ML18005A781

Forwards Quarterly Rept of Changes to Procedures or Plant Mods Which Change Plant as Described in FSAR for Oct 1988 to 890112.No Tests or Experiments Identified During Interval Which Are Not Described in FSAR

ML18005A781
Person / Time
Site:	Harris
Issue date:	02/16/1989
From:	Watson R CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HO-890014-(O), NUDOCS 8902230069
Download: ML18005A781 (6)

Text

i ACCELERATED D+RIBt'TlON DEMONISTTIO.'i SYZTEk REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8902230069 DOC.DATE: 89/02/16 NOTARIZED: NO FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME AUTHOR AFFILIATION WATSON,R.A.

Carolina Power

& Light Co.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

DOCKET 05000400 R

SUBJECT:

Forwards quarterly rept of changes to procedures or plant mods which change plant as described in FSAR.

I DISTRIBUTION,CODE:

IE47D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: 50.59 Annual Report of Changes, Tests or Experime ts Made W/out Approv NOTES:Application for permit renewal filed.

05000400 RECIPIENT ID CODE/NAME PD2-1 LA BECKER,D INTERNAL: ACRS AEOD/DSP/TPAB NRR/DOEA/EAB 11 NUDOCS-ABSTRACT RGN2 FILE 01 EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1

0 1

0 6

6 1

1 1

1 1

1 1

1 1

1 1

1 RECIPIENT ID CODE/NAME PD2-1 PD AEOD/DOA NRR/DLPQ/HFB 10 NRR/DREP RPB 10 0

NRC PDR COPIES LTTR ENCL 5

5 1

1 1,

1 2

2 1

1 1

1 NOTE 'IO ALL "RIDS" RECIPIENTS:

PLEASE HELP US 'IO REDUCE %APK!

COÃZACr 'IHE DOCUMENI'XÃIBOLDESK, RCCM Pl-37 (EXT. 20079) K) EXJKCNATE YOUR mK FRY DISTRZKlTION LISTS H)R DCjCUMEÃIS YOU DON'T NEED'OTAL NUMBER OF COPIES REQUIRED:

LTTR 25 ENCL 23

emL Carolina Powe~

8 ugh! Cornpar y HARRIS NUCLEAR PROJECT P.O.

Box 165 New Hill, NC 27562 FE8 16 198'ile Number'SHF/10-13510C Letter Number.'H0-890014 (0) 10CFR50.59 U.S. Nuclear Regulatory Commission ATTN:

NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 UARTERLY REPORT IN ACCORDANCE WITH 10CFR50.59 Gentlemen.'n accordance with 10CFR50.59 and CPGL Letter (NLS-86-454) of commitment dated December 9,

1986, the following report is submitted for the period of October 1,

1988, through January 12, 1989.

This report contains brief summaries of changes to procedures and/or plant modifications, which change the plant as it is described in the FSAR.

There were no tests or experiments conducted during this

interval, which are not described in the FSAR which require reporting in this report.

CP&L committed in letter NLS-86-454 dated December 9, 1986, that for a period of two years from issuance of the full-power license (January 12, 1986), quarterly reports would be filed with the NRC within 60 days after the close of the reporting period.

With the issuance of this report that commitment has been fulfilled.

Future reports will be submitted annually in accordance with 10CFR50.59.

OOD w~A wOQ.

NO OO o IA SO WC&

On OQ RCE OY RQQ'ery truly yours, R. A. Watson Vice President Harris Nuclear Project MGW:acm Enclosure cc.'Mr. W. H. Bradford (NRC SHNPP)

Mr. M. L. Ernst (NRC " RII)

MEM/HO-8900140/Page 1/OSl

CHANGE TO FACILITY AS DESCRIBED IN THE FSAR Title'.

PCR-002551, Spent Resin Storage and Transfer System Modification Functional Summar This plant modification replaced the spent resin transfer pumps with larger capacity pumps.

The capacity of the pumps were increased from 35 gpm to 100 gpm.

With the larger capacity

pumps, the restoration of redundant operation has been accomplished by separating the controls in the Waste Processing Control Room to permit single pump operation.

(The redundancy was eliminated during initial plant start-up due to insufficient flow rate.)

Miniflow recirculation lines on the pumps suction and discharge line were removed and two manual isolation valves have been installed on the transfer pumps common suction line.

The resin samplers were relocated to elevation 261'previously near the decanting tank) to the spent resin transfer pump discharge piping on elevation 211'.

