ML20245B890

License NPF-82,authorizing Operation of Core Levels Not to Exceed 2,436 Mwt

ML20245B890
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	04/21/1989
From:	Murley T Office of Nuclear Reactor Regulation
To:
Shared Package
ML20245B887	List: ML20245B885 ML20245B890 ML20245B895 ML20245B896
References
NUDOCS 8904260347
Download: ML20245B890 (17)

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, h* ** Coq fi k UNITED STATES NUCLEAR REGULATORY COMMISSION 5 E WASHINGTON, D. C. 20666 p

'+,. . . . . ,o LONG ISLAND LIGHTING COMPANY DOCKET NO. 50-322 SHOREHAN NUCLEAR POWER STATION, UNIT 1 FACILITY OPERATING LICENSE License No. NPF-82

1. The Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A .- The application for a license filed by the Long Island Lighting Company (the licensee) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I, and all required. modifications to other agencies or bodies have been duly made; B. Construction of the Shoreham Nuclear Power Station, Unit 1 (the facility), has been completed in conformity with Construction Permit No. CPPR-95 and the application, as amended, the provisions of the Act, and the regulations of the Comission; C. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission (except as exempted from compliance in Section 2.D below);

D. There is reasonable assurance: (i)thattheactivitiesauthorized by this operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Cha Section 2,0 below);pter I (except as exempted from compliance in E. The licensee is technically qualified to engage in the ectivities authorized by this operating license in accordance with the j Comission's regulations set forth in 10 CFR Chapter I; j F. The licensee has satisfied the applicable provisions of 10 CFR 140,

" Financial Protection Requirements and Indemnity Agreements," of the Comission's regulations; G. The issuance of this license will not be inimical to the comon defense and security or to the health and safety of the public; j l

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H. After weidhing the environmental, ecot%mic, technical, and other benefits of the facility against environmental and other costs and considering available alternatives, the issuance of Facility Operating License No. NPF-82, subject to the cor.ditions for protection of the environment set forth in the Environmental Protection Plan attached as Appendix B, is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied; and I. The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40, and 70.

2. Based on the foregoing findings and the Concluding Initial Decision i issued by the Atomic Safety and Licensing Board on September 23, 1988, N '

Facility Operating License No. NPF-82 is hereby issued to the Long Island Lighting Company (the licensee) to read as follows:

A. This license applies to the Shoreham Nuclear Power Station, Unit 1, a boiling water nuclear reactor and associated equipment, owned by the licensee. The facility is located in Suffolk County, New York, and is described in the licensee's Updated Safety Analysis Report, (USAR) as supplemented and amended, and the licensee's Environmental Report, as supplemented and amended.

B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses the Long Island Lighting Company (LILCO, thelicensee):

(1) Pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use, and operate the facility at the designated location in Suffolk County, New York, in accordance with the procedures and limitations set forth in this license; (2) Pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Updated Safety Analysis Report, as supplemented and amended; 1/ See also: Partfal Initial Decision, LBP-83-57, September 21, 1983; X N 758, October 31, 1984; Commission Me:noranium and Order, CLI-84-21, November 21, 1984; Memorandum and Order Ruling on Remand Issues, LBP-84-53, November 30, 1984; Partial Initial Decision on Emergency Diesel Ger,eratnrs, 85-18, June 14, 1985; Partial Initial Decision on Emergency Plannin0 (EP), LBP-85-12, April 17, 1985; Concluding Partial Initial Decision on EP, LBP-85-31, August 26, 1985; LBP-87-30, November 6, 1987; CLI-87-12, November 5, 1987; Partial Initial Decision (EP), LBP-88-12, May 5, 1988; LBP-88-24, September 23, 1988; CLI-89-02, March 3, 1989.

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(3) . Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed neutron sources for resctor. instrumentation and radiation monitoring equipment calibration, and as fission detectors in l

, amounts as required; (4) Pursuant to the Act'and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source -

or special nuclear material without restriction to chemical or physical form, for samp'a analysis or instrument calibration or associated with radioactive apparatus or components; and (S) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess; but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C.- This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in.10

'CFR. Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect except as exempted from compliance as described in Section 2.D. below; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The licensee is authorized to operate the facility at core power levels not to exceed 2,436 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein and other. items identified in Attachments 1 and 2 to this license. The items identified in Attachments 1 and 2 to this license shail be completed as specified. Attachments 1 and 2 are hereby incorporated into this license.

