ML20247E656

Summary of 890228 Meeting W/Util Re Status of Licensing Issues for Plant.Supporting Info Encl

ML20247E656
Person / Time
Site:	Hatch
Issue date:	03/22/1989
From:	Crocker L Office of Nuclear Reactor Regulation
To:	Matthews D Office of Nuclear Reactor Regulation
References
NUDOCS 8904030198
Download: ML20247E656 (21)

Text

. _ _ _

,,1

.m 1

/

\\

UNITED STATES l'

~1-NUCLEAR REGULATORY COMMISSION h'

y WASHINGTON, D, C. 20666

~I

[,

' March 22, 1989

...e Docket-Nos.: 50-321

~

50-366 MEMORANDUM FOR:-

David D. Matthews, Director Project Directorate 11-3 Division of Reactor Projects -I/II FROM:

Lawrence P. Crocker, Project Manager Project Directorate 11-3 Division of Reactor Projects -I/II

SUBJECT:

MEETING

SUMMARY

On February 28, 1989, a meeting was held with representatives of Georgia Power Company to discuss the status of licensing issues for Hatch Nuclear-Plant. The meeting was held at the plant. provides a list of attendees; Enclosure 2 is the agenda for the meeting.

. Similar meetings have been held on an approximate quarterly schedule to

' assure that all interested parties are generally aware of the outstanding issues that are being worked by. the staff and the relative priority those that are needed by the licensee.

In addition, the meetings have provided a P

forum for the parties to advise each other of forthcoming issues.

At the time of the meeting, both Hatch units were operating at a nominal 100% power.

Unit I had completed a refueling outage in December,1988, with its next refueling outage tentatively scheduled for March 1990. Unit t

2 is scheduled for a refueling outage in September 1989. However Unit I will have an approximately 3-day outage for snubber surveillance this spring and Unit 2 is slated for an approximate 5-or 6-day maintenance outage this spring.

Hatch 2.is the lead BWR in the Technical Specification Improvement Program (TSIP). Enclosure 3 provides the current schedule for the TSIP activities.

The generic BWR topical report is to be submitted in May 1989 followed by the Hatch 2 slant specific submittal in September 1989 and the Hatch I submittal in Decem)er 1989.

Both plant specific packages have a scheduled nine-month review periods. includes a draft for portion of the new TS to show the format.

The licensee also discusaed the Configuration Management Program which was recently been initiated.

The objectives and the tentative work efforts for this program are presented in Enclosure 5.

The outstanding licensing issues with an indication of relative priority are listed in Enclosure 7.

All requests are being reviewed on a schedule ll compatible with the licensee's needs except for the ISI/IST programs and the revision to the suppression pool temperature limits to 110*F.

c 8904030198 890322L PDR ADCCK 05000321 P

PNU; g

2 The'ISI/IST review status is not clear at this time.

Both programs have been under review, but neither shows any signs of early completion.

The=

review of the request to raise the suppression pool temperature limit to 110*F will be handled by a contractor with results not expected for a number of months.

However, the revision to raise the limit to 100 F should be approved prior to the start of the summer season.

The next meeting will be held in about three' months, probably at corporate headquarters in Birmingham.

Original Signed By:

Lawrence P. Crocker, Project Manager Project Directorate II-3 Division of Reactor Projects -I/II Office of Nuclear Reactor Regulation

Enclosures:

As stated i

i l

]f (7

PD I-3 P 11-3 I

l LCrocker:sw pliatthews i

j 3/A}/89 03/7)/sS9 1

____:_____=_______

-l{.

.m.

.Mr. W. G. Hairston', III-Edwin I. Hatch Nuclear Plant, Georgia Power Company Units Nos. 1 and 2 i

cc:

.G. F. Trowbridge, Esq.

Mr. R. P. Mcdonald Shaw, Pittman, Potts and Trowbridge Executive Vice President -

I 2300 N Street, N. W.

Nuclear, Operations

. Washington, D.C.

