction will increase by 0.003. Since the PCT for the previous FSAR case is 2071 degrees F, there is sufficient margin available to the 2200 degrees F limit to absorb the increase resulting from the reanalysis.

Repe.rformance of the LOCA analysis was prompted by changes to three input parameters:

- Updated analytical limits for the LPCI and LPCS injection valve parminniva

- Updated analytical limits for level setpoints LL1, LL2 and LL3

- MOV closure time relaxations The Mov closure time relaxations contributed the largest share of the 34 degrees F PCT increase.

GE Licensing is processing a Licensing Action Notice (LAN) to inform Illinois Power of the need for an FSAR update to reflect the results of the reanalysis.

~/Y) Y M. H. Howe

  • Resident Site Manager Clinton Power Station MHH: 1rt cc: .J. A... Miller,-V-130D W. Connell, V-928 F. Spangenberg, V-920 J. Weaver, V-920

. D..Phares,.V-920.., _ L. H. Larson, M/C 396

._.S._W.. Coulter,10ak-Brock- J. Leong, M/C 046 rc, W.. Cooley, M/C.784

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K. Berry, M/C 682 R. B.'Talwar, V-800 R. C. Cha11 berg, V-800 File: E12;A.S.4 -

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- . . . . . .m u -..m CUI VFCLUCL UC*36 L 6 / CU 1)I SY Prepared by: _ Pharea. V-920 Date March 18. 1987 Copies to: ,

F. A. Scannenbern. V-92 File Code L30-87(o3-181-6 P. J._Tetrhorse -920 Retention Code 6 J. D. Weaver. V-920 Record Type Class of Record

_J. W. Wilson. T-31 J. G. Cook T-31 R. F. Schalter. T-31 Quality of Record R. W. Morgenstern, T-31 J. R. Hays, T-31 RECORD OF COORDINATION Type Meeting __X_Telecon Other: .

Date: March 17. 1987 Time: 10:00 A.M.

Participants:

R. F. Phares (L&S. B. L. Sienel (NRC)

Subject:

CPS Technical Soecifications (CPS-TS)

Summary In letter dated March 3, 1987 (U-600848), IP submitted changes to l CPS-TS. During meetings held with the NRC on March 10-11, 1987, I met with Messrs. B. Siegel, C. Schulten, J. Lee, and P. Hearn. The reviewers, Lee and Hearn, had minor comments and recommendations with respect to pages 11 (CPS-TS p. 3/4 3-104) and 15 (CPS,yTS p. 3/4 6 7) of the subject letter attachment. The NRC recommendstions attached are acceptable and will not constitute a change to the intent of the IP submittal.

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Attachment 5 600848 CONTAINM[N1 $Y$1[M5 Pase 15 of 23

(.. H51v LtAKAGE CONTROL $YSTEM LIM 111NG COND1110N FOR OPERATION l

3.6.1.4 Two independent MS]v leakage control system (LCS) subiysters shall be OPERABLE.

APPLICABIL11Y: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

With one MSlv leakage control system subsystem inoperable, restore the inoper-able subsystem to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SUR_VEILLANCE RE001REMENTS

4. 6.1. 4 Each M51V leakage control system subsystem shall be demonstrated OPERABLE: ,
a. At least once per 31 days by verifying:
1. Blower OPERABILITY by starting the blowers from the control room and operating the blowers for at least 15 minutes.
2. Heater OPERABILITY by demonstrating electrical continuity of the heating element circuitry.
b. During each COLD SHtJTDOWN, if not performed within the previous 92 days, '

by cycling each remote, manual and automatic motor operated valve through  ;

at least one complete cycle of full travel, i l

c. At least once per 18 months by:
1. Performance of a functional test which includes simulated actuation of the subsystem throughout its operating sequence, and verifying ,

that each automatic valve actuates to its correct position, the l blower (s) start.

2. Verifying that blower develops at least the required vacuum at l the rated capacit andeac{hheaterunitdraws7.4to9.2 amperes per phase. ,,

a) I ar(system,15" H 0 vacuum at > 100 cfa.

b) utboardkyst ,15"ka0vacuumati cfm M eed, t,b[

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U-600848 Page 11 of 23 TABLE 3.3.7.121 (Continued) f RAD 10 ACTIVE CA$t00$ (FFLUENT MONITORING IN51RUMENTAT10N TABLE NOTATIONS . .

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W ACT10N With the number of channels OPERABLE less than required by the ACTION 121 - Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at' least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and analyzed for gross noble gas activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

With the number:of channels OPERABLE less than required by the ACTION 122 - Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after the channel has been declared inoperable, samples are contin-uously collected with auxiliary sampling equipment as required in Table 4.11.2-1. '

With the number of channels OPERABLE less than required by the ACTION 123 - Minimum Channels OPERABLE requirement, effluent releases via this pathway mRy continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

With the number of channels OPERABLE less than required by the ACTION 124 - Minimum Channels OPERABLE requirement, operation of the main condenser off-gas treatment system may continue provided grab samples are collected at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

4 ACT10N 125 - Deleted With the number of channels OPERABLE less than required by the ACTION 126 - Minimum Channels OPERABLE requirement, suspend release of radio-l i

activity effluents via this pathway.

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