(2) Technical Specifications and Environmental Protection Plan k 1

The Technical Specifications contained in Appendix A and the f Environmental Protection Plan contained in Appendix B, are i hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3) F' ire Protection Program (Section 9.5, SER, SSER1, SSER2, SSER9)

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The licensee shall maintain in effect all provisions of the approved fire protection program as described in the Fire Hazards Analysis Report and the Updated Safety Analysis Report for the facility through Revision 33 and as approved in the SER and Supplements 2 and 9, subject to the following provision:

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4 The licensee may make changes to the approved fire protection program without prior approval of the Comission only if these l changes would not adversely affect the ability to achieve and  ;

maintain safe shutdown in the event of a fire.  !

(4) Flux Monitor (Section 22, SER) I The licensee shall implement (installation or upgrade) provisions of Regulatory Guide 1.97 for flux monitoring prior to startup following the first refueling outage.

(5) Instrumentation and Controls Systems Required for Safe Shutdown (Section 7.4.3 55ER3, 55ER4, 55ER8) prior to startup following the first refueling outage, the licensee shall implement and document all of the required )

design changes discussed in Attachment.1 and shall perform an )

acceptable procedure verification test for the remote shutdown I system design.

(6) Steam Condensing Mode of RHR (Section 3.8.2 SER, SSER1, SSER3, SSER4)

The licensee shall'not operate th'e residual heat removal (RHR) system in the steam condensing mode.(SCM) during any normal plant operations.

(7) Emergency Diesel Generator License Condition (Section 8.3 SSER 9)

The license conditions described in Attachment 2 apply to the operation, maintenance, testing, and inspection of Emergency Diesel Generators EDG-101, 102, and 103 at Shoreham. With the imposition of these conditions, the Comission has determined that the facility satisfies the requirements of General Design Criterion 17 (GDC-17) for the first cycle of operation. Prior to startup following the first refueling outage, the licensee shall submit the results of additional tests, inspections, and/or analyses that taken together with the nuclear industry' '

experience with TDI diesels up to tnat time demonstrate to the satisfdctionoftheNRCstaffthatthefaciIitywillconcinue to settsfy the requirements of GDC-17 for the second fuel cycle and beyond.

(8) Fission Gas Release and Ballooning and Rupture (Sections 4.2.3.2 and 4.i.'T T 5EMJ The licansee shall submit for NRC revtew and approval a reanalysis of the Emergency Core Cooling System (ECCS) performance for the second cycle and beyond utilizing models that (a)

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>- account'for the effects of high burn-up fission gas release ana prepressurized fuel and (b) accommodate the information in i

NUREG-0630' including its effects on local oxidation.

(9) Strike Shutdown License Condition (Section 13.3.5.7 SSER 10)

Since the licensee relies on an offsite emergency response organization consisting entirely or primarily of the licensee's

. employees, in anticipation of the commencement of any strike by such employees, the licensee shall bring the facility to cold shutdown. condition'using normal-operating procedures. .The licensee shall commence bringing.the: facility to cold shutdown condition 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the commencement of such strike, or .

immediately_upon receipt.of less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />' notice of.the L impending commencement Jf a strike, with the goal of having the  ;

plant in cold Lshutdown. condition by the time the strike i commences. The licensee shall maintain the facility in a cold shutdown condition-until the strike is over and review by the.

. Federal. Emergency Management Agency and the NRC Staff has given U assurance that the Local Emergency Response Organization ,

capability. is . fully restored. During a' strike-occasioned 1

. shutdown, with the prior approval of the NRC Staff upon review of written application by'the. licensee, the licensee shall be

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permitted to take the reactor to a refueling mode to conduct.

refueling or.other operations requiring access to the reactor core if it is shown that such operations cannot result in the occurrence of any events requiring offsite emergency response ';

capability. This condition shall be terminated only in accordance with the regulatory procedures for amendment of an operating license.  ;

(10)~ Hurricane Shutdown License Condition (NRR Director's Finding Re: EP Dated 4/17/89) '

If the National Weather Service issues a hurricane watch for the Long Island, New York area, the licensee, within I hour, shall begin to make necessary preparations to place the reactor into a HOT SHUTDOWN condition. The licensee shalf continue to monitor the National Weather Service advisories hourly until the watch is cancelled. If the National Weather Service issues a hurricane warning for the Long Island, New York area, the licensee will take action to ensure that the reactor is in a HOT SHUTDOWN condition within the next 24 hears, unless the warning is  !

cancelled. The licensee shall maintain the reactor in this condition until the National Weather Service has cancelled its hurricane warning.

