ML20207B734

Forwards Correction of Typo in TS Table 3.3.6.1-1 for Plant, Unit 1

ML20207B734
Person / Time
Site:	Perry
Issue date:	05/26/1999
From:	Pickett D NRC (Affiliation Not Assigned)
To:	Myers L CENTERIOR ENERGY
References
TAC-MA5062, NUDOCS 9906020083
Download: ML20207B734 (4)

Text

.

} e atto g t UNITED STATES s* j NUCLEAR REGULATORY COMMISSION

, g WASHINGTON, D.C. 2050641001 May 26, 1999

p. . . . . ,p Mr. Lew W. Myers Vice President - Nuclear, Perry FirstEnergy Nuclear Operating Company P.O. Box 97, A200 Perry, OH 44081

SUBJECT:

CORRECTION OF TYPOGRAPHICAL ERRORS IN TECHNICAL SPECIFICATION TABLE 3.3.6.1 PERRY NUCLEAR POWER PLANT, UNIT 1 (TAC NO. MA5062)

Your letter of March 15,1999 (PY-CEl/NRR-2373L), requests revisions to Technical Specification (TS) Table 3.3.6.1-1, " Primary Containment and Drywell isolation Instrumentation,"

pursuant to 10 CFR 50.90. In your letter, you state that the proposed changes will correct typographical errors that have existed since the staff approved the conversion to the improved BWR/6 Technical Specifications (ITS) on June 23,1995. Specifically, TS Table 3.3.6.1-1, page 6 of 6, Function 5.c, " Reactor Vessel Steam Dome Pressure - High," lists surveillance requirements (SRs) that are not valid numbers and, therefore, do not coincide with valid test requirements.

The staff has reviewed the documentation associated with the Perry conversion to the ITS and has concluded that the typographical errors were inadvertently introduced during the review process and were not reviewed by the staff. The staff makes this finding based on the following:

The original application for the ITS, dated December 16,1993 (PY-CEl/NRR-1732L),

included marked-up pages to the draft ITS. TS Table 3.3.6.1-1, page 6 of 6, referenced the appropriate SRs for Function 5.c.

Supplemental letter dated November 7,1994 (PY-CEl/NRR-1880L), included new marked-up pages to the draft ITS. Again, TS Table 3.3.6.1-1, page 6 of 6, referenced the appropriate SRs for Function 5.c.

A second supplemental letter also dated November 7,1994 (PY-CEl/NRR-1881L),

included a clean, retyped version of the proposed ITS. The invalid SR numbers were inadvertently introduced in the enclosure to this letter. SRs 3.3.6.1.3, 3.3.6.1.4, and 3.3.6.1.5 were changed to 3.6.1.1.3,3.6.1.1.4, and 3.6.1.1.5, respectively.

License Amendment No. 69, issued on June 23,1995, included the retyped version of the ITS as received from the licensee as an enclosure. Thus, the typographical errors described above were formally issued in TS Table 3.3.6.1-1.

The staff has determined that the typographical errors were inadvertently introduced in a specific license amendment, and that the changes were not addressed in the notice to the public nor reviewed by the staff. Under these limited circumstances, the changes that introduced the 9906020083 990526 fDR ADOCK 05000440 PDR i . . _ . __ _ _ .

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, L. Myers -2' typographical errors were not a proper amendment to the license because they were neither l - addressed in the notice nor reviewed, and correction of the typographical errors is not a i "

change" to the TS, Consistent with NRC policy, the typographical errors may be corrected by letter in lieu of a license amendment pursuant to 10 CFR 50.90.

! Accordingly, TS Table 3.3.6.1-1, page 6 of 6 is being reissued and is enclosed for your

! information.'

r

! Sincerely,

' Original signed by l

Doug' .M.'. Pickett, Senior Project Manager, Section 2 Project Directorate ill l' .

