PY-CEI-NRR-1969, Application for Amend to License NPF-58,revising Tech Specs Allowable Values & Trip Setpoints for Selected Plant Process Instrumentation Using Instrument Setpoint Methodology Discussed in Util (PY-CEI/NRR-1706L)

Application for Amend to License NPF-58,revising Tech Specs Allowable Values & Trip Setpoints for Selected Plant Process Instrumentation Using Instrument Setpoint Methodology Discussed in Util (PY-CEI/NRR-1706L)

ML20091R175
Person / Time
Site:	Perry
Issue date:	08/29/1995
From:	Shelton D CENTERIOR ENERGY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20091R178	List: ML20091R191 PY-CEI-NRR-1969, Application for Amend to License NPF-58,revising Tech Specs Allowable Values & Trip Setpoints for Selected Plant Process Instrumentation Using Instrument Setpoint Methodology Discussed in Util (PY-CEI/NRR-1706L)
References
PY-CEI-NRR-1969, NUDOCS 9509060250
Download: ML20091R175 (5)

Text

. . _ - _ . - . . _ .. --_ ._ ___ ..

GNTW g Donaki C. Shelton

PERRY NUCLEAR POWER PLANT.- Maii Address

m BO M ' ' SENIOR VICE PRESIDENT 10 CENTER ROAD PERRY, OHlO 44081

- PERRY, OHIO 44081 . NWM

-(216) 250-3737 x .: August' 29,=1995!

PY-CEI/NRR-1969Li i

United States Nuclear. Regulatory Commission

-Document Control Desk u

~ Washington,;D.C. '20555

. Perry. Nuclear Power Plant -

. Docket No. 50-440 License. Amendment Request: Instrumentation ,

Trip Setpoints and Allowable Values

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.Gentlement' Amendment.of the Facility Operating License (NPF-58) for the Perry.

Nuclear.PowerfPlant (PNPP). Unit'l is requested. This License Amendment Application proposes thei revision of Technical Specification Allowable Values and Trip Setpoints for selected plant process instrumentation.

. .Thenew Allowable Values and Trip Setpoints were calculated using the

. Instrument Setpoint Methodology discussed in a previous letter dated October 15, 1993 (PY-CEI/NRR-1706L). This current amendment request

. fulfills a commitment made in that letter to'. incorporate into the '

Technical Specifications (TS) those new Allowable Values and Trip

[ 'Setpoints which vere more conservative than the current TS values.

A Summary, Description of Proposed. Changes, Safety Analysis, and an Environmental Consideration are provided in Attachment 1. Attachment 2

'provides a copy of the marked up TS pages, in both the present format and

. the format required following implementation of Amendment 69 (the improved. Technical Specifications). Attachment 3 provides the .

Significant' Hazards Consideration.

.If you have questions ^or require additional information, please contact

'Mr.. James D. Kloosterman,-Manager - Regulatory Affairs at (216) 280-5833.

Very truly'yours, 4

2)&/vv%

eBSF sc

. . Attachments.

cc: 1.NRC Pr6 ject' Manager- NRC Region III l NRC Resident Inspector;0ffice. State of Ohio opeenocompakes .

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• PY-CEI/NRR-1969L 4- Attachment 1

- Page 1 of 4 j

i SUNNARY

' In 1983 during the-Technical Specification reviev's for various facilities, the NRC staff identified several concerns regarding the values of protection system trip setpoints and the mathodology used for their determination. The '

NRC relayed this issue to the Perry Nuclear Power Plant (PNPP) in a letter dated June 21, 1983. As a result of this issue, and in an effort to

' conserve resources, a number of these utilities formed the Instrument Setpoint Methodology Group (ISMG). The ISMG program was accepted by the

staff in a letter from B. Youngblood (NRC) to J. Carolan (ISMG) dated July i 23, 1984. The endorsement of the activities of this group for the Perry t Nuclear Power Plant is detailed in a letter dated October 9, 1984 (PY-CEI/NRR-0132L). The instrument channels selected for PNPP vere based on the functions assumed to operate in the analyses contained in the Pinal

ESafety Analysis Report'(FSAR; since renamed as the Updated Safety Analysis

Report (USAR)) Chapters 6 and 15.

! The PNPP FSAR was updated in 1985 to include a commitment in Appendix 1B to

provide a report documenting the basis and methodology for establishing ,

protection system trip setpoints and allowable values based on the ISMG

! . effort. The ISMG vorked with General Electric (GE) to develop the

, Instrument Setpoint Methodology Report. This activity culminated in the submittal of GE Topical Report NEDC-31336, " General Electric Instrument i Setpoint Methodology," dated October 1986.

i In a letter dated March 23, 1993,.PNPP was notified that the NRC staff had i completed its review of the GE Topical Report. A copy of the staff's Safety Evaluation on the Topical Report was also provided. Work then commenced on

the PNPP-specific submittal. The results of the calculations and analyses vere submitted to the NRC in a letter dated October 15, 1993 (PY-CEI/NRR-1706L). The letter noted that several calculated Allowable j Values and Trip Setpoints were more conservative than the current Technical

- Specification values, and that changes to the Technical Specifications would 4

be submitted in a future license amendment request. These changes are i detailed below.

{

DESCRIPTION OF PROPOSED CBANGES

!. Note that the new values provided below and in the TS markups in Attachment 2 are rounded from those reported in'the letter dated October 15, 1993

, (PY-CEI/NRR-1706L). Also, the Trip _Setpoints and Allovable Values for the LPCI A, B, and C Injection Valve Permissive were adjusted from those reported in the October 15, 1993 letter, in order to remove head correction factors. This is consistent with the method of specifying other Perry Technical Specification setpoints. Head correction is accomplished in ,

instrumentation calibration instructions. Removal of the head correction l factors masks the changes to the Trip Setpoint and Allovable Value for the l LPCI Injection Vaive Permissive. The values for the Trip Setpoint and  !