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(11) County Liaison License Condition (NRR Director's Finding Re: EP Dated 4/17/89)

The licensee shall modify its offsite emergency plan to require that a LILCO representative, knowledgeable of the offsite emergency plan, upon declaration of an Alert, Site Area Emergency or General Emergency at the Shoreham site, transport the offsite emergency plan, appropriate support information and necessary communications equipment to the Suffolk County Emer-gency Operations Center (E0C) oc to a location designated by the Suffolk County Executive. This person shall be available to aid and assist the County Executive in responding to the emergency condition at Shoreham.

(12) Brentwood Staffing License Condition (NRR Director's Finding Re: EP Dated 4/17/89)

The luensee shall modify its offsite emergency plan to designate at least one trained person who shall be at the Brentwood facility at all times during plant operations above i 5 percent rated power. This person will begin the conversion process of the Brentwood facility into the Local Emergency Response Organization (LERO) Emergency Operations Center (EOC) when an Alert or higher emergency class is declared.

(13) Quarterly Drills License Condition (NRR Director's Finding Re: EP Dated 4/17/89)

The licensee shall conduct training drills such that its offsite emergency plan is drilled quarterly with full or partial participation by the Local Emergency Response Organization (LERO).

D. The facility requires exemptions from certain requirements of Appendices A and J to 10 CFR Part 50. These include: (a) exemption from GDC 56, the installation prior to startup following the first refueling outage of two isolation barriers in series in all instrument lines penetrating containment that are not part of the automatic reactor protection system (Section 6.2.3, SER, SSER 1, SSER 3, SSER 4, SSER 8); (b) exemption from the requirement of paragraphs II.H.4 endix J, the leak rate testing of the Main Steam and III.C.2 Isolation of App (MSIVs) at the peak calculated containment pressure, Valves P and exemption from the requirements of paragraph III.C.3 of A$p,endixJthatthemeasuredMSIVleakratesbeincludedinthe summation for the local leak rate (Section 6.2.5.1 of the SER and SSER 8); (c) exemption until startup after the first refueling outage from GDC 19, that the remote shutdown system design should

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a provide redundant safety-grade capability to achieve and maintain hot shutdown and subsequently cold shutdown from a location or locations remote from the control room, assuming no fire damage to any required systems and equipment and assuming no accident has occurred (Section 7.4.3 of SSER 3, SSER.4, and SSER 8); and (d) temporary exemption from the requirement of 10 CFR 50.44(c)(3)(i) for containment inerting so that' operation of the plant with a non-inerted containment may continue during the remainder of the initial startup test program for 120 full effective power days from initial criticality (Section 6.2.4 of.SSER9).

These exemptions are authorized by law and will not endanger. life or property or the common defense and security and are otherwise in the public interest. Therefore these exemptions are hereby granted pursuant to 10 CFR 50.12. With the granting of these exemptions the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.

E. The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled:

"Shoreham Nuclear Power Station Physical Security Plan," with revisions submitted through December 20, 1988; the "Shorenam Nuclear Power Station Guard Training and Qualification Plan,"

with revisions submitted through December 14, 1983; and "Shoreham Nuclear Power Station Safeguards Contingency Plan," with revisions sub'nitted through May 13, 1988. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein, i F. Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, the licensee shall report any violations of the requirements centained in Section 2.C of this license in the followin initial notification shall be made within twenty four (24)g manner: hours to the NRC Oparations Center via the Emergency Notification System with written followup within 30 days in accordance with the procedures described in 10 CFR 50.73(b), (c),

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G. The licensee shall have and maintain financial protection of such l type and in such amcunts as the Commission shall require in l accordance with Section 170 of the Atomic Energy Act of 1954, as l amended, to cover public liability claims.

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" H. This license supersedes Facility' Operating License No. NPF-36, dated

, July 3. 1985.

I. This license is effective as of the date of issuance and shall expire

- at midnight on April 13, 2013.

