ML20042H017

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Discusses Resolution of plant-specific Differing Prof Opinion Issues Re Tech Specs.Issues Involve Definition of ESFAS Instrumentation Trip Setpoints & Inconsistencies in Feedwater Isolation Response Times
ML20042H017
Person / Time
Site: Mcguire, McGuire, 05000380  Duke Energy icon.png
Issue date: 05/14/1990
From: Thadani A
Office of Nuclear Reactor Regulation
To: Varga S
Office of Nuclear Reactor Regulation
Shared Package
ML20042H018 List:
References
NUDOCS 9005170058
Download: ML20042H017 (14)
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UNITED $TATES

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May 14, 1990 MEMORANDUM FOR:

Steven A. Varga, Director Division of Reactor Projects - 1/II FROM:

Ashok C. Thadani, Director Division of Systems Technology

SUBJECT:

T 0 0L'di10N OF PLANT-SPECIFIC DP0 ISSUES CONCERNING MCGUIRE TECHNICAL SPECIFICATION.5 i

Dr. Thomas Murley's memorandum dated December 29, 1989, identified the scope ofworktoresolvethedifferingofprofessionalopinion(DPO) issues concerning McGuire Technical Specifications. The Reactor Systems Branch was assigned the responsibility to resolve all the plant-specific DP0 issues by April 1990. The Technical Specifications Branch (OTSB) will complete the evaluation of all DP0 generic issues by June 1990.

PD 11-3 will issue the i

i final consolidated report by July 1990. The Director, DST, will coordinate the overall foregoing actions.

Plant-Specific DP0 issue - SRXB The licensee provided their response to the plant-specific DP0 issues in their submittal dated June 10,1986 (Ref. 4). The licensee responded to 51 DP0 l

issues in their submittal. Out of 51 issues, the licensee concluded that 41 l

issues are plant-specific and 10 issues are generic in nature, in performing our review of the plant specific issues, we have discussed them with Robert Licciardo, NRR reviewers of various branches, (SRXB, SPLB, SICB, SELB, EMEB, and PRPB) and the licensee, For the most part, the issues involved inconsistencies between the FSAR safety analysis values, technical specifica-tions values and the setpoint methodology report values.

Resolution of these 41 issues involved disposition in one of the following categories:

(1) Plant-specific issues resolved by Technical Specification Amendment as j

l listed in Table-1.

(2) Plant-specific issues resolved by updating the FSAR as listed in Table-2.

(3) Plant-specific issues determined not to require any action by the licensee as listed in Table-3.

The 10 generic _ issues identified by the licensee in their submittal will be resolved by the OTSB under the Technical Specifications Improvement Program by June 1990. These issues are listed in Table-4.

Each plant-specific issue and its resolution are discussed in detail in j

l Enclosures 1, 2, and 3.

These enclosures provide the resolution of the issues

Contact:

K. Desai, SRXB, x21058 m

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o Steven A. Yarga May 14, 1990

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1 as listed in the Tables 1, 2, and 3 respectively. This completes our efforts on the DP0 plant-specific issues.

l Generic DP0 1ssues - OTSB Table-S lists all generic issues including the issues identified in Table-4.

licability, either extending the mode Most of the issues deal with mode app (Modes 5 and 6) or applyinc the LCO to i

ap)1icability to the shutdown inodes otter modes. A few may require changes to actions taken whe: LCOs are not i

met while others may require changes to surveillance requirements or the d

Bases. One issue requires a new Technical Specification, 0TSB has resolved these generic issues by either incorporating as LCO, action statements, or part of Bases Section at this time. The staff dispositions may change due to the interaction with the Owners Groups under the TS improvement These changes will be noted as a follow-up to the DP0 resolution.

program.

OTSB will provide their evaluation report by June 1990.

hbv Asho C. Thadani, Director Divi ion of Systems Technology

Enclosures:

As stated cc: See next page 1

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T. Murley i

F. Miraglia W. Russell l

A. Thadani G.'Laines B. Boger t

'G. Holahan i

C. Rossi J. Calvo 1

0. Matthews 1

S. Newberry

'J. Mauck i

F. Rosa C. McCracken l'

J. Kudrick R. Licciardo L. Marsh I

D. Hood R. Giardina l

T. Collins L. Phillips P. VanDoorn, SR]

PDR j

SRXB Members l-t f

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DP0 CONCERNS ON MCGUIRE TECHNICAL SPECIFICATION i

TABLE-I PLANT-SPECIFIC DP0 ISSUES RESOLVED BY TECHNICAL SPECIFICATION AMENDMENT TABLE 2 PLANT-SPECIFIC DP0 ISSUES RESOLVED BY UPDATING FSAR j

TABLE-3 PLANT-SPECIFIC CPO ISSUES REQUIRING NO LICENSEE ACTION TABLE-4 DP0 ISSUES CONSIDERED AS GENERIC ISSL'ES TO BE RESOLVED BY THE OTSC UNDER TS IMPROVEMENT PROGRAM (LICENSEE IDENTIFIED THESE ISSUES IN THEIR SUBMITTAL DATED JUNE 1986).