, Allowable Value appear-to be raised. However, the values stated in

PY-CEI/NRR-1706L, which include the head correction factors, show that the Trip Setpoint and Allowable Value vere, in fact, lowered. Since the

- function _ provided by the LPCI Injection Valve Permissive is to protect lov 4

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• PY-CEI/NRR-1969L Attachment 1

. - Page 2-of 4 4

pressure LPCI pipe, lowering the Trip Setpoint and Allowable Value increases l

the margin between the rated pipe pressure and the pressure _the pipe would ,

see in an accident. Thus, the proposed changes are more conservative. '

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current Technical Specifications

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! If this amendment is issued prior to implementation of the improved .

- Technical Specifications (Amendment 69), Technical Specification Trip Setpoints and Allovable Values for the following parameters should be revised as noted in Attachment 2: ,

4 (1) Table 3.3.2-2 f

3 Item-2.c,-Main Steam Line Pressure - Lov Allowable Value (psig)

From

2795.0 To: 2795.2

Item 2.d, Main Steam Line Flow - High Allowable Value (psid)

From: $191 To: f189.3 f (2) Table 3.3.3-2 Item A.1.e, Reactor Vessel Pressure - Low (LPCI Injection Valve Permissive)-(for LPCI Pump A)

Trip Setpoint (psig) Allovable Value (psig)

, From: 502.5 + 5, -10 502.5 + 10, -40

(- 492.5 + 507.5) (- 462.5 + 512.5) e To: 2527.18 and $532.82 2490.0 and $537.1 Item A.2.c, ADS Timer Allovable Value (seconds)

From: $117 To: >100.5 and <109.5 Item B.1.c, Reactor Vessel Pressure - Low (LPCI Injection Valve l Permissive) (for LPCI Pump B and LPCI Pump C) .

Trip Setpoint (psig) Allowable Value (psig)

LPCI B From: 508.0 + 5, -10 508.0 +10, -40

(- 498.0 + 513.0) (- 468.0 + 518.0)

i. To: 2527.18 and $532.82 2490.0 and $537.1 a

LPCI C From: 506.6 + 5, -10 506.6 + 10, -40

(- 496.6 + 511.6) (- 466.6 + 516.6)

To: 2527.18 and $532.82 2490.0 and $537.1 4

3

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PY-CEI/NRR-1969L'

- Attachment.1

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• Page 3 of 4 Item B.2.c, ADS Timer Allowable Value (seconds) l From: $117 To: 2100.5 and 3109.5 (3) Table 3.3.9-2

~ Item 1.b,-Containment Pressure - High Allowable Value (psig)

From: $8.85

'To: $8.71 Improved Technical ~ Specifications

- The following Technical Specification Tables in the improved TS format

.(i.e., Amendment 69) should be. revised to reflect the Allowable Values. ,

' listed above (Trip Setpoints are not incorporated in the improved Technical ,

. Specification format):

(1) Table 3.3.5.1-1 Item 1.e, Reactor Vessel Pressure - Low (LPCI Injection Valve Permissive) (for LPCI A subsystem}

Allowable Value (AV) - 2490.0 and $537.1 psig Item 2.d, Reactor Vessel Pressure - Low (LPCI Injection Valve Permissive) (for LPCI B and LPCI C' subsystems}

AV - 2490.0 and $537.1 psig Item 4.b, ADS Initiation Timer AV - 2100.5 and $109.5 seconds 4 Item 5.b. ADS Initiation Timer AV - 2100.5 and $109.5 seconds (2) Table 3.3.6.1-1 i

Item 1.b, Main Steam Line Pressure - Lov AV - 2795.2 psig  ;

. Item 1.c, Main-Steam Line Flov - High 3

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AV - f189.3 psid (3). Table 3.3.6.2-1 Item 2, Containment Pressure - High AV - $8.71 psig i

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PY-CEI/NRR-1969L Attachment 1 Page 4 of 4 SAFETY ANALYSIS The Allovable Values and Trip Setpoints involved with this particular licensa amendment request were developed using methods of analysis conforming to those described in the Topical Report. As provided for in the ISMG methodology, additional vendor data and PNPP-specific field data vere factored into the calculations as they became available. By letter dated July 18, 1995, the NRC staff forwarded a Safety Evaluation presenting the results of their review of the PNPP-specific incorporation of the setpoint methodology. This letter also noted that the commitment contained in USAR Appendix 1B vas considered to be satisfied.

The proposed revised setpoints/ allowable values are more conservative than those currently approved in the Technical Specifications. Therefore, any proposed system or component actuations will occur earlier, resulting in a more conservative plant response. The proposed changes to the Technical Specifications do not introduce any new components nor modify the design of any existing components. Other than making setpoints/allovable values of existing instrumentation more conservative, the change does not affect the design or function of any plant system, structure, or component, nor does it change the way plant systems are operated. Since the proposed revised setpoints are more conservative than the existing values, the margin of safety would be increased by issuance of the changes.

! Calculations are available for inspection at PNPP.

ENVIRONMENTAL CONSIDERATION The proposed Technical Specification change request has been reviewed against the criteria of 10 CFR 51.22 for environmental considerations. As shown above and in Attachment 3, the proposed change does not involve a significant hazards consideration, does not increase the types and amounts of effluents that may be released offsite, and does not significantly increase individual or cumulative occupational radiation exposures. Based on the foregoing, it has been concluded that the proposed Technical Specification change request meets the criteria given in 10 CFR 51.22(c)(9) for a categorical exclusion from the requirement for an Environmental Impact Statement.

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