FOR THE NUCLEAR REGULATORY COMMISSION

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Thomas E. Murley, Director Office of Nuclear Reactor Regulation Attachments:-

1. Attachment 1

2. Attachment 2 l 3.- Appendix A - Technical-Specifications'(NUREG-1357).

',' 4. Appendix B Environmental' .

Protection. Plan Date of Issuance: April 21, 1989 fd jft a

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H. This license supersedes Facility Operating License No. NPF-36, dated July 3, 1985.

I. This license is effective as of the date of issuance and shall expire at midnight on April 13, 2013.

FOR THE NUCLEAR REGULATORY COMMISSION Thomas E. Murley, Director i Office of Nuclear Reactor Regulation Attachments:

1. Attachment 1

2. Attachment 2

3. Appendix A - Technical Specifications (NUREG-1357)

4. Appendix B - Environmental Protection Plan Date of Issuance:

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H. This license supersedes Facility Operating License No. NPF-36, dated July 3, 1985.

I. This license is effective as of the date of issuance and chall expire at midnight on April 13, 2013.

FOR THE NUCLEAR REGULATORY COMMISSION A

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Thomas E. Murley, Director Office of Nuclear Reactor Regulation Attachments:

1. Attachment 1

2. Attachment 2

3. Appendix A - Technical Specifications (NUREG-1357)

4. Appendix B - Environmental Protection Plan Date of Issuance: ' April 21, 1989

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ATTACHMENT 1 Changes to the Remote Shutdown Panel (RSp) (Section 7.4.3 SSER3 SSER4)

The licensee shall provide the following additional instrumentation and controls to meet the single-failure criterion.

(1) Residual Heat Removal (RHR) system--An RHR A flow indicator will be provided on a local panel.

(2) Reactor Building Service Water (RBSW) system--Provide RBSW train A flow indication at a local panel.

(3) Spent fuel pool cooling--Provide pump controls for the A spent fuel pool cooling pump on a local panel.

(4) Miscellaneous local indicators--Provide a Division 2 indicator.for Raacto- Pressure Vessel (RPV) pressure and Division 1 and 2 indicators for suppression pool temperature.

The following remote shutdown panel instruments, including their sensors, power supplies, displays and associated connections shall meet the quality standards applicable to Quality Assurance Category I equipment.

(1) RHR B flow (2) RPV level (3) RPV pressure (4) service water B header pressure (5) suppression pool temperatures (6) suppression pool level (7) Reactor Core Isolation Cooling (RCIC) i: low (8) RCIC turbine speed (9) SRV N2 pressure

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ATTACHMENT 2

I Emergency Diesel Generator (EDG) 101, 102, and 103 License Conditions A.. General Changes L to the maintenance and surveillance program for- the TDI diesel engines, as identified in NUREG-1216 Section 2.3.." Maintenance /

Surveillance Program" shall be subject to the provisions of 10 CFR 50.59.

The frequency ~of the major engine overhauls referred to in the license conditions below shall be consistent with Section IV.1, " Overhaul Frequency" in Revision 2 of Appendix ~ II of the Design Review / Quality

- Revalidation report which was transmitted by letter dated May 1, 1986, from J. George, Owners Group, to H. Denton, NRC.

B. C_ylinder Block-

. The following inspection requirements are as defined in Failure Analysis Associates, Inc. (FaAA) report entitled, " Design Review of TDI R-4 and RV-4 Series Emergency Diesel Generator Cylinder Blocks" (FaAA report No.

4 FaAA-84-9-11.1) and dated December 1984. The inspection intervals (i.e.,

- frequency) shall not exceed the intervals calculated using the cumulative damage index model in the subject FaAA report. Liquid-penetrant testing or a similarly sensitive nondestructive testing technique should be used to detect cracking, and eddy current should be used as appropriate to L - determine the crack depth.

1. EDG.101,102 and 103 cylinder block top surface shall be inspected for'" ligament" cracks, " stud-to-stud" cracks and " stud-to-end" cracks at each major engine overhaul.

2., The licensee shall perform eddy current testing or boroscopic examination between adjacent cylinder heads after any operation of EDG;101 or 102 at greater than 1750 KW.

3. EDG 101 and 102 cylinder block top surface shall be partially inspected at each refueling outage to detennine whether or not cracks have initiated.on the top surface exposed by the removal of two cylinder heads. This process should be repeated over four refueling outages until the entire block top has been inspected.