TABLE-5 000 ISSUES CCNSIDERED AS GENERIC ISSUES TO BE RESOLVED BY THE OTSB UNDER TS IMPROVEMENT PROGRAM.

(TABLE S INCLUDES ISSUES IDENTIFIED IN TABLE 4).

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DP0 CONCERNS ON MCGUIRE TECHNICAL SPECIFICATIONS PLANT-SPECIFIC DP0 ISSUES RESOLVED BY TECHNICAL SPECIFICTION AMENDMENT QUESTION

  • TS_

SUBJECT TS AMENOMENT NO.

UNIT I UNIT 2 6a Table 3.3-4, Item 4d Steam Line Isolation 102 E4 Trip Setpoint 7d Table 3.3-5 Item 2e Contalment Purge and 102 84 Exheust Isolation Response

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Time 71 Table 3.3-5 Item 3e 102 84 7k Table 3.3-5 Item 4e 102 84 71 Table 3.3-5 Item 4h Steam Line Isolation 29 10 Response Time 7n Table 3.3-5. Item 6b Feedwater Isolation 102 84 Response Time 4

15 TS 3/4.5.3 ECCS - Subsystems (Low The licensee is in Temperature Overpressure process to revise the Protection TS.

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  • Questfons numbers are from reference 4.

TABLE-2 DP0 CONCERNS ON P'CGUIRE TECilNICAL SPECIFICATIONS PLANT-SPECIFIC DP0 ISSUES RESOLVED BY UPDATING FSAR DUESTION*

H SUBJECT UPDATE REFERENCE 4a/4b Table 3.3-2. Items 9/10 Reactor Trip-Response FSAR Page 7.2 Time 4c Table 3.3-2. Item 17 Reactor Trip-Response Licensee response dated Time June 10, 1986 made a cosuiitment to update the FSAP Table 7.2.1-4, Note e.

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  • Questions numbers are from reference 4.

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e-TABLE-3 DP0 CONCERNS ON MCGUIRE TECHNICAL SPECIFICATIONS PLANT-SPECIFIC DP0 ISSUES REQUIRING NO LICENSEE ACTION QUESTION

  • 3 SUBJECT STATUS 1

Table 2.2-1 Steam Generator-Setpoint Complete - Staff agrees with the licensee response and that no licensee action required. Enclosure 3 pro-vides the details of resolution.

la Table 2.2-1, Item 3-Reactor Trip-Setpoint Ib Table 2.2-1. Ite.; 4 Reactor Trip-Setpoint Ic Table 2.2-1 Item 9 Reactor Trip-Setpoint Id Table 2.2-1 Item 13 Reactor Trip-Setpoint le Table 2.2-1, Item 18b Reactor Trip-Setpoint 2

TS Page 3/4.1-6, Minimum Temperature for (TS 3.1.1.4)

Criticality 3

Table 3.3-1, Item 6c Reactor Trip Instrumentation Sa Table 3.3-3. Item 79 Auxiliary Feedwater Mode Applicability

  • Questions numbers are from reference 4.

e TABLE-3 (contine<!)

QUESTION

_TS SUBJECT STATUS-6b Table 3.3-4, Items Auxiliary Feedwater-Trip Complete - Staff agrees with 7c (1) and (2)

Setpoints the ifcensee response and that no licensee action required. Enclosure 3 pro-vides the details of resolu*.fon.

6c Table 3.3-4, Item 9 Loss of Power-Trip Setpoint 7a Table 3.3-5, Item 2a Safety Injection (ECCS) -

Response Time 7b Table 3.3-5 Item 25 Reactor Trip (from SI) i

- Response Time 7c Table 3.3-5 Item 2d Containment Isolation -

Phase "A" (2) - Response Time 7e Table 3.3-5 Item 2f Auxiliary Feedwater -

Response Time 7f Table 3.3-5,-Item 3a Safety Injection (ECCS) -

Response Time 79 Table 3.3-5, Item 3b Reacter Trip-Response Time -.

TABLE.3 (continued)

QUESTION TS SUBJECT STATUS 7h Table 3.3-5 Item 3d Containment Isolation Complete - Staff agrees with the licensee response and that no licensee action requirec. Enclosure 3 provides the details of resolution.

