ML20059H786

Forwards Revised Resolution of Plant-Specific Differing Prof Opinion (DPO) Issues Concerning McGuire Tech Specs, in Support of Completion of Dpos,Per Author 891229 Memo.Actions Re Tech Specs Listed

ML20059H786
Person / Time
Site:	Mcguire, McGuire
Issue date:	09/10/1990
From:	Murley T Office of Nuclear Reactor Regulation
To:	Licciardo R Office of Nuclear Reactor Regulation
Shared Package
ML20059H790	List: ML20059H786 ML20059H795
References
TAC-55435, TAC-55436, TAC-67757, NUDOCS 9009190016
Download: ML20059H786 (14)

Text

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m L SEP 101990 l-Docket Nos. 50-369 and 50-370 MEMORANDUM FOR: Robert Licciardo, Planning, Program and Management Support Branch, PMAS Office of Nuclear Reactor Regulation FROM: Thomas E. Murley, Director Office of Nuclear: Reactor Regulation

SUBJECT:

CLOSURE OF DPO ISSUES REGARDING MCGUIRE TECHNICAL SPECIFICATIONS (TACS 55435/

55436/67757).

In accordance with my memorandum to you of December 29,'1989, the actions the McGuire regarding your ~Differing Technical Specifications Professional = Opinion (DPO) on (TSs) have been completed'or are proceeding have included: to an established resolution plan. These actions (1) Issuance of amendments to the McGuire operating-licenses changing TSs based on plant-specific issues.

The DPO issues resolved in this manner are: identified by Table 1 and are discussed-by Enclosure 1.

(2) Changes updates. to the McGuire FSAR by the licensee's annual discusscd byThese are identified Enclosure 2. by Table 2 and are those changes to the FSAR The licensee in identified has itsstated letter that~

of June 10, 1986, if not already made, arefbeing addressed by the "1989 update" to be issued-in September 1990..

(3) Reevaluations by SRXB and other technical branches: for several plant-specific issues. -Unlike item (1) above,'

s these by taken reevaluations the licensee. determined that no actions need be During these reevaluations the NRC staff has had the benefit of comments by an NRC contractor, the licensee :(who, in turn, reflected the results.ofstaff previous comments reviews. by Westinghouse) and the results of DPO issues resolved by this further evaluation discussed by Enclosureare 3. identified'by Table 3 and are The staff has also had the benefit of your further comments of June 19, 1990, on A. Thadani's memorandum CONTACT: D. Hood, PDII-3/NRR 49-20905 h

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SEP 101990l Distribution See_Next Page of May 14, 1990. -Where appropriate, these further:

comments have been addressed'in Enclosure 3 by adding' clarifications to the: prior resolutions of May,14, 1990 ~

'(dated' April 1990).

(4) Evaluation by OTSB of DPOs based upon generic' issues. . i Issues in this category were evaluated using criteria  ;

given in the Commission's Interim Policy Statement on -!

Technical-Specification Improvement tol determine if they '

should be incorporated.into the Standard Technical' Specifications (STS) for the Westinghouse Owners Group  !

(WOG). For this evaluation, OTSB .7d the benefit of i

extensive-support by NRR technical branches and information from WOG. These issues are identified by Tables- 4 and 5' and are discussed in Enclosure 4.: The j

results generally indicate that.the new STS have addressed'several of the DPO issues, while other DPO concerns need not be added to the'STS because they do.

not qualify under the: Commission's TS: criteria or for.

jl technical reasons.

1 The above actions have addressed all'DPO issues not previously closed by R. Bernero'a memorandum of August 30,'1984.-

Additionally, these previously closed issues (160 in.all) were reviewed in light of events at Diablo Canyon and Vogtle. ~ 'The review found that the original DPO issues regarding mid-loop operation have all been addressed throughEstaff considerations and actions in response to the Diablo Canyon event,Lincluding- 1 resolution of Generic-Issue 36A. . With respect to the Vogtle-event, none of the 160 issues included concerns regarding:' station blackout. Moreover, no reason to re-open anyJof the 160. issues i' was found during the review.