20037 Georgia Power Company j

P.O. Box 1295

)

Mr. L. - T. Gu cwa -

Birmingham, Alabama 35201-Engineering Department Georgia Power Company Mr. Alan R. Herdt, Chief P. O. Box 1295 Project Branch #3 Birmingham, Alabama 35201 U.S. Nuclear Regulatory Comission 101 Marietta Street, NW, Suite _2900 Nuclear Safety and Compliance Manager Atlanta, Georgia 30323 D

Edwin I. Hatch Nuclear Plant Georgia Power Company P. O. Box 442 Baxley, Georgia 31513 Mr. Louis B. Long.

Southern Company Services, inc.

P. O. Box 1295-Birmingham, Alabama 352C1 Resident Inspector U.S.- Nuclear Regulatory Commission Route:1, Box 725 Baxley, Georgia 31513 Regional Administrator, Region II U.S. Nuclear Regulatory Commission -

101.Marietta Street, Suite 2900 Atlanta, Georgia 30323 Mr. Charles H. Badger Office of Planning and Budget Room 610 270 Washington Street, S.W.

Atlanta, Georgia 30334 Mr. J. Leonard Ledbetter, Commissioner Department of Natural Resources 270 Washington Street, N.W.

Atlanta, Georgia 30334 l

Chairman j

Appling Couaty Commissioners l

County Courthouse Baxley, Georgia 31513

(.,f

.( l_

I'~4 ; Y I

I

,.?

p.

=- 4 4

.: a,

~

f $?

.7_'

f..

r 5

'tf DISTRIBUTION FOR MEETING.

SUMMARY

DATED: March 22, 1989 1

Fa'cilityi. Hatch I/2*'

yW A DotA. 4JJ3e-or C'entraliF11e-J p- (,

.NRC~PDR:

^ J t-i

Lot-l'PDRS-.

PD;;-3 Read _ing:

+' "

T. NurleyL

~

a-12-G-18 12-G-18, J. Sniezek l:

G.; Holohan.,

13-A-2 G. Lainas,'

14-E-4 <-

'E?.Adensam 14-H,3<

D.L Matthews:

.14-H-25' M. Rood

' ~

14-H-25

'L -Crocke'r,,

14-H-25 0GC' 15'-B-18

~E. Jordan'

=MNBB-3302' B'.: Grimes 9-A-2

~J. Henning; RII'-

3 R. Musser RII !

L. Trocine RII

-A. Herdt

-RII ACRS(10)

~P-315 B.~Borchardt'-

17-D-19 i.

L m

-. L._ _ _ _ - - - - _ _ _. -

h-

.. ~ ',

1

-NRC QUARTERLY MEETING

~

February 28, 1989 L

NAME-ORGANIZATION-

. TITLE 1

Steve Tipps GPC Nuclear Safety & Compliance Mgr.

Jim Heidt GPC Mgr. Licensing - Hatch Larry Crocker NRC Project Manager.

John Menning

-NRC Sr. Resident Inspector Randy Musser NRC Resident Inspector-Leigh Trocine:

'NRC Project Engineer Alan Herdt

-NRC Chief, Reactor Projects Branch-I.

h.

.- EncloIura 2z j

l-

-NRC QUARTERLY MEETING FOR HATCH PROJECT

. FEBRUARY 28, 1989 - 1:00.p.m.

AGENDA Plant' Status...............................................S.'B. Tipps TSIP.......................................................J. D. Heidt

- Overview

- Schedule

. Configuration' Management'...................................J.

D. Heidt

...................................S.

B. Tipps Outstanding Submittals.....................................J.

D. Heidt

.....................................S..B.

Tipps

.....................................L. Crocker G3neral' Discussion.........................................All e

e

t;

~Enclorura 3 i

y

.' ' Program Status

+ Generic. Topical Report Submittal"May 1, 1989 p

L

+ Hatch Unit 2 (Lead Plant) Submittal' September-1, 1989

' L 1'

-Independent Verification of Buses-

.(GE,- Bechtel and Southern Services)-

Complete April-1989

-Differenc'es' Comparison

.(Standard Technical Specifications'and Generic)~

Ongoing.

