ML18101A433

Proposed Tech Specs Re Surveillance Requirements for Areas within Containment

ML18101A433
Person / Time
Site:	Salem
Issue date:	12/23/1994
From:	SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML18101A432	List: ML18101A431 ML18101A433
References
NUDOCS 9501040274
Download: ML18101A433 (7)

Text

• , ATTACHMENT 1 PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS LICENSE AMENDMENT APPLICATION REVISION OF SURVEILLANCE REQUIREMENTS FOR AREAS WITHIN CONTAINMENT SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 NLR-N94171 DOCKET NOS. 50-272 and 50-311 LCR 94-33 I. DESCRIPTION OF THE PROPOSED CHANGE This proposed amendment revises Surveillance Requirement 4.5.2.c.2 by requiring at least one daily (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> consecutive period) inspection of areas affected by containment entry and during the final entry when Containment Integrity is established instead of an inspection at the completion of each entry.

II. REASONS FOR THE CHANGE Through this submittal, PSE&G is requesting implementation of the NRC recommendation regarding the surveillance requirement to perform a visual inspection of containment areas affected by personnel entry.

The proposed change to the Technical Specification is consistent with the guidance of Generic Letter (GL) 93-05, "Line-Item Technical Specifications Improvements to Reduce surveillance Requirements for Testing During Power Operation" and incorporates the recommendation of NUREG-1366, "Improvements to Technical Specifications Surveillance Requirements."

The proposed change provides the additional benefit of a reduction in radiation exposure to plant personnel and the elimination of an unnecessary burden on plant staff.

III. JUSTIFICATION FOR THE CHANGE Salem Technical Specification 4. 5. 2. c. 2 currently requires containment areas affected by entry to be visually inspected at the completion of each entry when containment integrity is established. In NUREG-1366 and GL 93-05, the NRC recommended that this inspection be done at least once d::iily if the containment has been entered that day and during the final containment entry to ensure that there is no loose debris present that would clog the sump. The proposed change reduces Page 1 of 3

A'.I'TACHMENT 1 NLR-N9.4171 REVISION OF SURVEILLANCE REQUIREMENTS FOR LCR 94-33 AREAS INSIDE CONTAINMENT the exposure to personnel performing the inspection when multiple entries are required into containment. Also, consistent with NUREG-1366, a record is maintained of containment areas visited. During multiple containment entries, this record would facilitate visual inspection during the final entry prior to establishing Containment Integrity.

A review of Salem Unit 1 and Unit 2 operating experience for the past two years does not indicate any problem involving loose debris (e.g. rags, _trash, clothing, etc.) left inside containment when containment integrity is established. The proposed change is therefore compatible with Salem Unit 1 and Unit 2 plant operating experience.

IV. DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION PSE&G has, pursuant to 10CFR50. 92, reviewed the proposed amendment to determine whether our request involves a significant hazards consideration. We have determined that operation of Salem Generating Station Unit 1 and Unit 2, in accordance with the propo~ed cl?-anges:

1. Does not involve a significant increase in the probability or consequences of an accident previously evaluated.

The proposed change does not alter the assumptions, design parameters or results of Updated Final Safety Analysis Report (UFSAR) accidents analyzed. The proposed change does not involve a hardware change, a change to the operation of any systems or components, or a change to any existing structures. The proposed change leads to a reduction in radiation exposure to plant personnel and the elimination of an unnecessary burden on plant staff. The revised visual inspection practice will not increase the probability or consequences of an accident previously evaluated.

2. Does not create the possibility of a new or different kind of accident from any previously evaluated.

The proposed change does not modify equipment, affect system design bases or operability. This change does not alter parameters utilized in the analyzed accident scenarios. The proposed change in surveillance frequency Page 2 of 3

ATTACHMENT 1 REVISION OF SURVEILLANCE REQUIREMENTS FOR NLR-N94171 LCR 94-33 AREAS INSIDE CONTAINMENT J

is consistent with the guiuance provided in GL 93-05. The performance of a visual inspection of containment areas affected by multiple containment entries on a daily bases and at the completion of the final entry when containment integrity is established will not create the possibility of a new or different kind of accident from those previously evaluated.

3. Does not involve a significant reduction in a margin of safety.

The proposed change only involves a decrease in surveillance frequency when multiple entries are made in a single day and does not alter the performance of the surveillance* itself. System equipment and operation remains unchanged. Operability and reliability is still maintained by the required inspection. The adaptation of the proposed surveillance frequency does not involve a significant reduction in the margins of safety.

