ML17300A651

Forwards Response to Generic Ltr 86-06 Re Implementation of NUREG-0737,TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps. Basis for Adverse Containment Parameters Established from Instrument Accuracy Evaluations

ML17300A651
Person / Time
Site:	Palo Verde
Issue date:	11/24/1986
From:	Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Licitra E Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.05, TASK-TM ANPP-39138-JGH, GL-86-06, GL-86-6, TAC-59412, TAC-64110, TAC-64111, NUDOCS 8612050365
Download: ML17300A651 (18)

Text

REQULATO INFORNATION DISTRIBUTION TEN (RIDS) k ACCESSION NBR: 8612050365 DOC. DATE: 86/j j/24 NOTARIZED:

NO DOCKET 4 FAC IL:STN-50-528 Palo Verde Nuclear Stations Unit ji Arizona Pub li 05000528 STN-50-529 Palo Verde Nuclear Station>

Unit 2i Arizona Pub li 05000529 STN-50-530 Palo Verde Nuclear Stationi Unit 3i Arizona Pub li 05000530 AUTH. NANE AUTHOR AFFILIATION HAYNES, d. G.

Arizona Nuclear Pouer Pro Ject (formerly Arizona Public Serv REC IP. NANE RECIPIENT AFFILIATION LICITRAiE. A.

PWR ProJect Directorate 7

SUB JECT:

Forwards response to Generic Ltr 86-0&i "Implementation of.

NUREQ 0737> TNI Action Item II. K. 3. 5~

Automatic Tri p o1 Reactor Coolant Pumps. " Basis for adverse containment parameters established from instrument accuracy eva luations.

DISTRIBUTION CODE:

A046D COPIES RECEIVED: LTR ENCL SI ZE:

TITLE:

OR Submitt'al:

TNI Action Plan Rgmt NUREG-0737 5, NUREQ-0660 NOTES: Standardized plant. N. Davisi NRR: jCg.

Standardized plant. M. Davis> NRR: jCg.

Standardized plant. N. Davisi NRR: jCg.

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Arizona Nuclear Power Project P.O. BOX 52034

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PHOENIX, ARIZONA85072-2034 Mr. E. A. Licitra, Project Manager PWR Prospect Directorate No.

7 Division of PWR Licensing B

U. S. Nuclear Regulatory Commission 7920 Norfalk Avenue

Bethedsa, MD 20814 November 24, 1986 ANPP-39138-JGH/JBK/98.05

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2 and 3

Docket Nos.

STN 50-528 (License NPP-41)

STN 50-529 (License NPP-51)

STN 50-530 Implementation of TMI Action Item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps" (Generic Letter 86-06)

Pile:

86-010-026 86-A-056-026

Reference:

(A)

Letter from ANPP to U. S.

NRC (

Subject:

Same; ANPP-37467-JGH/JBK/98.05; dated July 24, 1986).

Dear Mr. Licitra:

Reference (A) contained ANPP's response to Generic Letter 86-06's request for a

schedule for submittal of plant specific information regarding implementation of RCP trip strategy.

Attached please find ANPP's response to the four plant specific items contained in the subject Generic Letter.

If you need additional information or have any questions, do not hesitate to call.

JGH/JBK/dim Very truly yours, Cup~

J.

G.

Haynes Vice President Nuclear Production (all w/a) cc0

0. M. DeMichele E. E.

Van Brunt, Jr.

R.

P.

Zimmerman J.

B. Martin A. C. Gehr U. S. Nuclear Regulatory Commission (Original)

Document Control Desk Wasington, D.C.

20555 8612050365 861124 PDR ADOCK 05000528 P

PDR 0III4

'L((

A

ATTACHMENT NRC UESTION l.

Identify the instrumentation to be used to determine the RCP trip setpoints, including the degree of redundancy of each parameter signal needed for the criteria chosen.

ANPP RESPONSE The instrum'entation utilized to determine RCP trip setpoints for the trip-two/leave-two strategy is provided in Table I.

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BRC QUESTION 2.

Identify the instrumentation uncertainties for both normal and adverse containment conditions.

Describe the basis for the selection of the adverse containment parameters.

Address, as appropriate, local conditions such as fluid gets or pipe whip which might influence the instrumentation reliability.

ANPP RESPONSE The instrumentation uncertainties for normal and adverse containment conditions are provided in Table I.

The basis for selection of adverse containment parameters is established from instrument accuracy evaluations and environmental qualifications.

CEN 268'ustification of T2/L2 Reactor Coolant Pump Trip Strategy During Transients,"

provides the basis for the selection of generic trip setpoint parameters during adverse containment conditions.