' Division of Licensing Project Management Office of Nuclear Reactor Regulation

. Docket No. 50-440

Enclosure:

As stated cc: See next page I

w PUBLIC PD lll-3 r/f GGrant, Rlli WBeckner, TSB CThomas/AMendiola

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l , DOCUMENT NAME: G:\PD3-3\ PERRY \A5062LTR.WPD l To receive a copy of this document, Indicate in the box: 'C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy ]

OFFICE PM.lRQP E LA

LPD3 E OGC ,3 SC:LPD3-l NAME DPiBliett EBarnhill 9/y Q'WlV A,6 l DATE 05/17/99 05/l7/99 05/ O /99 Off/fJ/99 g OFFICIAL RECORD COPY j j nCon44 l

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L. Myers Perry Nuclear Power Plant, Units 1 and 2 FirstEnergy Nuclear Operating Company cc:

James R. Williams Mary E. O'Reilly Chief of Staff FirstEnergy Corporation Ohio Emergency Management Agency 76 South Main St. 2855 West Dublin Granville Road Akron, OH 44308 Columbus, OH 43'235-7150 Resident inspector's Office Mayor, Village of Perry U.S. Nuclear Regulatory Commission P.O. Box 100 P.O. Box 331 Perry, OH 44081-0100 Perry, OH 44081-0331 Radiological Health Program Regional Administrator, Region lli Ohio Department of Health U.S. Nuclear Regulatory Commission P.O. Box 118 801 Warrenville Road Columbus, OH 43266-0118 Lisle, IL 60532-4531 Ohio Environmental Protection Sue Hiatt - Agency OCRE Interim Representative DERR-Compliance Unit 8275 Munson ATTN: Mr. Zack A. Clayton Mentor, OH 44060 P.O. Box 1049 Columbus, OH 43266-0149 Henry L. Hegrat Regulatory Affairs Manager Chairman FirstEnergy Nuclear Operating Company Perry Township Board of Trustees Perry Nuclear Power Plant 3750 Center Road, Box 65 P.O. Box 97, A210 Perry, OH 44081 Perry, OH 44081 State of Ohio William R. Kanda, Jr., Plant Manager Public Utilities Commission FirstEnergy Nuclear Operating Company East Broad Street Peny Nuclear Power Plant Columbus, OH 43266-0573 P.O. Box 97, SB306 Perry, OH 44081 Mayor, Village of North Perry North Perry Village Hall -

4778 Lockwood Road North Perry Village, OH 44081 Donna Owens, Director Ohio Department of Commerce Division ofIndustrial Compliance Bureau of Operations & Maintenance 6606 Tussing Road P. O. Box 4009 Reynoldsburg, OH 43068-9009

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'o Primary Containment and Drywell Isolation Instrumentation l 3.3.6.1 Table 3.3.6.1 1 page 6 of 6) l Primary Containment and Drywel(l Isolation Instrunentation

\PPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS TRIP SYSTEM ACTION C.1 REQUIREMENTS VALUE

5. 'RHR System Isolation

a. RNR Equipment Area 2I 'I,3I 'I 1 per area F SR 3.3.6.1.1 s 159.9'F Anblent SR 3.3.6.1.4 Tenperature - H1ph SR 3.3.6.1.5 SR 3.3.6.1.7

b. Reactor vessel Water 1,2I 'I,3I8I 2 F SR 3.3.6.1.1 a 177.1 Level Low, Level 3 SR 3.3.6.1.2 inches l SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5 2I 'I,3 I'3,4, IU 2 J SR 3.3.6.1.1 a 177.1 l 5 SR 3.3.6.1.2 inches SR 3.3.6.1.3 4 SR 3.3.6.1.4  :

SR 3.3.6.1.5

c. Reactor Vessel Steam 1,2,3 2 F SR 3.3.6.1.1 s 150 psig Dome Pressure - High SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5

d. Drywell Pressure - High 1,2,3 2 F SR 3.3.6.1.1 s 1.88 psig SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5

e. Manual Initiation 1,2,3 2 G SR 3.3.6.1.5 NA (e) With reactor vessel steam dome pressure less than the RNR cut in permissive pressure.

(f) Only one trip system required in MODES 4 and 5 with R9R Shutdown Cooling System integrity maintained. l (g) With reactor vessel steam dome pressure greater than or equal to the RHR cut in permissive pressure.

l l

PERRY - UNIT 1 3.3-59 Amendment No. 85 Corrected May 26, 1999