=Accordingly, this completes NRR action on your DPO and.the

~

subject TACS are closed.

geimai.swesori f  ;

Thomas E. Murley, Director Office of Nuclear Reactor Regulation '

i Enclosures As stated (Tables and Enc ures) ~'

LA:PDII-3 PM:PDII-3 D:DS D:DOsA II-3 4 ERossi[dDMatthews A Lainas 4

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DISTRIBUTION: Closure of McGuire DP0 Issues Dated September 10, 1990 g' aselset;'lFi.laba

.~,,4 NRC PDR i Local PDR PDII-3 Reading F. Miraglia J. Partlow S. Varga G. Lainas H. Smith F. Gillespie E. Rossi J. Calvo A. Thadani R. Jones M. Caruso R. Emch K. Desai D. Matthews D. Hood 00072 s _

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DP0 CONCERNS ON MCGUIRE TECHNICAL SPECIFICATION I

TABLE-1 PLANT-SPECIFIC DP0 !$$UES RESOLVED BY TECHNICAL SPECIFICATION ,

AMENDMENT I

TABLE-2 PLANT-SPECIFIC DP0 ISSUES RESOLVED BY UPDATING FSAR i

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

TABLE-5 DP0 ISSUES CONSIDERED AS GENERIC ISSUES RESOLVED BY THE OTSB UNDER TS IMPROVEMENT PROGRAM. (TABLE 5 INCLUDES ISSUES IDENTIFIEDINTABLE4).

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TABLE-?

DP0 CONCERNS ON MCGUIRE TECHNI' CAL SPECIFICATIONS PLANT-SPECIFIC DP0 I,",UES RESOLVED BY TECHNICAL SPECIFICTION APENDfENT QUESTION

• TS SUBJECT TS AMENOMENT NO.

UNIT I UNYT 2 6a Table 3.3-4, Item 4d Steam Line Isolation 102 84

. Trip Setpoint

', 7d Table 3.3-5. Item 2e Contafreent Purge and 102 84 Exhaust Isolation Response Time 7f 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 66 Feedwater Isolation 102 84 Response Time f

15 TS 3/4.5.3 ECCS - Subsystems,(Low The licensee fs in Temperature C...,ncssere process to revise the Protection TS.

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• Questfons numbers are from reference 4 .

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. i TABLE-2  :

i DP0 CONCERNS ON MCr#1RE TECHNICAL SPECIFICATIONS i e PLANT-SPECIFIC DP0 ISSUES RESOLVED BY UPDATING FSAR TS SUBJECT UPDATE REFERENCE  ;

QUESTION

• 1 3

L 4a/4b Table 3.3-2. Items 9/10 Reactor Trfp-Response r5f,:: Page 7.2-15 i t Time i

ac Table 3.3-2 Item 17 Reactor Trip-Response Licensee response dated- i Time M 10, 1986 mode a coeuritment to update the FSAR Table 7.2.1-4. Note e.

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• Questions numbers are from reference 4.

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TABLE-3 ,

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DP0 CONCERNS ON MCGUIRE TECHNICAL SPECIFICATIONS  :

PLANT-SPECIFIC DPC ISSUES REQUIRING NO LICENSEE ACTION

! TS, SUBJECT STATUS QUESTION

• I I Table 2.2-1 Steam Generator-Setpoint Complete - Staff agrees .

with the licensee response and that no licensee action t

required. Enclosore 3 pro-

! vides the details of i resolution.

i la Table 2.2-1. Item 3 Reactor Trip-Setpoint

" " ' I Ib Table 2.2-1, Item 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 i

2 TS Page 3/4.1-6, Minimum Temperature for

(TS3.1.1.4) Criticality i " *

3 Table 3.3-1, Item 6c Reactor Trip Instrumentation

, 5a Table 3.3-3, Item 79 Aox111ery Feeduster Mode Applicability

• Questions numbers are free reference 4 ,

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_ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ = _ _ _ _ _ . - . . _

t TABLE-3 (continued)

QUESTION TS SUBJECT STATUS 6b Table 3.3-4. Items Auxiliary Feedwater-Trip Complete - Staff agrees with j 7c (1) and (2) Setpoints the licensee response and that no Ifcensee action required. Enclosure 3 pro- t vides the details of I j resolut1on.

• i 6c Table 3.3-4, Item 9 Loss of Power-Trip Setpoint * "

4 7a Table 3.3-5, Item 2a Safety Injection (ECCS) - " "

Response Time  :

7b Table 3.3-5 Item 2b Reactor Trip (from SI) * " '

t

- Response Time

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t 7c Table 3.3-5, Item 2d Containment Isolation - " "

. Phase "A" (2) - Response

Time 7e Table 3.3-5. Item 2f- Aux 111ery Feedwater - "

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

Response Tfme 79 Table 3.3-5. Item $b Reactor Trip-Response Time

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TABt.E 3 (continued) i QUESTION TS, SUBJECT STATUS 1

7h Table 3.3-5 Iten 3d Containment Isolation Complete - Staff agrees with i

the licensee response and that no licensee action 1

required. Enclosure 3 ,

~

provides the details of l resolution.