4. If any inspection reveals cracks in the cylinder blocks between stud holes of adjacent cylinders (" stud-to-stud" cracks) or

" stud-to-end" cracks, this condition shall be reported promptly to the NRC staff and the affected engine shall be considered inoperable. The engine shall not be restored to " operable" status until the proposed disposition and/or corrective actions have been approved by the NRC staff.

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(Attachment 2) 5. In adoition to the above, the following license conditions are applicable during the first fuel cycle and through the first refueling outage.

a. During any period of continuous operation following automatic diesel generator initiation, the licensee shall perform daily visual inspections of the area between adjacent cylinder heads and the general block top. The licensee shall also perform visual inspections of the same areas under intense light during the monthly surveillance testing. This condition is applicable to EDGs 101, 102, and 103.

b. Following any loss of offsite power event which results in the automatic starting of any EDG, the licensee shall inspect the top surface of the block exposed by the removal of two appropriate cylinder heads from each of the three EDG engines.

Inspections shall be by liquid penetrant, with eddy current for any identified cracks, to determine the presence of new cracks and the depth of any new or old cracks.

c. The licensee shall perform a liquid penetrant and, as appropriate, UT inspection of the cylinder liner landing at any time a cylinder liner is removed for any other reason. This condition is applicable to EDGs 101, 102 and 103.

d. Examination of the block top between cylinder heads as required by item 2 above will be performed by eddy current inspection only.

C. Cylinder Block Cam Gallery Cracks Cam gallery saddle locations nos. 2 and 8 on the EDG 101 and 102 blocks will be inspectad by LILCO every 3 months, or after 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> of operation at or above a load of 1800 KW, whichever comes first. These inspections shall be performed from the time the EDGs are initially placed in operation for emergency standby service until the first refueling outage. Liquid penetrant examinations of the nos. 2 and 8 saddle locations shall be performed to monitor the length of the cracks, followed by TSI depth gauge measurements of the cracks to monitor their depth.

D. Crankshafts

1. EDGs 101,102, and 103 shall not be operated at power levels greater than 3400 KW*, as indicated by the installed power meter in the Shoreham control room. If an engine is operated at a power level greater than 3400 KW, for any time, (1) the engine shall be removed from service as soon as is safely possible, (2) the engine shall be declared inoperable, and (3) the crankshaft shall be inspected in accordance with the provisions of conditions D.4 and 0.5.

Momentary transients (not exceeding 5 sec) that result from changing bus loads need not be considered as an overload. 4 i

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2. For the first fuel cycle EDGs 101, 102, and 103 are each limited to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of cumulative operation at loads between 3300 and 3400 KW, {

in addition to the monthly surveillance tests. If this limit is '

exceeded, (1) the engine shall be removed from service as soon as is safely possible, (2) the engine shall be declared inoperable, and (3) the crtakshaft shall be inspected in accordance with the provisions of conditions D.4 and D.5 below.

3. Following the satisfactory inspections of the EDGs 101, 102 and 103

-crankshafts at the first refueling outage, if the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ** cumulative load limit of 3300 to 3400 KW, described in D.2 above is exceeded, a crankshaft inspection pursuant to items D.4 and D.5 shall be performed at the next refueling outage.

4. At each refueling. outage, the licensee shall measure and record hot and cold web deflection readings on each of the diesels.

5. At the first refueling outage, the licensee shall inspect the crankpin journals numbered 5, 6 and 7 and the main bearing journals between crankpins 5, 6 and 7, including the associated oil holes and fillets in all of these journals, using LP and ET as appropriate.

This condition is applicable to EDGs 101, 102 and 103.

6. During the second and third refueling outages, inspect the fillets and oil holes of two of the three most heavily loaded crankpin journals in each crankshaft, using liquid penetrant. Indications found should also be evaluated with eddy current methods as appropriate. '

7. Following the third refueling outage, inspect the fillets and oil holes of the (a) three most heavily loaded crankpin journals (Ncs.

5, 6, and 7) and (b) the main jcurnals located between crankpin journals 5, 6 and 7, at the refueling outage corresponding to an approximately 5 year interval between crankshaf t inspections.

E. Cylinder Heads

1. Cylinder heads purchased as replacements will be inspected in accordance with paragraphs (a) and (b) are subject to paragraph (c) bclow.