-Sholly Writeup Commence March 1989-

.+ Hatch Unit 1 Submittal December 1989:

+NRC~ Approval Hatch Unit 2 June 1990

+NRC Approva1 Hatch Unit 1 September ~1990

+ Site; Implementation September 1991 l

l

% e l

____________m.

L, 1

y Enclosura 4 I.

q

'{,

TECHNICAL SPECIFICATIONS IMPROVEMENT-PROGRAM l

• NRC/ UTILITY PROGRAM

+ Increase Overall Plant.. Safety

+ Relocate Portions Not Directly,Related to Primary-Safe Operation of Plant

+ Rewrite Considering Human Factors

' Georgia Power Company Program

+ Involved Since Inception of Program

+BWR/4 Lead Plant

-Full Time Participation in Owners Group

-On Site Review of Sections

]

~.

1

____m______

I

A A.C. S:urces - Op; rating K

3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1: A.C. Sources - Operatina l

LCO 3.8.1 The following A.C. Electrical Power Sources shall be OPERABLE:

A.

Two [ physically independent] circuits between the off-site transmission network and the on-site Class IE distribution system, EUQ B.

[Three] independent dieral generators.

APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One of the required A.1 Perform SR 3.8.1.1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> circuits from off-site for remaining required inoperable, circuits from off-site.

AND Once per

-[8] hours thereafter 8HD A.2 Restore required

72. hours from inoperable circuit from discovery of off-site to OPERABLE inoperable status.

circuit from off-site (continued)

BWR/4 3.8-1 2/15/89

=

~

A.C.'Sturces.- Operating-

'.3.8.1~

ACTIONS (continuedi

.y CONDITION REQUIRED ACTION COMPLETION TIME B.

One diesel generatot B.1

. Perform SR 3.8.1.1 for I hour inoperable.

required circuits from off-site.

M.

Once per

-[8] hours thereafter O

1 8.2 Verify required redundant 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> systems, subsystems,.

trains, devices and-components that depend on the OPERABLE diesel generators'as a source of emergency power are OPERABLE.

M B.3.1 ----------NOTES----------

1.

Only required if.

diesel. generator became inoperable for any cause other than preplanned maintenance or testing.

2.

If SR 3.8.1.5 not required to restore inoperable diesel generator to OPERABLE status, Required Action B.3.2 can be i

performed in lieu of l

SR 3.8.1.5.

Perform SR 3.8.15 for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OPERABLE diesel generators.

?

(continued) 1 i

l BWR/4 3.8-2 2/15/89 La

4 A.C. Sources,0perating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and 7 days

- indicated power availability for each of the required circuits from off-site.

SR 3.8.1.2 Verify each fuel day tank contains According to 2 [900] gallons of fuel.

Table 3.8.1-1 SR 3.8.1.3 Verify the fuel storage tanks contain 31 days 2 [32,000] gallons of fuel.

SR 3.8.1.4 Demonstrate each fuel transfer pump 31 days starts and transfers fuel from storage tanks to its day tank.

(continued)

I 4

4 9

4

)

BWR/4 3.8-7 2/15/89 LL__

. i

V

'h-A.C.. Sources - Operating-

s * -

3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY-i SR' 3.8.1.30'

Demonstrate when started simultaneously,

-10' years.

1

[2A and 2C]' diesel generators achieve the-i following voltage'and frequency in

{

< [12] seconds:

~ A.

' Voltage of-[3760] to (4560] volts.

]

B.

Frequency of_[58.0] to (62.0] Hz..

SR 3.8.1.31 For the fuel oil system:

10 years A.

. Drain each_' fuel' oil storage tank..

B.

Remove the sediment from the storage tank.

C.

Clean the storage tank.

1

~ CROSS-REFERENCES TITLE NUMBER ECCS:- Operating 3.5.1

-j

-q l

s.

BWR/4 3.8-17 2/15/89 i

6 c.:

A.C. S:urces'- Operating DRAFT B,3.8. ELECTRICAL PDWER SYSTEMS

'B 3.8.1 A.C. Sources - Doeratino BASES BACKGROUND The A.C. power system consists of the off-site power sources (preferred power) and the on site standby power sources. As required by General Design Criteria 17 (Ref.1), the design of the A.C.-power system provides independence and redundancy to ensure an available source of power to the Engineered Safety Feature (ESF) systems.

l The on-site Class IE A.C. system is divided into redundant load groups so that loss of any one group will not prevent the minimum safety functions from being perfomed.