V. CONCLUSIONS Based on the above, PSE&G has determined that the proposed change does not involve a significant hazards consideration.

Page 3 of 3

• ATTACHMENT 2 TECHNICAL SPECIFICATION PAGE WITH PEN AND INK CHANGES LICENSE AMENDMENT APPLICATION REVISION OF SURVEILLANCE REQUIREMENTS FOR AREAS WITHIN CONTAINMENT SALEM GENERATING STATION UNIT 1 FACILITY OPERATING LICENSE DPR-70 NLR-N94171 DOCKET NO. 50-272 LCR 94-33 The following Technical Specification for Facility Operating License No. DPR-70 is affected by this License Amendment Request:

Technical Specification 4.5.2.c.2 3/4 5-5

tMERGENCY CORE COOLING SYSTEMS RVEILLANCE REQUIREMENTS (Continued)

c. By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall be performed:

1. For all accessible areas of th~ containment prior to establishing CONTAINMENT INTEGRITY, and

2. affected within containment at tAe eempletieA ef 4-...

-4.aGR-E:Mt~i-Amem:~ant when CONTAINMENT INTEGRITY is* established.

by:;-=-tt:t:..:..:..:/"":.i..:""'~!:1.1::....__:e~...,~r::..!r:...;y~t:1~"1~vl~d.~v~r~1'.:'.::'""'-9-:!.+~h~t:__!l'i~,*"'~e:t'.J../~

11 At least once per 18 months"ti;';""-.;c.()'V

1.

• A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and ,

that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.

e. At least on~e per 18 months, during shutdown, by:*

1. Verifying that each automatic valve in the flow path actuates to its correct position on a safety injection test signal .

2. Verifying that each uf the following pumps start automatically upon receipt of a safety injection test signal:

a) Centrifugal charging pump b) Safety injection pump c) *Residual heat removal pump SALEM - UNIT 3/4 5-5 Amendment No. 44

• ATTACHMENT 3 TECHNICAL SPECIFICATION PAGE WITH PEN AND INK CHANGES LICENSE AMENDMENT APPLICATION REVISION OF SURVEILLANCE REQUIREMENTS OF AREAS WITHIN CONTAINMENT SALEM GENERATING STATION UNIT 2 FACILITY OPERATING LICENSE DPR-75 NLR-N94171 DOCKET NO. 50-311 LCR-94-33 The following Technical Specification for Facility Operating License No. DPR-75 is affected by this License Amendment Request:

Technical Specification 4.5.2.c.2 3/4 5-5

EMERGENCY CORE COOLING SYSTEJitS SURVEILLANCE REQUIREMENTS (Continued)

c. By 1 visual inspection which verifies that no loose debris (~lgs, trash, clothing, etc.) is present in the containment which could be transported to th* containment SU!lq) and cause T"estrictian of th*

pump suctions during LCCA conditions. This visual 1nsp1ction shall b* perfarmed:

1. Far 111 accessible areas of the containment prior to est&Dlfshing CONTAIHMEHT INTEGRITY, and

~ th* ar.as 1ff1ctad within containment 1t ~e eemp1etien of ...R.

...each conuf 1dHn~ry when CCffTAIHMEHT IHTEGRITY is est.aal ished.

6y C.tJ"'1t;o,,",,,,_,e..,-t e,,.,t-ry c,.,e/( ol~r/i.? -rL. f'.1 /

At least once per 18 aanths by: ~ e r "'e:i

.I

1.

• A visual inspection af the contain11ant sump and verifying that th* subsystem suction inlets are not "strfctad by debris and

'* that th* sump components (t-rash racks, scnens., etc.) show no

• videnc* of sti-uc:tural d1st1'"9ss ar COM"Osion.

1. At l11st once per 18 manths, during shutdown, by:

1. Verifying that 11ch automatic valve in the flow path actuates to its cornet position on 1 safety injaction test signal *

%. Verifying ttlat uch of the fallowing p~s start automatically upon l"Kafpt af a safety injection tut signal:

I) CantrlfugGl charting PUllP b) S&fety f njectian pump c) Residual heat 1"9110va1 pump SALEM

• UNIT ~ 3/4 S-5 Amendment Ho. 8