Phase "A" (2) - Response Time 7j Table 3.3-5, item 3f Auxiliary Feedwater (5) -

Response Time 7m Table 3.3-5, Item Sa Containment Spray - Response Time 70 Table 3.3-5, Item 12 Automatic Switchover to Recirculation-Response Time 9

TS Page 3/4 4-2 Natural Circulation Cocidown (TS 3.4.1) 11a TS 3/4.5 ECCS 11b TS 3.5 ECCS 11c TS 3.5 ECCS _ _ _ _

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Table-3 (continued)

OUESTION T_S SUBJECT STATUS S

12a Table 3.5.1.1.d Cold Leg Injection Accumulator Complete - Staff agrees with Nitrogen Cover Pressure the licensee response and that no licensee action-

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required. Enclosure 3 provides the details of resolution.

12b TS 4.5.1.1.1.1.d.1 Accumulator Relief Yalve Setpoints Testing 13 TS 3.5.1.2.d ifpper Head Injection Accumulator 14 TS 4.5.2.h ECCS - Subsystems 17 TS 3/4.7.5 Standby Nuclear %rvice Water Pond 18 TS 3/4.9.1 Boron Concentration i

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TABLE A DP0 CONCERNS ON MCGUIRE TECP.NICAL SPECIFICATIONS DP0 ISSUES CONSIDERED AS GENERIC 'SSifES TO BE RESOLVED BY THE 0758 UNDER TS IMPROVEMENT PROGRAM i

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QUESTION

  • _T_S SUBJECT STATUS S

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Sb Table 3.3-3 Item 8 Automatic Switchover to Open Recirculation and Loss of RHR l

Cooling (Modes 4 and 5) l 8a TS 3/4.4.1 G.2.6.1 Papid Reactivity Increase l

in Lower Modes 8b TS 3/4.4.1 G.2.6.2 Steam Line Breaks 8c TS 3/4.4.1 G.2.6.3 Loss of Primary Coolant 8d TS 3/4.4.1 G.2.6.4 Increase in RCS Temperature 8e TS 3.4.1 RCS Loops 10 TS Page 3/4 4-3 RCS - Hot Shutdown 16 TS 3.7.1.2.6 Auxiliary Feedwater Operability 19 TS 3/4.9.8 Refueling Operations 20 TS 4.9.8.2 Refueling Operations

  • Questions numbers are from reference 4.

TAPLE 5 DP0 CONCERNS ON MCGUIRE TECliNICAL SPECIFICATIONS DP0 ISSUES CONSIDERED AS GENERIC ISSUES TO BE PFSOLVED BY THE OTSB UNDER TS IMPROVEMEMT PROGRAM MODES l

CONCERN

  • TS SUBJECT STATUS APPLICABILITY 9A 3/4.2.5 DNB parameters To be covered in bases 10A 3/4.3.1 Source Range Neutron Flux Ir, proposed STS (NRC markup) 14A Table 3.3.3 ESFAS instrumentation In proposed STS containment phase "B" (NRC markup) isolation pressure hi-hi 15A Table 3.3-4 ESFAS trip setpoints Under review feedwater isolation IPA 3/4.4 RCS-hot shutdown Under review Shutdown (Quest. 10) l 19A 3/4.4 Cold shutdown with loop Under review Shutdown ff11ed
  • Concerns and questions are from references 7 and 4 respectively.

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PODES CONCERN

  • T_S SUBJECT STATUS APPLICABILTTY S

29x 3/4.7

a. AFW system operability Covered by proposed (Ques?. 16)
b. AFW instrumentation STS 30A 3/4.7 MSIV's operability Covered by proposed Shutdown STS 31A 3/4.7 ADV's Covered by new STS 32A-3/4.7.3 CCW-operability modes 5 & 6 Covered by definition Shutdown of operability - no n*w spec.

33A 3/4.7.4 SWS-operability modes 5 1. 6 See 32A 35A 3/4.9.8 RHR-high water level Under review (Cuest. 19) 36A 3/4.9 Refueling operations -

Unoer review Shutdown-(Guest. 20) low water level 38A Table 2.2-1 RTS setpoints - low power In proposed STS reactor trip (NRC markup). - - _ -.- -

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CCNCERN*

H SUBJECT STATUS-APPLICARIL TTY 3B Table 2.2-1

a. P-7 permissive' In proposed STS
b. pressurizer water level (hRC markup) high 108 3/4.3 P-11 interlock Under review I

l 128 Table 3.3-3 ESFAS-autoswitchover on In prc, posed STS (Quest. Sb)

RWST 1evel (NRC markup)

ISB 3.4.4.1 PCS loops Under review (Quest. Ba, ab, ac, Bd. & se) 208 3/4.7.5 Ultimete heat sink See 32A Shutdown operability sedes 5 & 6 218 3/4.9 Refueling operations-low Under review Shutdown water level 4 f n

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