Each A.C. load group has connections to two preferred (off-site) power supplies and to.a single' diesel generator. Each. diesel generator is exclusively connected to a single 4160-volt load group.

Eight transmission lines supply off-site power.to the on-site 230 kV and 500 kV switchyards. Two electrically and physically separated 230 kV circuits provide power from the switchyard to the 2C and 2D startup auxiliary transformers-(SAT),

respectively.

Primary station distribution voltage.is 4160-volts.

Startup auxiliary transformer 2D provides the normal source of power to the 4160-volt emergency buses 2E, 2F and 2G with SAT l

2C providing an alternate, standby source. During normal operation with the main generator on line, 4160-volt station service buses 2A, 28, 2C and 2D are nesusEy supplied through k.

the two main generator powered, unit auxiliary transformers.

Buses 2A.and 28 supply power to large motors, while buses 2C and 2D supply power to other station auxiliaries requiring A.C.

power. During operation with the main gen m tor off-line, SAT 2C supplies power to 4160-volt buses 2A and 2B, while SAT 2D supplies power to 4160-volt buses 20, 2D,.2E,' 2F and 2G.

During either mode of operation, if any 4160-volt emergency bus loses power, either due to a loss of SAT 2D or to a trip of the normal supply breaker (from SAT 2D), the alternate supply breaker from SAT 2C will close (unless prohibited by an electrical fault interlock) and the 4160-volt buses 2A and 2B supply breakers from SAT 2C will trip open (if clo:ed) and remain interlocked open. This prevents overloading the SAT 2C with non-essentirl loads when it is required to supply emergency loads.

(continued)

BWR/4 B 3.8-1 2/15/89

~

A.C. S:urces - Operating 3.8.1 BASES (continued)

BACKGROUND The on-site standby A.C. power source for Unit 2 c.onsists of (continued) three diesel generator units, which supply standby i

power to 4160-volt emergency buses 2E, 2F and 2G. Diesel generators 2A and 2C supply emergency buses 2E and 2G respectively.

Diesel generator IB is a shared power source and 4

can supply either Unit 1 essential bus IF or Unit 2 emergency bus 2F. The diesel generator starts automatically on LOCA signals (i.e. low reactor water level signal or high drywell pressure signal) and a loss of off-site power signal (i.e. bus i

undervoltage). Additionally, the diesel generator will automatically tie to its respective bus on a loss of off-site power signal.

In accordance with Regulatory Guide 1.9 (Ref. 2), diesel generators 2A and 2C have the following ratings:

2850 kw - continuous 3100 kw - 2000 h 3250 kw - 300 h 3500 kw -

30 min Diesel generator IB has the following ratings:

2850 kw - continuous 3250 kw - 168 h The diesel generators are rated at 4160-volts, three phase, 60 Hz, and are capable of attaining rated frequency and voltage i

within [12] seconds after receipt of a start signal (Ref. 3).

l The ESF systems which are powered from divisional power sources I

are listed in Reference 4.

APPLICABLE The initial conditions of design basis transient and accident SAFETY analyses in the FSAR Chapters (6), Engineered Safety Features ANALYSES and (15), Accident analyses assume all ESF systenis are OPERABLE. The A.C. power system is designed to provide sufficient capacity, capability, redundancy and reliability to ensure the availability of necessary power to ESF systems so that the fuel, reactor pressure vessel and containment-design limits are not exceeded. These limits are discussed in more detail in the BASES for LCO Sections 3.2 (Power Distribution Limits) and 3.6 (Containment Systems).

(continued)

BWR/4 8 3.8-2 2/15/89

n A.C. S:urces - Operating 3.8.1

~

BASES (continued)

APPLICABLE

' The OPERABILITY of the power sources are consistent with then SAFETY initial ' assumptions of the accident analyses'and are based upon.

ANALYSES (1) maintaining'at least one of the on-site A.C. and D.C. power (continued) sources and associated distribution systems OPERABLE during accident conditions,.(2) an assumed loss of off-site power and (3)-a single _ failure of.the other A.C. source.

