ML17207A762

Submits Request to Amend License Re Tech Spec Pages 3-10, 3-14,3-16 & 3-18.Changes Include Actuation Sys Instrumentation,Instrument Trip Valves & Actuation Sys Instrumentation Surveillance Requirements

ML17207A762
Person / Time
Site:	Saint Lucie
Issue date:	01/22/1980
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Stello V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
Shared Package
ML17207A763	List: ML17207A762 ML17207A764
References
L-80-28, NUDOCS 8001290205
Download: ML17207A762 (11)

Text

RKGULA fURY FORMATION DISTRIBUTION SY .N (RIDS)

ACCESSION NBR ~ 8001290205- DOC ~ DATE ~ 80/01/22 NOTARIZED YES DOCKE1T "FI>>>>CTC:50 335' St. Lucie AOYH",NAME" "Plantg'nit

"'AUTHOR AFFIL'SATION ii Flor ida. Power 'I>> 'I.3ght t:o., 05050535 UARIG~H,E, Florida Power '8 Light Co.

RECIP.hlANE REC lP LENT AFF ILlAT ION STKCLOiV; 0>v'i's'i'ori of Ope'r'at'i'rig Reactors

SUBJECT:

Submits request to>> amend license re Tech Spec pages 3 10~

3>>14~3 16 8 8 18.Changes include actuatlop sys initrumentationilnstrument trip valves L actuation sys inst rumentet fun survei i 1'ence requ ( i cmental.

DISTRIBUTION CODE:

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P 'OX 529100, MIAMI,FL 33152

~gills J/A~iwxh FLORIDA POWER 4 LIGHT COMPANY January 22, 1980 L-80-28 Office of Nuclear Reactor Regulation Attention: Mr. Victor Stello, Director Division of Operating Reactors U. S. Nuclear Regulatory Commission tlashington, D. C. 20555

Dear Mr. Stello:

Re: St. Lucie Unit No. 1 Docket No. 50-335 Proposed Amendment to Facilit 0 eratin License DPR-67 In accordance with 10 CFR 50.30, florida Power 5 Light Company herewith submits three (3) signed originals and forty (40) copies of a request to amend Appendix A of Facility Operating License DPR-67.

The proposed amendment is being submitted to include the Safety Injection Actuation Signal (SIAS) as an initiating event for the Containment Isolation Signal (CIS). The modification was made in response to I8E Bulletin 79-06B.

The proposed amendment is shown on the attached Technical Specification pages.

Pa e 3/4 3-10 The proposed revision to Table 3.3-2, Engineered Safety Feature Actuation System Instrumentation, adds the SIAS as an actuator for the CIS.

Pa e 3/4 3-14 The proposed revision to Table 3.3-4, Engineered Safety Features Instrumentation Trip Values, adds the SIAS as an actuator for the CIS.

Pa e 3/4 3-16 The proposed revision to Table 3.3-5, Engineered Safety Features Response Times, adds Containment Isolation as a function of the Safety Injection Actuation and the Pressurizer Pressure-Low Signals.

8001890 QG+~ PEOPLE... SERVING PEOPLE

0 7' Office of Nuclear Reactor Regulation Page Two Pa e 3/4 3-16 The proposed revision to Table 4.3-2, Engineered Safety Feature Actuation System Instrumentation Surveillance Requirements, adds the SIAS, with its surveillance requirements, as an actuator for the CIS.

The proposed amendment has been reviewed by the St. Lucie Plant Facility Review Group and the Florida Power 5 Light Company Nuclear Review Board.

They have determined that the proposed change does not involve an unreviewed safety question.

Very truly yours, Vice President Advanced Systems 8 Technology REU/HAS/cph Attachment cc: Hr. James P. O'Reilly, Region II Harold F. Reis, Esquire

t SAFETY EVALUATION Re: St. Lucie Unit 1 Docket Ho. 50-335 Containment Isolation on SIAS Introduction The intent of items 3 and 8 of ISE Bulletin 79-06B was to ensure no inadvertent release from containment in an event where the Safety Injection Actuation Signal (SIAS) occurs without the Containment Isolation Signal (CIS) Although the St. Lucie Unit 1 original

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design isolated the most likely path (containment sump pump discharge) it was consi dered desirable to isolate all paths not needed for core cooling capability. Therefore the SIAS was added as an actuator for the CIS.

II. Evaluation The proposed amendment modifies the CIS so that it actuates upon a SIAS in addition to the original initiating events (high containment pressure and high radiation). Essentially this means that the Pressurizer Pressure-Low signal becomes an additional ini tiating event for the CIS. This will ensure no inadvertent releases from containment in an event where the SIAS occurs without the original CIS actuation setpoints being reached.

This modification involves "hard wiring" whereby the SIAS becomes a direct input to the CIS system. Thus all calibrations and checks are already included in the surveillance requirements for the SIAS and CIS functional units and the only appropriate additional testing is the proposed channel functional test per Table 4.3-2, A list of the containment penetrations affected by this change is attached. All other lines penetrating containment are either essential to core cooling capability, have locked closed manual valves, or already'isolate on SIAS per original design. Review of

, this list has verified that control of the Reactor Coolant System during accident conditions is not adversely impacted by containment

'isolation on SIAS.

III. Conclusions

!Ae have concluded, based on the considerations discussed above, that:

(1) the proposed amendments do not involve a significant increase in the probability or consequences of accidents previously considered and

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do not involve a significant decrease in a safety margin, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.

Containment Penetrati ons Affected b S I AS The following is a list of lines penetrating containment which previously were not isolated on a safety injection actuation signal (SIAS):

1. Steam Generator Blowdown (2 lines)

2. Primary Makeup Water

3. Instrument Air Supply

4. Containment Purge Air Exhaust

5. Containment Purge Supply

6. Nitrogen Supply to Safety Injection Tanks

7. Reactor Coolant Sample

8. Pressurizer Surge Line Sample

9. Pressurizer Steam Space Sample

10. Steam Generator Blowdown Sample (2 lines) ll. Containment Vent Header

12. Reactor Drain Tank Pump Suction

13. Reactor Coolant Pump Controlled Bleedoff *

14. Containment Atmosphere Radiation Monitoring System (3 lines)

All other lines penetrating containment are either 'essential to core cooling capability, have locked closed manual valves, or isolate already on a safety injection actuation signal.

• Seal bleedoff will relieve to the quench tank and RCP operation is permissible with the containment isolation valves closed.

STATE OF FLOBXDA, )

) st COUNTY OF DADE )

A. D. Schmidt , being first. duly sworn, deposes and says:

That he is Vice President ~

of Florida Power 6 Light Company, the herein; That he has executed the foregoing document; that the state-ments made in this said document are true and correct. to the best of his knowledge, information, and belief, and that he is authorized to execute the document. on behalf of said A. D. Schmidt Subscr-'bed and sworn to before me..this day of 19~0 NOTARY PUBLZCr and for the County o 'ade, State of Florida Notary Public, State of Clorttfe at Larg0 My Comintsslon Expfros Octobor 30, 1983

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