PVNGS presently utilizes parameters which are equally or more conservative than the generic values presented in CEN 268.

Additionally, CEN 239 and Supplement 1,

"Post Accident Monitoring Instrumentation Accuracy Evaluation,"

provide the detailed instrument accuracy evaluations for each instrument given in Table I except for the subcooled margin monitor and containment radiation monitor.

The subcooled margin monitor's instrument uncertainty is conservatively calculated to be no greater than +40'F.

The environmental qualification for each instrument given in Table I is provided in ANPP's environmental qualification program.

3 ~

In addressing the selection of the criterion, consideration of uncertainties associated with the GEOG supplied analyses values must be provided.

These uncertainties include both uncertainties in the computer program results and uncertainties resulting from plant specific features not representative of the GEOG generic data group.

ANPP RESPONSE The technical Justification for the T2/L2 reactor coolant pump trip strategy is provided in CEN

268, "Justification of,Trip Two/Leave Two Reactor Coolant Pump Trip Strategy 'During Transients."

CEN 268 provides the consideration of uncertainties associated with the supplied analyses values for a generic reference plant.

The T2/L2 RCP trip signals and setpoints were selected on a generic basis to provide a

simple setpoint scheme with enough flexibility to accommodate the plant specific signal and numerical setpoint selection at PVNGS.

The changes to the generic parameters in order to accommodate PVNGS-specific parameters were derived from conservative analysis (e.g.,

CEN 239 and Supplement

1) to ensure the generic parameter's factor of safety was not decreased.

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3.

In addressing the selection of the criterion, consideration of uncertainties associated with the GEOG supplied analyses values must be provided.

These uncertainties include both uncertainties in the computer program results and uncertainties resulting from plant specific features not representative of the GEOG generic data group.

ANPP RESPONSE ANPP is currently addressing the GEOG uncertainty issue with Combustion Engineering and will provide a

formal response upon receipt of the results.

gt t

" NRC UESTION 4 ~

Identify all plant procedures (except

for, those concerning normal operations such as normal cooldown) which require RCP trip guidelines.

Reference to the GEOG EPGs is acceptable if endorsed by the licensee.

Include training and procedures which provide direction for use of individual steam generators with and without operating RCPs.

ANPP RESPONSE Plant procedures which require T2/L2 RCP trip guidelines are based upon the methodology presented in CEN 152 Revision 2, "Combustion Engineering Emergency Procedure Guidelines" (May 1984).

The development of the T2/L2 emergency procedures at PVNGS is illustrated in Figure I.

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TABLE I INSTRUMENTATION UTILIZED TO DETERMINE RCP TRIP SETPOINTS FOR T2/L2 STRATEGY Parameter Normal 172 Error Adverse Actual Total Re uired 3

Number of Channels Degree of Redundanc IWide Range Pressurizer Pressure I

IRCS Hot Leg Temperature

+ 15X

+ 12'F P-102A,B,C,D T-112HA,B,C,D T-1228'A,B,C,D T-112H1,2 T-122H1,2 6/loop 2/loop IRCS Cold Leg Temperature

+ 12'F T-112CA,B,C,D T-122CA,B,C,D T-112C1,2 T-122C1,2 6/loop 2/loop ISubcooled Margin Monitor

+ 40'F-P-102A,B T-112H1,2 T-122H1$ 2 T-112C1$ 2 T-122C1$ 2 1.

Instrument Error is the tolerance appended to a particular instrument's reading by the operator.

2.

Normal conditions apply when containment temperature is less than 200'F; and adverse conditions apply when containment temperature equals or exceeds 200'F.

3.

Only environmentally qualified channels are considered.

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FIGURE I DEVELOPMENT OF T2/L2 EMERGENCY PROCEDURES SCEN 152 Revision 2:

Combust'ion Engineering Emergency Procedure Guidelines.

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I I40AC-9ZZ11:

j I 40AC-9ZZ12:

I 170AC-OZZOl:

I SCEN 268 and I

I SCEN 239 and Emergency Procedure Development Program.

Emergency Procedure Technical Guidelines.

Emergency and Recovery Procedure Verification.

Emergency and Recovery Procedure Validation.

Procedure Writer's Handbook.

Supplement 1:

Justification of T2/L2 RCP Trip Strategy During Transients.

Supplement 1:

Post-Accident Monitoring Instrumentation Accuracy Evaluation.

I

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Diagnostic Aids I

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Optimal Recovery Guidelines l4[1,2,3"]RO-[1,2,3"]ZZ10:

Functional Recovery Guideline.

+The emergency procedures for Unit 3 have not been formally approved as of the date on this letter.

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