A.C. Sources - Operating satisfies the requirements of Selection criterion 3 of the NRC Interim Policy Statement on Technical Specification Improvements as documented in Reference 16.

LCOs Two physically independent circuits between the off-site

. transmission network and'the on-site Class IE distribution system, and the [three) independent diesel. generators ensure availability of the required power to respond to accidents and transients and maintain the unit in a safe shutdown condition.

The two circuits are required to be " physically independent" such that a single component fault-(e.g., breaker trip) will not catD both power sources to be lost to one or more 4160-V emergency bus (es). Thus, a physically independent circuit consists of one incoming line'to the 230-kV switchyard ( one of the four lines connecting directly to the 230-kV switchyard or

.the 500/230-kV autotransformer and an associated.500 kV incoming line), a circuit path (including breakers and disconnects) to one energized'startup auxiliary transformer (2C or 20), and a circuit path to the 4160-volt emergency buses 2E, 2F, and 2G (including the associated 4160-volt supply breakers to the essential buses).

APPLICABILITY The A.C. power sources are required to be OPERABLE in MODES 1, 2 and 3 to ensure that:

1.

Acceptable fuel design limits and reactor coolant pressure-boundary limits are not exceeded as a result of anticipated operational occurrences or abnormal transients, and, 2',

Adequate core cooling is provided, and containment integrity and other vital functions are maintained in the event of a postulated DBA.

A.C. power requirements for MODES 4 and 5 are covered in LC0 3.8.2.

(continued)

BWR/4 B 3.8-3 2/15/89

=_

A A.C. Sources'- Operating 3.8.1-4 7

BASES (continued) 4: ACTIONS _

The Required Actions specified for the levels of degradation of

- the power sources provide restrictions upon continued operation commensurate with the level of degradation.

A.I. A.2 With one of the. required off-site circuits inoperable,.

l' sufficient off-site power is available from the other required off-site circuit to ensure that the unit can be maintained in a safe shutdown condition following a design basis transient or t

I accident.

Even failure of the remaining required off-site circuit will not jeopardize a safe shutdown of the unit because of the redundant standby diesel generators. Operation could therefore safely continue if the availability of the remaining sources is verified. However, since the system reliability is degraded below the LCO, a time limit on continued operation is imposed.

To ensure a highly reliable power source, it is necessary to verify the availability of the remaining required off-site circuit on a more frequent basis if one off-site circuit is inoperable. The availability of the remaining required off-site circuit must be verified within I hour and once per

[8] hours thereafter until the inoperable off-site circuit is restored to OPERABLE status.

- Per Regulatory Guide 1.93 (Ref. 5), power operation may continue for a period that should not exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

If' source is not restored within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, a controlled shutdown must be initiated per Required Actions F.1 and F.2.

B.1. B.2. B.3. B.4 With one diesel generator inoperable, sufficient A.'. power C

sources remain available to ensure safe shutdown of the unit in the svent of a transient or accident without a single failure.

Operation could therefore safely continue for a short period of time if the availability of the remaining sources is verified.

Completion times are consistent with those of Condition A.

(continued) 1 BWR/4 B 3.8-4 2/15/89

/p;

'l*

A.C. Sturces -;0perating 3.8.1

'~

BASES (continued)

ACTIONS-B.1. B.2. B.3. B.4 (continued)

(continued)'

The specific list of equipment encompassed by Required Action B.2 is provided in ([ Table B 3.8.1-1], [ Reference 6]). This requirement.is intended to provide assurance that a loss of-off-site power, during the period that one diesel' generator is inoperable, will not result in a complete loss of safety function of critical systems. The term. verify, as used in this.

context, means to administrative 1y check, by examining logs or other information, to determine if certain components are out of service for maintenance or other reasons.

It does not mean to perform the surveillance requirements needed to demonstrate the OPERABILITY of the component.

Required Action B.3 provides' an allowance to avoid unnecessary testing of the OPERABLE diesel generator when a diesel generator is declared inoperable because of a component which can be tested independently to restore the inoperable diesel generator to OPERABLE status.