This modification will reduce radiation hot spots by isolating infrequently used portions of the system such as recirculation lines and by increasing the system's flush capabilities.

The design flow rate of increased from 35 gpm to the common line of resin entering the line when it the spent resin transfer pumps will be 100 pgm.

Isolation valves installed on transfer pumps will prevent resin from is not in use.

Spent resin transfer pump redundancy has been restored as a result of the increased pump capacity since a single pump will be able to achieve the necessary flow rate.

The relocation of the resin samplers will allow the capability to sample the contents of either the high or low activity spent resin storage tanks while they are in 'the recirculation mode or sample the contents of the tank in the transfer mode.

This change does not increase the probability or consequences of analyzed accidents, nor introduce a different type of accident or equipment malfunction than already evaluated in the FSAR.

Thus, no unreviewed safety question exists.

FSAR

Reference:

Figure 11.2.2-03 MEM/HO-8900140/Page 2/OS1

CHANGE TO FACILITY AS DESCRIBED IN THE FSAR Title'.

PCR-000851, Disconnection of Temporary Condensate Pump High Differential Pressure Switches Functional Summar This plant modification disconnects high differential pressure switches PDS-1923A and PDS-1923B located across temporary suction strainers in the condensate lines upstream from each condensate pump.

These switches were installed as temporary equipment to protect the condensate pumps during initial start-up/testing.

The switches are being disconnected to prevent unnecessary trips of

'he condensate pumps.

Switches PDS-1923A and PDS-1923B served only a temporary function of protecting the condensate pump during initial start-up/testing.

The instrumentation can be disconnected without affecting the operation of the Condensate and Feedwater System.

Disconnection of these switches will decrease the possibility of a pump trip due to spurious actuation or mechanical failure of the instrument, thus making operation of the system more reliable.

This change does not increase the probability or consequences of analyzed accidents, nor introduce a different type of accident or equipment malfunction than already evaluated in the FSAR.

Thus, no unreviewed safety question exists.

FSAR

Reference:

Figure 10.1.0-4 MEM/H0-8900140/Page 3/OS1

CHANGE TO FACILITY AS DESCRIBED IN THE FSAR

Title:

PCR-000558, Reactor Coolant Drain Tank Pump (RCDTP)

Breakers Functional Summar This plant modification upsized the reactor coolant drain tank pump breakers in MCC 1D11 and 1E11.

This new design was required because the pump motors are 33 HP and the'riginal breakers were sized for 20 HP.

This modification necessitated moving the existing breakers to spare locations in juxtapositional stacks to create sufficient space for the larger size breakers.

Reviews were conducted to confirm that the additional load on the AC power system resulting from the larger breakers does not overload, the bus.

Design criteria was reviewed to verify that existing cable size was adequate and that containment electrical penetrations were properly protected.

By upsizing the RCDTP breakers the potential for an electrical failure has been reduced.

Based on the evaluations performed it is concluded that the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR is not increased.

In

addition, the possibility for an accident or malfunction of a

different type than -any evaluated previously in the FSAR has not been created.

Thus, no unreviewed safety question exists.

FSAR

Reference:

Table 16.3-6 MEM/H0-8900140/Page 4/OS1

CHANGE TO FACILITY AS DESCRIBED IN THE FSAR

Title:

PCR-002038 6 PCR-003547, Radwaste Demineralizer Skid Functional Summar Th'ant modification added piping and valves in the liquid 1s p

f a waste processing system (LWPS) to allow for the future hookup o

a vendor demineralizer system.

The vendor system is being instal ed as an alternate means of processing liquid wastes.

The existing LWPS will be maintained in an operable condition to meet FSAR and Technical Specification requirements.

The piping and valves added by this modification are connected to the existing liquid waste processing system using the original codes and standards.

The new piping is located in the same area as the existing piping', therefore, the failure of the piping or valves would not affect the safety of the plant.

Any liquid released due to the failure of the new items would be contained within the Waste Processing Building.

These scenarios are covered b

the scope of the analysis provided in Section 15.7.2 of the FSAR which assumes complete failure of all nonsafety and nonseismic category 1 equipment in the LWPS.

Therefore, the addition of the piping and valves will not increase the probability or consequences of an accident or malfunction of equipment important to safety previously analyzed; create the ossibility of an accident or malfunction of equipment important posse to safety not previously analyzed; or impact the margin of a

y

~

~

of safet as defined in any Technical Specification bases.

Thus, no unreviewed safety question exists.

FSAR

References:

Sections 11.2, 11.4 MEM/H0-8900140/Page 5/OS1,