Phase "A" (2) - Response Time l

7J Table 3.3-5, Item 3f Auxiliary Feedwater (5) - " "

Response Time ,

7m Table 3.3-5, Item 5a Containment Spray - Response Time -

l " "

7e Table 3.3-5. Item 12 Automatic Switchover to ,

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Recirculation-Respome Time j

9 TS Page 3/4 4-2 Natural Circulation Cooldown  !

(TS 3.4.1) 11a TS 3/4.5 ECCS 11b TS 3.5 ECCS 11c TS 3.5 ECCS I

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, -4 i Table-3 (continued)

SUBJECT STAT 1f5 .

nUESTION TS

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Cold Leg Injection Accumulator Complete - Staff agrees with 12a Table 3.5.1.1.d Nitrogen Cover Pressure .

the ifcensee response and that no licensee action .

required. Enclosure 3 provides th *-tafIs of resolution.

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12b TS 4.5.1.1.1.1.d.1 Accumulator Relief Valve Setpoints Testing i

13 TS 3.5.1.2.d ifpper Head Injection Accumulator .

TS 4.5.2.h ECCS - Subsystems 14 17 TS 3/4.7.5 Standby Nuclear Service Water Pond 18 TS 3/4.9.1 .

Boron Concentration t

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TABLE-4 DPO CONCERNS ON MCGUIRE TECPJtfCAL SPECIFICATIONS t DP0 ISSUES CONSIDERED AS GENERIC ISSUES RESOLVED BY THE OTS8 I UNDER TS IMrPOVEMENT PP0GR4f QUESTION

• S T_S SUBJECT STATUS Sb Table 3.3-3. Item 8 Automatic Switchover to Complete ,

i Recirculation and loss of Fl5t

{ Cooline (Modes 4 and 5) i Ba TS 3/4.4.1 G.2.6.1 Rapid Reactivity Increase *

in tower Modes '

i 8b TS 3/4.4.1 G.2.6.2 Steam Line 8maks "

i 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 - Het Shutdown i l 16 TS 3.7.I.2.6 , Aux 111ery Feedwater Operability "

! 19 TS 3/4.9.8 Refueling Orarations "

20 TS 4.9.8.2 Refueling Operations "

. l

• Questfons numbers are from m ference 4 i D

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! TABLE 5 DP0 CONCERMS ON PfCGUIRE TECilNICAL SPECIFICATIONS 1 DPO ISSOES CONSIDERED AS GENERIC ISSUES PESOLVED BY THE 0T58 UNDER TS IMPROVEMENT PROGRAM

< MODES CONCERN

• TS_ SUBJECT STATUS APPLICA8ILITY l

9A 3/4.2.5 DPB parameters To be covered in bases 10A 3/4.3.1 Source Range Neutron Flux Ir. proposed STS i (NRC markup) 14A Table 3.3.3 ESFAS instrumentation In proposed STS containment phase "B" (NRC markup) isolation pressure foi-hi Complete

ISA Table 3.3-4 ESFAS trip setpoints Under review I feedwater isolation l

18A 3/4.4 RCS-hot shutdown Under review Shutdowr (Quest. 10) 19A 3/4.4 Cold shutdown with loop Under review Shutdown

- . filled

' Concerns and questions are from references 3 and 4 respectively.

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. mS CONCERN

• S T_S, SUBJECT STATUS

• APPLICABILTTY 29A 3/4.7 a. A W system operability Covered by proposed *

(Quest. 16) b. A W instrumentation STS 30A 3/4.7 MSIV's operao111ty

., Covered by proposed Shutdown STS 31A- 3/4.7 ADV's Covered by new STS l 32A 3/4.7.3 CCW-operability modes 5 & 6 Covered by definition Shutdown of operabillty - no  !

I DN SPEC- Complete 33A 3/4.7.4 SWS-operabillty modes 5 & 6 See 32A i

35A 3/4.9.8 RHR-high water level Under review l

{0uest. 19) .

36A 3/4.9 Refuelfag operations - Under review Shutdown i

(Quest. 20) low water level 38A Table 2.2-1 RTS setpoints - low power in proposed STS reactor trip (NRC merkup) 2_ ___._ . ______.-____-_ - e _ r___ _ _ _ _ ___ _+ --_ _ = _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ . _ _ . _ _ _ _______u_____._ ..m_._____ ._.._ _ m.___.. _ . _ _. _ ... __.u.m__m;

t MODES C_0NCERN* H SUBJECT STATUS AF *.ICARILITY t

3B Table 2.2-1 a. P-7 permissive in proposed STS

b. pressurizer water level (NRC markup) i hioh l

108 3/4.3 P-11 1nterlock Under review  ;

r 128 Table 3.3-3 ESFAS-autoswf tchover on In proposed STS

! (Quest. Sb) RWST 1evel (NRCmarkup) i ISB 3.4.4.1 PCS loops Under mvfew #**

i (Quest. 8a, .

%, &, N, 8 h) 208 3/4.7.5 Ultimate heat sink See 32A Shutdown i

operability reis-6 & 6 218 3/4.9 Refueling operations-low Under mvfew Shutdown water level i *

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