Regulatory Guide 1.108 (Ref. 7) defines the diesel generator unit as consisting 6f the engine, generator, combustion air system, cooling water system up to the supply, fuel oil supply system,' lubricating oil system, starting energy sources, auto start controls, manual controls and the diesel generator breaker. There are many potential failures of diesel generator subsystems that could cause a diesel generator to become inoperable and therefore, ' require.

all OPERABLE diesel generators be demonstrated OPERABLE but'do not require starting and loading the inoperable diesel generators-to restore it to OPERABLE status.

Inoperabilities of diesel generators caused by failures.of. equipment that are

'1 not part of the defined diesel generator unit are categorized as invalid failures in accordance with Regulatory Guide 1.108 since the failure would not have prevented.the diesel generator from performing its intended safety function in an emergency.

As such, they do not impact the technical specification surveillance frequency of the diesel generator that failed.

Likewise, there should be no reason to require additional testing of OPERABLE diesel generators to determine if the same invalid failure mode exists.

(continued)

BWR/4 8 3.8-5 2/15/89 J

i

7 q

.itnclosurs 5

]

OmFIGURATICN ENAGEMENT PPOGRAM

. CONFIGURATION MANAGEMENT PLAN A ' Configuration Management Program ensures that: the following objectives are

.I achieved throughout the life of the plant for both safety-related-and non-safety related hardware and documents:

Objective A.

The design basis of the plant has been

)

established, documented, maintained, and l

retrievable.

I Objective B.

Plant physical structures,. systems, components, and comptner software conforms to the approved design requirements.

Obj ecti ve. C.

The plant's physical and functional characteristics are accurately' reflected in the plant documents (e.g. Procurement, operating, maintenance, testing, and training).

-Objective D.

' Plant changes are minimized through an integrated review and approval process with established approval criteria.

Objective E.

Proposed changes to plant hardware and l

documents are fully evaluated to determine their impact on~other hardware _and documents.

Objective F.

Proposed changes to plant hardware and documents are reviewed and-approved by the proper authorities prior to implementation.

Objective G.

Consistency is maintained between plant documents (e.g. design, procurement, operating, maintenance, testing, and training).

i O

+.

l CONFIGURATION' MANAGEMENT PROGRAM - SCOPE L

• Phase 1

-+ Complete System Evaluation Documents

+ Complete Distribution Panel and MCC Review

+ Complete Control Room Panel Review

+ Assess' Program

-Scope

-Priorities

• Phase 2 (Tentative)

+ Procedural and Design Control Enhancements

+ Pilot Design Basis Documents

• Phase 3 (Tentative)

+ Perform Safety System Functionals

+ Complete Design Basis Documents s.

. Vc

. CONFIGURATION' MANAGEMENT-DISPOSITION OF DISCREPANCIES l4:

Evaluation Engineering

+

+ Safety

-+ Deportability i

i i

1

__-________.___-___m___...__.-____-_.___m___..___.m__

9

(

9 ENCLOSURE PLANT HATCH - UNITS 1, 2 4

NRC 00CKETS 50-321, 50-366 OPERATING LICENSES OPR-57. NPF-5 OUTSTANDING LICENSING SUBMITTALS Letter Hatch Date Unit _,

subiect 03/27/86 1,2 Proposed Change to Technical Specifications E ualizing Reactor Protection System S ecifications Between Units 02/24/88 1,2 Revised Inservice Inspection and Testing Pro 9 tam

• 05/13/88 1,2 Request to Revise Technical Specifications' - MSIV Closure Time Requirements 05/13/88 1,2 Request to Revise Technical Specifications Suppression Pool Temperature Limits (110'F) 09/06/88 1,2 Request to Revise Technical Specifications Suppression Pool Temperature Limits (100*F)*

09/06/88 1

Request to Revise Technical Specifications Hydrostatic and Leak' Testing Above 212*F Using Non-Nuclear Heat 10/25/88 1.2 Exemption Request - Worker Respiratory Protection Apparatus 01/23/89 2

Request to Revise Technical Specifications - MSIV Local Leak Rate Test Requirements

• 02/03/89 1.2 Request to Revise Technical Specifications - Valve Stroke Times and Selected Leak' Rate Test Requirements

• High Priority Item 0032V HL-348 E-1 i