(a) Perform an ultrasonic inspection of the firedeck of all the cylinder heads at six locations to verify that the minimum thickness requirements of .400 inch is met. The six locations are specified as follows:

(i) The first location is on the firedeck between the exhaust gas ports approximately directly between the two exhaust gas ports.

If there are multiple overload events since the previous crankshaft inspection then the time criterion applies to the total accumulated time in the load range.

.c 4' (Attachment 2) (ii) The second location is approximately 1 1/2 inches from the first location in a direction toward the exhaust side of the cylinder head.

(iii) The third location 1s approximately 2 inches from the first l: location in a direction toward the intake side of the cylinder head.

(iv) The fourth location is approximately midway between the injector port and the exhaust port on the governor side of the head.

(v) The fifth location is approximately directly between the two intake gas ports.

(vi) The sixth location is approximately midway between the injector and exhaust port on the flywheel side of the head.

Cylinder heads not meeting this thickrest requirement shall not be used.

(b) Perform surface inspection (either liquid penetrant or magnetic particle) of intake and exhaust valve seats and the firedeck area between the exhaust valves to verify that they are free of unacceptable surface defects. Cylinder heads with unacceptable and irreparable surface defects shall not be used. Acceptance criteria are as specified in ASME III, paragraph NB-5350.

(c) Ascertain from shop records or otherwise whether any heads have through-wall weld repairs of the firedeck where the repair is performed from one side only. Any such 'neads shall not be used.

2. Any head which leaks due to a crack shall be replaced.

3. The air roll test described below shall be performed as specified except when the plant is already in an Action St_atement of Technical Specification 3/4.8.1, " Electric Power Systems, A.C. Sources:

The licensee shall bar the engines over with the barring device and roll the engines over with the airstart system, with the cylincer stopcocks open, prior to each planned start, unless that start occurs within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of a shutdown. In addition, after engine operation, the engines shall be barred and rolled over with the airstart system and with the cylinder stopcocks open after 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, but no more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after engine shutdown and then rolled over once again approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after each shutdown. In the event an engine is removed from service for any reason other than the rolling over procedure prior to expiration of the 8-hour or 24-hour periods noted above, that engine need not be rolled over while it is out of service. The licensee shall air roll the engine over with the stopcocks open at the time it is returned to service. The

E L. j (Attachment 2) ,

origin of any water detected in the cylinder must be determined and any cylinder head which leaks due to a crack shall be replaced. The 6bove post operational air roll test may be discontinued following the first refueling outag3 subject to the following conditions:

(a)' All cylinder heads are Group III heads (i.e., cast after September 1980).

(b) Ouality revalidation inspections, as required by El above, have been completed for all cylinder heads.

(c) Group III heads continue to der'. strate leak free performance.

This should be confirmed with Tb1 prior to deleting air roll tests.

F. Turbocharger

1. -The turbocharger thrust bearings shall be visually inspected for excessive wear after 40 non-prelubed starts since the previous visual inspection.

2. Turbocharger rotor axial clearance shall be measured at each refueling outage to verify compliance with TDI/Elliott specifications. In addition, thrust bearing measurements shall be compared with measurements taken previously to determine a need for further inspection or corrective action.

3. Spectrographic and ferrographic engine oil analysis shall be performed quarterly to provide early evidence of bearing degradation. Particular attention shall be paid to copper level and particulate size which could signify thrust bearing degradation.

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4. The nozzle ring components and inlet guide vanes shall be visually inspected for missing parts or parts showing distress on a one-turbocharger-per-refueling-outage basis. In addition, these inspections shall be performed for all turbocharger at each turbocharger o'verhaul (i.e., at approximately 5-year intervals). If any missing parts or distress is noted, the entire ring assembly shall be replaced and the subject turbocharger ball be reinspected at the next refueling outage.

G. EDG 3300 KW Alarm The licensee shall install a distinctive visual and audible alarm for each diesel generator in the main control room that will be set no higher than 3300 KW for operation.

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g yt (Attachment 2) H.- Inspection Results and Restart If any of the engine inspections required by paragraphs B, C and D above identify a degraded component condition, the associated engine shall be declared inoperable until the results of the inspection and further analyses by the licensee of the degraded condition have been reviewed, and further operation of the engine has been approved by the NRC staff.

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